{{Adams | number = ML16088A332 | issue date = 03/23/2016 | title = License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 2 of 9) | author name = | author affiliation = Entergy Operations, Inc | addressee name = | addressee affiliation = NRC/NRR | docket = 05000382 | license number = NPF-038 | contact person = | case reference number = W3F1-2016-0012 | package number = ML16088A324 | document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50 | page count = 1006 | project = | stage = Other }}

Text

{{#Wiki_filter:LICENSE RENEWAL APPLICATION WATERFORD STEAM ELECTRIC STATION, UNIT 3 FACILITY OPERATING LICENSE NPF-38 MARCH 2016 ( "" .. PREFACE Waterford Steam Electric Station, Unit 3 . License Renewal Application .The following describes the information location, layout, and editorial conventions in the Waterford steam Electric Station, Unit 3 (Waterford 3 or WF3) License Renewal Application (LRA) (hereinafter referred to as "this application" or "the application"). Abbreviated names and acronyms used throughout the application are defined at the end of this preface. Commonly understood terms (such as U.S.) and terms used only in referenced document numbers may not be identified in this table. Regulatory documents such as NUREG-1801, Generic Aging Lessons Learned (GALL) Report, and 10 CFR 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants, may be referred to by the documel')t number, i.e., NUREG-1801 and 1 O CFR 54, respectively. References to tre FSAR are to the updated Waterford 3 Final Safety Analysis Report, Revision 308. Section 1 provides administrative inforrnation required by 1 O CFR 54.17 and 1 O CFR 54.19. Section 2 describes and justifies the methods used to determine the systems and structures within the scope of license renewal and the structures and components subject to aging management review. The results of the system and structure scoping are provided in Tables 2.2-1 through 2.2-5. Tables 2.2-1, 2.2-2 and 2.2-4 list mechanical systems, electrical and instrumentation and controls (l&C) systems, and structures, respectively, within the scope of . . license renewal. Tables 2.2-3 and 2.2-5 list the systems and stn.ictures, respectively, not within *the scope of license renewal. Section 2* also provides descriptions of in-scope systems and structures and their intended functions with tables* identifying components and commodities requfring aging management review and their component intended functions. References are provided to the results of the aging management reviews in Section 3.

The descriptions of systems in Section 2 identify license renewal drawings that depict the components subject to . aging management review for mechanical systems. The drawings are provided in a separate
submittal. Section 3 describes the results of aging management reviews of mechanical, electrical and structural components*requiring agir:ig management review. Section 3 is divided into sections that address (1) the reactor vessel, internals, and reactor coolant system, (2) engineered_ safety features, (3) auxiliary systems, (4) steam and power conversion systems, (5) containments, structures and component supports, and (6) electrical and l&C. The tables in Section 3 provide a summary of information concerning aging effects requiring management and applicable aging management prpgrams for component and commodity groups subject to aging management review. The information presented in the tables is based on the format and content of NUREG-1800, Standard Review Plan [SRP] for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U.S. Nuclear Regulatory Commission (NRG), December 2010, as modified by applicable NRG Interim Staff Guidance (ISG) documents for license renewal. The tables include comparisons with the evaluations documented in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, U.S. NRG, December 2010, as modified by applicable NRG ISG documents for license renewal.

Waterford Steam Electric Station, Unit 3 License Renewal Application Section 4 addresses time-limited aging analyses, as defined by 1 O CFR 54.3. It includes identification of the component or subject and an explanation of the time-dependent aspects of the calculation or analysis. Section 4 demonstrates whether (1) the analyses remain valid for the period of extended operation, (2) the analyses have been projected to the end of the period of extended operation, or (3) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation. Section 4 also documents the determination that no plant-specific exemptions granted pursuant to 1 O CFR 50: 12 that are based on time-limited aging analyses as defined in 10 CFR 54.3 will remain in effect. Appendix A, Final Safety Analysis Report Supplement; provides a summary description of programs and activities for managing the effects of aging for the period of extended operation. A summary description of the evaluation of time-limited aging analyses for the period of extended operation is also included. Following issuance of the renewed license, the material contained in this appendix will be incorporated into the updated.FSAR. The information in Appendix A fulfills the requirements in 10 CFR 54.21 (d). Table 3.0-1, "FSAR Supplement for Aging Management of Applicable Systems," from Revision 2 of NUREG-1800 was used as guidance.for the content of the applicable management program summaries. Appendix B; Aging Management Programs and Activities, describes aging management programs and activities that will manage aging effects on components and structures within the scope of license renewal slich that they will continue to perform their intended functions consistent with the current licensing basis for the period of extended .operation. Appendix B contains a comparison of site programs to the programs* evaluated in NUREG-1801. *The information in Section 2, Section 3, and Appendix B fulfills the*Tequirements of 10 CFR 54.21 (a). . \. Appendix C, Response to Selected Applicant/Licensee.Action Items for Inspection and Evaluation Guidelines for PWR Internals, provides the Waterford 3 response to applicant action items identified in the Nuclear Regulatory Commission (NRC) safety evaluation (SE) of MRP-227, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines." Appendix D, Technical Specification Changes, documents that no technical specification changes are necessary to manage the effects of aging during the peribd of extended operation. The information in Appendix D fulfills the requirements in 1 O CFR 54.22. Appendix E is the environmental information that fulfills the requirements of 1 O CFR 54.23 and 10 CFR 51.53(c). ii \ ) Abbreviation or Acronym AC ACC ACI ACSR ADG AE AEM Al AMP AMR ANSI ANP ARM ARR AS ASME ASTM ATWS BAM BO BM BTP BWR c CAP CASS Waterford Steam Electric Station, Unit 3 License Renewal Application ABBREVIATIONS AND ACRONYMS Description alternating current auxiliary component cooling water American Concrete Institute aluminum conductor steel reinforced auxiliary diesel generator air evacuation aging effect/mechanism aluminum aging management program aging management review American National Standards Institute annulus negative pressure area radiation monitoring airborne radioactivity removal auxiliary steam American Society of Mechanical Engineers American Society for Testing and Materials anticipated transient without scram boric acid makeup blowdown boron management Branch Technical Position boiling water reactor centigrade containment atmosphere purge cast austenitic stainless steel iii Abbreviation or Acronym CAR CB cc ccs ccws CD CE CEA CED CEDM CF CFR Cll CLB CMU cs CSP Cu CUF CVAS eve CVR cw DC OCT EAF Description Waterford Steam Electric Station, Unit 3 License Renewal Application containment atmosphere release containment building component cooling water containment cooling HVAC system component cooling water system condensate conducts electricity, Combustion Engineering control element assembly control element drive control element drive mechanisms chemical feed, chemistry factor Code of Federal Regulations containment inservice inspection current licensing basis condensate makeup and storage containment spray, core shroud condensate storage pool copper cumulative usage factor controlled ventilation area system chemical and volume control containment vacuum relief circulating water direct current dry cooling tower reference temperature change environmentally assisted fatigue iv Abbreviation or Acronym EBA ECCS EOG EFPY EFW EN EPRI .' , . EQ ESF ext FAC FB FC FD Fen FHS FLB FP FS FSAR ft-lb FW GALL GL GSI GWM Description Waterford Steam Electric Station, Unit 3 License Renewal Application emergency breathing air emergency core cooling system emergency diesel generator

effective full power years emergency feedwater enclosure protection Electric Power*Research Institute environmental qualification engineered safety feature external flow-accelerated corrosion fire barrier flow control flow distribution environmentally assisted fatigue correction factor fuel handling and storage flood barrier fire protection fuel pool cooling and purification Final Safety Analysis Report foot-pound main feedwater Generic Aging Lessons Learned [NUREG-1801 report] Generic Letter Generic Safety Issue gaseous .waste management v Abbreviation or Acronym H&V HOPE HELB HEPA HPSI HRA HS HVAC HVC HVD HVF HVR HVT l&C IA ICI ICl/HJTC-CET ILRT IN INPO int IPA ISG ISi ksi KV or kV Description heating and ventilation high density polyethylene high-energy line break high efficiency particulate air Waterford Steam Electric Station, Unit 3 License Renewal Application high pressure safety injection hydrogen recombiners and analyzers heat sink heating, ventilation, and air conditioning control room heating, ventilation, and air conditioning hot machine shop and decontamination facility ventilation fuel handling building HVAC reactor auxiliary building HVAC turbine building ventilation instrumentation and control instrument air incore instrumentation I Cl/heated junction thermocouple-core exit thermocouples integrated leakage rate test insulation; [NRG] Information Notice Institute of Nuclear Power Operations internal integrated plant assessment Interim Staff Guidance inservice inspection kilo-pounds per square inch kilo-volt vi

'-._ _ __,Jr Abbreviation or Acronym LAS LLRT LOCA LPSI LR LRA LREH LRT MB MEB MeV MIC MS MSIV MSL MSLB MWe MWt NA n/cm2 NOE NEI NFPA NG Ni NPIS NPS. Description

low alloy steel local leakage rate test . loss of coolant accident Waterford Steam Electric Station, Unit 3 License Renewal Application low pressure safety injection system license renewal license renewal. application License Renewal Electrical Handbook leak rate testing missile barrier metal enclosed bus million electron-volts microbiologically induced corrosion main steam; Mississippi main steam isolation valve mean sea level * , main steam line break" megawatts-electrical megawatts-thermal neutron absorption; not applicable neutrons per square centimeter nondestructive examination Nuclear Energy Institute National Fire Protection Association nitrogen nickel nuclear plant island structure nominal pipe size vii Abbreviation or Acronym NRC NSSS OBE OE OVHLL PB PCSR pH PH PM PMP PMU PRM PSL PSPM P-T PVC PW PWR PWST QA RAB RC RCC RCP Waterford Steam Electric Station, Unit 3 Description Nuclear Regulatory Commission r nuclear steam supply system operating basis earthquake operating experience Overhead Heavy Load and Light Load pressure boundary permanent cavity seal ring potential of hydrogen precipitation-hardened preventive maintenance probabl_e maximum precipitation primary makeup * -process radiation monitoring primary sampling License Renewal Application .. _ / periodic surveillance and preventive maintenance pressure-temperature polyvinyl chloride potable water pressurized water reactor primary water storage tank quality assurance reactor auxiliary building reactor coolant reactor cavity cooling reactor coolant pump viii Abbreviation or Acronym RCPB RCS RG RPV RTNDT RWSP SA *s&PC SBO SBV SCBA sec SE SER SG SI SIS
SIT SNS S02 SP SRE SRP SS SSC SSR STAMR svs Description Waterford Steam Electric Station, Unit 3 License Renewal Application reactor coolant pressure boundary reactor coolant system Regulatory Guide
reactor pressure vessel (synonymous with reactor reference temperature (nil-ductility transition) refueling water storage pool service air steam and power conversion station blackout shield building ventilation self-contained breathing apparatus supplementary chiller condensing; stress corrosion cracking Safety Evaluation Significant Event Report steam generator safety injection safety injeCtion system safety injection tank support for Criterion (a)(2) equipment sulfur dioxide sump pump support for Criterion (a)(3) equipment [NUREG-1800, License Renewal] Standard Review Plan site security; stainless steel system, structure, or component support for Criterion (a)(1) equipment subject to aging management review cable vault and switchgear ventilation ix Abbreviation or Acronym TC TGB TLAA, TLAAs TRM TSP TW USE v yr Zn Description turbine b.uilding cooling water turbine generator building Waterford Steam Electric Station, Unit 3 License Renewal Application time-limited aging analysis, time-limited aging analyses Technical Requirements Manual trisodium phosphate dodecahydrate treated water upper-shelf energy volt year zinc one-fourth of the way through the vessel wall measured from the internal surface of the vessel x TABLE OF CONTENTS Waterford Steam Electric Station, Unit 3 License Renewal Application 1.0 ADMINISTRATIVE INFORMATION ............................... 1-1 1.1 GENERAL INFORMATION ............................................... 1-1 1.1.1 Name of Applicant .................................................... 1-1 1.1.2 Address of Applicant .................................................. 1-1 1.1.3 Description of Business of Applicants ..................................... 1-2 1.1.4 Legal Status and Organization .......................................... 1-2 1.1.5 Class and Period of License Sought ...................................... 1-5 1.1.6 Alteration Schedule ...................... , ............................ 1-5 1.1. 7 Regulatory Agencies with Jurisdiction ..................................... 1-5 1.1.8 Local News Publications ............................................... 1-6 1.1.9 Conforming Changes to Standard Indemnity Agreement ...................... 1-6 1.1.10 Restricted Data Agreement ............................................. 1-7 1.2 PLANT DESCRIPTION .................................................. 1-7 2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RES UL TS ................................. 2.0-1 2.1 SCOPING AND SCREENING METHODOLOGY .............................. 2.1-1 2.1.1 Scoping Methodology ................................................. 2.1-1 2.1.1.1 Application of Safety-Related Scoping Criteria ............................ 2.1-3 2.1.1.2 Application of Criterion for Nonsafety-Related SSCs Whose Failure Could Prevent the Accomplishment of Safety Functions ... , ..................... 2.1-5 2.1.1.3 Application of Criterion for Regulated Events ............................. 2.1-7 2.1.2 Screening Methodology ................................................ 2.1-11 2.1.2.1 Screening of Mechanical Systems ..................................... 2.1-12 2.1.2.2 Screening of Structures ............................................. 2.1-17 2.1.2.3 Electrical and Instrumentation and Control Systems ....................... 2.1-19 2.1.2.4 Consumables ..................................................... 2.1-20 2.1.3 Interim Staff Guidance Discussion ....................................... 2.1-21 2.1.4 Generic Safety Issues ................................................. 2.1-23 xi Waterford Steam Electric Station, Unit 3 License Renewal Application 2.1.5 Conclusion .......................................................... 2.1-24 2.1.6 References ......................................................... 2.1-25 / 2.2 PLANT LEVEL SCOPING RESULTS ....................................... 2.2-1 2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS .........*... 2.3-1 2.3.1 Reactor Coolant System .................................. * ........... *. 2.3-1 2.3.1.1 Reactor Vessel .................................................... 2.3-3 2.3.1.2 Reactor Vessel Internals ............................................. 2.3-8 2.3.1.3 Reactor Coolant Pressure Boundary ............ : ...................... 2.3-12 2.3.1.4 Steam Generators ................................................. : 2.3-18 2.3.1.5 RCS Systems in Scope for 1 O CFR 54.4(a)(2) ........................... : 2.3-24 2.3.2 Engineered Safety Features ....................... * .................... 2.3-29 2.3.2.1 Containment Spray ..... '. .... _ ........ : ....... ,, ................ *, . ,. ... 2.3-30 2.3.2.2 Safety Injection ..................................................... 2.3-33 2.3.2.3 Containment Penetrations ........................................... 2.3-37 2.3.2.4 ESF Systems in Scope for 10 CFR 54.4(a)(2) ..................... * ....... 2.3-42 Auxiliary Systems ................................................... 2.3-47 2.3.3.1 Chemical and Volunie Control ...... * ........................... * ....... *2.3-48 2.3.3.2 Chilled Water .......................................... : .......... 2.3-52 2.3.3.3 Component Cooling and Auxiliary Component Cooling Water ...... * .......... *2.3-55 2.3.3.4 Compressed Air ....................... * ......................... -... 2.3-61 2.3.3.5 Containment Cooling HVAC ... ; ....... '.: .... :* ...................... .'. 2.3-66 2.3.3.6 Control Room HVAC .. _ ........................................... : .. 2.3-69 2.3.3.7 Emergency Diesel Generator ................ ; ........................
2.3.3.8 fire Protection: Water ........... , .................................... 2:3-77 2.3.3.9 Reactor Coolant Pump Oil_ Collection ................................... 2.3-82 2.3.3.1 O Fuel Pool Cooling and Purification ..................................... 2.3-85 2.3.3.11 Nitrogen ......................................................... 2.3-89 2.3.3.12 Miscellaneous HVAC ............................................... 2.3_-93 2.3.3.13 Auxiliary Diesel Generator ........................................... 2.3-102 2.3.3.14 Plant Drains ...................................................... 2.3-105 2.3.3.15 Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2) ......................... 2.3-110 2.3.4 Steam and Power Conversion Systems ................................. 2.3-169 2.3.4.1 Condensate Makeup and Storage ..................................... 2.3-170 xii _j I_ Waterford Steam Electric Station, Unit 3 License Renewal Application 2.3.4.2 Emergency Feedwater ........................ , ........... * .......... 2.3-174 2.3.4.3 Main Feedwater ................................................... 2.3-177 2.3.4.4 Main Steam ....................................................... 2.3-180 2.3.4.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) ........ 2.3-185 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES .................. ... 2.4-1 2.4.1 Reactor Building ..................................................... 2.4-2 2.4.2 Nuclear Plant Island Structure ........................................... 2.4-11 2.4.3 Turbine Building and Other Structures .................................... 2.4-20 2.4.4 Bulk Commodities ........................... : ........................ 2.4-29 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND . INSTRUMENTATION AND CONTROL SYSTEMS ............................. 2.5-1 3.0 AGING MANAGEMENT REVIEW RES UL TS ...........*............ 3.0-1 3.1 REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM .......... 3.1-1 3.1.1 Introduction .............................. -........................... 3.1-1 3.1.2 Results .............................................................. 3.1-1 3.1.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs ........................................ 3.1-2 3.1.2.2 Further Evaluation of Aging *Management as Recommended by NUREG-1800 .. 3.1-7 3.1.2.3 Time-Limited Aging Analyses ................... * ...................... 3.1-11 3.1.3 Conclusion ..................................... -...................... 3.1-11 3.2 ENGINEERED SAFETY FEATURES .................... ................ ; . 3.2-1 3.2, 1 Introduction .......................................................... 3.2-1 3.2.2 Results .... _ .............. :* ..................... : .............. * ...... 3.2-1 3.2.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs ........................................ 3.2-1 3.2.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.2-6. 3.2.2.3 Time-Limited Aging An_alyses ......................................... 3.2-7 3.2.3 Conclusion .......................................................... 3.2-7 xiii Waterford Steam Electric station, Unit 3 License Renewal Application \ / 3.3 AUXILIARY SYSTEMS .................................................. 3.3-1 3.3.1 Introduction ............ *. : ........................................... 3.3-1 3.3.2 Results ............................................................. 3.3-1 3.3.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Managen:ient Programs ........................................ 3.3-5 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.3-22 3.3.2.3 Time-Limited Aging Analysis .......................................... 3.3-24 3.3.3 Conclusion ......................................................... : 3.3-24 3.4 STEAM AND POWER CONVERSION SYSTEMS ............................. 3.4-1 3.4.1 Introduction ......................................................... 3.4-1 3.4.2 Results ............................................. * ....... * .......... 3.4-1 3.4.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs ............. _ ......... : ....... : ......... 3.4-2 3.4.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.4-7
3.4.2.3 Time-Limited Aging Analysis .......................................... 3.4-8 . 3.4.3 Conclusion .......................................................... 3.4-8 3.5 CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS .............. 3.5-1 3.5.1 Introduction ........ : ................................................. 3.5-1 3.5.2 Results ...................................... : ...................... 3.5-1 3.5.2.1 Materials, Environments, Aging Effects Requiring Management.and Aging Management Programs ........................................ 3.5-1 3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.5-6 3.5.2.3 Time-Limited Aging Analysis ...........................*........ , ..... 3.5-17 3.5.3 Conclusion ......................................................... _. 3.5-17 . 3.6 ELECTRICAL AND INSTRUMENTATION AND CONTROLS .................. : . 3.6-1 3.6.1 Introduction .......................................................... 3.6-1 3.6.2 Results .............................................................. 3.6-1 3.6.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs ........................................ 3.6-1 3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.6-3 3.6.2.3 Time-Limited Aging Analysis ........................ : ................. 3.6-9 3.6.3 Conclusion ............ : ............................................. 3.6-9 xiv Waterford Steam Electric Station, Unit 3 License Renewal Application 4.0 TIME-LIMITED AGING ANALYSES .............................. 4.1-1 4.1 IDENTIFICATION OF TIME-LIMITED AGING ANALYSES ...................... 4.1-1 4.1.1 Identification of TLAAs ................................................. 4:1-2 4.1.2 Identification of Exemptions .......................................... _ .. *. *. 4.1-3 4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT * ........................... 4.2-1 4.2.1 Reactor Vessel Fluence ........ : ....................................... 4.2-1 4.2.2 Upper-Shelf Energy ................................................... 4.2-6 4.2.3 Pressurized Thermal Shock ............................................ 4.2-10 4.2.4 Pressure-Temperature Limits ........................................... 4.2-15 4.2.5 Low-Temperature Overpressure Protection (L TOP) Setpoints .................. 4.2-15 4.3 METAL FATIGUE ...................................................... 4.3-1 4.3.1 Class 1 Fatigue ............... * ....................................... 4.3-2 4.3.1.1 Reactor Vessel .... ............................................... 4.3.1.2 ReactorVessel Internals ....................................... , ...... 4.3-5 4.3.'1.3 Pressurizer ....................................................... 4.3.1.4 Steam Generators .................................................. 4.3-6 4.3.1.5 Control Element Drive Mechanisms .................................... 4.3-6 4.3.1.6 Reactor Coolant Pumps ............................................. 4.3-7 4.3.1.7 Reactor Coolant System Class 1 Piping ........... ._ ............... * ...... 4.3-7 4.3.2 Non-Class 1 Mechanical Systems ........................... , ............ 4.3-8 4.3.2.1 Nori-Class 1 Pressure Boundary Piping Using Stress Range Reduction Factors . 4.3-8 4.3.2.2 Flexible Connections and Expansion Joints .............................. 4.3-8 4.3.2.3 Non-Class 1 Heat Exchangers with Fatigue Analysis ....................... 4.3-8 4.3.3 Effects of Reactor Water Environment on Fatigue Life ........................ 4.3-9 4.4 ENVIRONMENTAL QUALIFICATION (EQ) OF ELECTRIC EQUIPMENT ........... 4.4-1 4.5 CONCRETE CONTAINMENT TENDON PRESTRESS .......................... 4.5-1 4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATIONS FATIGUE ANALYSIS ................................................... 4.6-1 xv Waterford Steam Electric Station, Unit 3 License Renewal Application 4.7 .OTHER PLANT-SPECIFIC TLAAS ......................................... 4.7-1 4.7.1 Crane Load Cycle Analysis ............................................. 4.7-1 4.7.2 Leak-Before-Break Analysis ............................................ 4.7-1 4.7.3 Postulation of High Energy Line Break (HELB) Locations ...................... 4.7-2 4.7.4 Reactor Vessel Internals Evaluations (Other than Fatigue) ..................... 4.7-2

4.8 REFERENCES

......................................................... 4.8-1 xvi LIST OF APPENDICES Appendix A: Final Safety Analysis Report Supplement Appendix B: Aging Management Programs and Activities Waterford Steam Electric Station, Unit 3 License Renewal Application Appendix C: Response to Selected Applicant/Licensee Action Items for Inspection and Evaluation Guidelines for PWR Internals Appendix D: Technical Specification Changes Appendix E: Applicant's Environmental Report, Operating License Renewal Stage xvii Waterford Steam Station, Unit 3 License Renewal Application _ .. _, LIST OF TABLES Table 2.0-1 Component Intended Functions: Abbreviations and Definitions ................... 2.0-2 Table 2.2-1 Mechanical Systems Within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . 2.2-3 Table 2.2-2 Mechanical Systems Not Within the Scope of License Renewal ................... 2.2-7 Table 2.2-3 Plant Electrical and l&C Systems Within the Scope of License Renewal. ............ 2.2-9 Table 2.2-4 Structures Within the Scope of License Renewal ............... *.-............... 2.2-11 Table 2.2-5 Structures Not Within the Scope of License Renewal ........................... 2.2-12 Table 2.3.1-1 Reactor Vessel Components Subject to Aging Management Review ............................ 2.3-6 Table 2.3.1-2 Reactor Vessel Internals Components Subject to Aging Management Review ................ , ........... 2.3-10 Table 2.3.1-3 Reactor Coolant Pressure Boundary Components Subject to Aging Management Review ............................ 2.3-15 Table 2.3.1-4 Steam Generators Components Subject to Aging Management Review ............................ 2.3-21 Table 2.3.1-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-.27 Table 2.3.1-5-2

Steam Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-28 xviii Table 2.3.2-1 Containment Spray System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review .................... '. : ...... 2.3-32 Table 2.3.2-2 Safety Injection System Components Subject to Aging Review .................... * ........ 2.3-36 Table 2.3.2-3 Containment Penetrations Components Subject to Aging Management Review ........... : . : .............. 2.3-41 Table 2.3.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-45 Table 2.3.2-4-2 Safety Injection System . Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-46 Table 2.3.3-1 Chemical and Volume Control System Components Subject to Aging Management Review ............................ 2.3-51 Table 2.3,3-2 Chilled Water System Components Subject to Aging Management Review ............................ 2.3-54 Table 2.3.3-3 Component Cooling and Auxiliary Component Cooling Water Systems Components Subject to Aging Management Review ......................... _ ... 2.3-60 Table *2.3.3-4 Compressed Air Systems Components Subject to Aging Management Review .......................... , . 2.3-65 Table 2.3.3-5 Containment Cooling HVAC System Components Subject to Aging Management Review ............................ 2.3-68 Table 2.3.3-6 Control Room HVAC System Components Subject to Aging Management Review ............................ 2.3-71 xix Table 2.3.3-7 Emergency Diesel Generator System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review ............................ 2.3-75 Table 2.3.3-8 Fire Protection: Water System Components Subject to Aging Management Review ............................ 2.3-81 Table 2.3.3-9 RCP Oil Collection System Components Subject to Aging Management Review ............................ 2.3-84 Table 2.3.3-10 Fuel Pool Cooling and Purification System Components Subject to Aging Management Review ............................ 2.3-88 Table 2.3.3-11 Nitrogen System Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-92 Table 2.3.3-12 Miscellaneous HVAC Systems Components Subject to Aging Management Review ............................ 2.3-101 Table 2.3.3-13 Auxiliary Diesel Generator System Components Subject to Aging Management Review ............................ 2.3-104 Table 2.3.3-14 Plant Drains Components Subject to Aging Management Review ............................ 2.3-109 Table 2.3.3-15-1 Air Evacuation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-133 Table 2.3.3-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-134 . xx Table 2.3.3-15-3 Annulus Negative Pressure System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review ............................ 2.3-135 Table 2.3.3-15.-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .................. : .. ...... 2.3-136 Table 2.3.3-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review, ........................... 2.3:.137 Table 2.3.3-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......................... ' .. * .. 2.3-138 Table 2.3.3-15-7 Chemical and Volume Control System Nonsafety-Relate.d Components Affecting Safety-Related Systems* Components Subject to Aging Management Review .................... *:* ....... 2.3-139 Table 2.3.3-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-140 . Table 2.3.3-15-9 Chilled Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-.141 Table 2.3.3-15-10 Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-142 Table 2.3.3-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-143 xxi Table 2.3.3-15-12 Compressed Air System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-144 Table 2.3.3-15-13 Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-145 Table 2.3.3-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-146 Table 2.3.3-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-147 Table 2.3.3-15-16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-148 Table 2.3.3-15-17 Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Subject to Aging Management Review ............................ 2.3-149 Table 2.3.3-15-18 Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-150 Table 2.3.3-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-151 Table 2.3.3-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-152 xxii Table 2.3.3-15-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Hot Machine Shop and Decon Facility Ventilation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......... -................... 2.3-153 Table 2.3.3-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-154 Table 2.3.3-15-23 Liquid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-155 Table 2.3.3-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-156 Table 2.3.3-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-157 Table 2.3.3-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-158 Table 2.3.3-15-27 Primary Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-159 Table 2.3.3-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-160 Table 2.3.3-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-161 xxiii Waterford Steam Electric Station, Unit 3 License Renewal Application '* "' Table 2.3.3-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .......... ; ................. 2.3-162 Table 2.3.3-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ................. * ........... 2.3-163 Table 2.3.3-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .... ; ........................ 2.3-164 Table 2.3.3-15-33 Secondary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review* ............................ 2.3-165 Table 2.3.3-15-34 Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ................... ; ........ 2.3-166 Table 2.3.3-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......... ., .................. 2.3-167 Table 2.3.3-15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting. Safety-Related Systems Components Subject to Aging Management Review .......................... * .. 2.3,.168 2.3.4-1 Condensate Makeup and Storage System Components Subject to Aging Management Review ............................ 2.3-173 Table 2.3.4-2 Emergency Feedwater System Components Subject to Aging Management Review ....................... * ...*. 2.3-176 xxiv

' I I Table 2.3.4-3 Main Feedwater System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review ............................ 2.3-179 Table 2.3.4-4 Main Steam System Components Subject to Aging Management Review ............................ 2.3-184 Table 2.3.4-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-190 Table 2.3.4-5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......................... , .. 2.3-191 Table 2.3.4-5-3 Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review." ........................... 2.3-192 Table 2.3.4-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-193 Table 2.3.4-5-5 Main Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-194 Table 2.3.4-5-6 Main Steam System Nonsafety-Related Components Affecting Components Subject to Aging Management Review ............................ 2.3-195 Table 2.4-1 Reactor Building Components Subject to Aging Management Review ............................ 2.4-7 Table 2.4-2 Nuclear Plant Island Structure Components Subject to Aging Management Review ............................ 2.4-17 xxv Waterford Steam Electric Station, Unit 3 J' License Renewal Application Table 2.4-3 . Turbine Building and Other Structures Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-27 Table 2.4-4 Bulk Commodities Components Subject to Aging Management Review ............................ 2.4-31 Table 2.5-1 Electrical and Instrumentation and Control Systems Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-5 Table 3.0-1 Service Environments for Mechanical Aging Management Reviews ................ 3.0-7 Table 3.0-2 Service Environments for Structural Aging Management Reviews ... * ............. . 3.0-10 Table 3.0-3 Service Environments for Electrical Aging Management Reviews .................. 3.0-12 Table3.1.1 Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801 .. : .................................. 3.1-12 Table 3.1.2-1 Reactor Vessel Summary of Aging Management Evaluation Table 3.1.2-2 Reactor Vessel Internals 3.1-49 Summary of Aging Management Evaluation .................................. 3.1-57 Table 3.1.2-3 Reactor Coolant Pressure Boundary Summary of Aging Management Evaluation Table 3.1.2-4 Steam Generators Summary of Aging Management Evaluation Table 3.1.2-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems 3.1-76 3.1-98 Summary of Aging Management Evaluation ................... " . . . . . . . . . . . . . . 3.1-113 xxvi Waterford Steam Electric Station, Unit 3

License Renewal Application Table 3.1.2-5-2 Steam Generators Nonsafety-Related Components Affecting Safety-Related *systems Summary of Aging Management Evaluation .................................. 3.1-118 Table 3.2.1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801 ..................................... 3.2-9. Table 3.2.2-1 Containment Spray System Summary of Aging Management Evaluation 3.2-33 Table 3.2.2-2 Safety Injection System Summary of Aging Management Evaluation 3.2-40 Table 3.2.2-3 Containment Penetrations Summary of Aging Management Eva I uation ................................. . 3.2-46 Table 3.2.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.2-49 Table
Safety Injection System Nonsafety-Related *components Affecting Safety-Related Systems Summar-Y of Aging Management Evaluation .................................. 3.2-51 Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 .................................... 3.3-25 Table 3.3.2-1 Chemical and Volume Control System Summary of Aging Management Evaluation .................................. 3.3-78 Table 3.3.2-2 Chilled Water System Summary of Aging Management Evaluation .................................. 3.3-88 xxvii Table 3.3.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Component Cooling and Auxiliary Component Cooling Water System Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-97 Table 3.3.2-4 Compressed Air System Summary. of Aging Management Evaluation .................................. 3.3-108 Table 3.3.2-5 Containment Cooling HVAC System Summary of Aging Management Evaluation .................................. 3.3-113 Table 3.3.2-6 Control Room HVAC System Summary of Aging Management Evaluation .................................. 3.3-117 Table 3.3.2-7 Emergency Diesel Generator System Summary of Aging Management Evaluation .................................. 3.3-123 Table 3.3.2-8 Fire Protection -Water System Summary of Aging Management Evaluation : ................................. 3.3-138 Table 3.3.2-9 Fire Protection RCP Oil Collection System Summary of Aging Management Evaluation .................................. 3.3-148 Table 3.3.2-10 Fuel Pool Cooling and Purification System Summary of Aging Management Evaluation .................................. 3.3-152 Table 3.3.2-11 Nitrogen System Summary of Aging Management Evaluation .................................. 3.3-156 Table 3.3.2-12 Miscellaneous HVAC Systems Summary of Aging Management Evaluation .................................. 3.3-159 Table 3.3.2-13 Auxiliary Diesel Generator System Summary of Aging Management Evaluation .................................. 3.3-167 xxviii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.3.2-14 Plant Drains Summary of Aging Management Evaluation Table 3.3.2-15-1 Air Evacuation System Nonsafety-Related Components Affecting Safety-Related Systems 3.3-170 Summary of Aging Management Evaluation .................................. 3.3-176 Table 3.3.2-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-177 Table 3.3:2-15-3 Annulus Negative Pressure System Nonsafety-Related Components Affecting Safety-Related Systems. Summary of Aging Management Evaluation ............. * ................ ' ..... 3.3-178 Table 3.3.2-15-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-180 Table 3.3.2-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation ......... *"* ..................... * .. 3.3-184
Table 3.3.2-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-186 Table 3.3.2-15-7 Chemical and Volume Control System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-191 Table 3.3.2-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ............. * ..................... 3.3-195 xx ix Table 3.3.2-15-9 Chilled Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-198 Table 3.3.2-15-10 Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-202 Table 3.3.2-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-205 Table 3.3.2-15-12 Compressed Air System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-209 Table 3.3.2-15-13 Containment Atmosphere Purge .System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-212 Table 3.3.2-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-214 Table 3.3.2-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-215 Table 3.3.2-15".'16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3,..216 Table 3.3.2-15-17 Emergency Diesel Generator*system Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-218 )()()(

Table 3.3.2-15-18 Fuel Handling Building HVAC System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-220 Table 3.3.2-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related' Systems Summary of Aging Management Evaluation ............... : .................. 3.3-222 Table 3.3.2-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-225 Table 3.3.2-15-21 Hot Machine Shop and Decon Facility Vent System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ................................... 3.3-228 Table 3.3.2-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ........ : ......................... 3.3-229 Table 3.3.2-15-23 Liquid Waste Management System

Nonsafety-Related Components Affecting Safety-Related Systems* Summary of Aging Management Evaluation .................................. 3.3-231 Table 3.3.2-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-235 Table 3.3.2-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation .................................. 3.3-237 Table 3.3.2-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-240 xxxi Table 3.3.2-15-27 Primary Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-242 Table 3.3.2-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems. Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-244 Table 3.3.2-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-248 Table 3.3.2-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ................................... 3.3-251 . Table 3.3.2-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-253
Table 3.3.2-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-254 Table 3.3.2-15-33 Secondary Sampling System Nonsafety-Related Co.mponents Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-257 Table Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Agirig Management Evaluation ....... : ....... : .................. 3.3-262 Table 3.3.2-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-264 xxxii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.3.2--15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-266 Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801 .................... * ................ *3.4-10 Table 3.4.2-1 Condensate Makeup and Storage System Summary of Aging Management Evaluation Table 3.4.2-2 Emergency Feedwater System 3.4-32 ' Summary of Aging Management Evaluation ............................. .... 3.4-35 Table 3.4.2-3 Main Feedwater System Summary of Aging Management Evaluation Table 3.4.2-4 Main Steam System Summary of Aging Management Evaluation Table 3.4.2-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems 3.4-38 3.4-43 Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-54 Table 3.4.2-5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-60 Table 3.4.2-5-3 Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-62 Table 3.4.2-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.4-64 xxxiii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.4.2-5-5 Feedwater System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ............................... : ... *3.4-65 Table 3.4.2-5-6 Main Steam System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-66 Table 3.5.1 Sur:nmary ofAging Management Programs for Containments, Structures and Component Supports
Evaluated in Chapters II and Ill of NUREG-1801 ............................... 3.5-18 Table 3.5,2-1 Reactor Building Summary of Aging Management Evaluation .................................. 3.5-50 Table 3.5.2-2 Nuclear Plant Island Structure Summary of Aging Management Evaluation .................................. 3.5-61 Table 3.5.2-3 Turbine Building and Other Structures Summary of Aging Management Evaluation Table 3.5.2-4 Bulk Commodities Summary of Aging* Management Evaluation Table 3.6.1 Summary of Aging Management Programs for the EiC Components 3.5-67 3.5-73 Evaluated in Chapter VI of NUREG-1801 ..................................... 3.6-10 Table 3.6.2-1 Electrical and l&C Components Summary of Aging Management Evaluation 3.6-20 Table 4.1-1 List of TLMs .......................................................... 4.1-4 Table 4.1-2 Comparison ofWF3 TLMs to NUREG-1800 Potential TLMs .................... 4.1-6 xxxiv Table 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Calculated Maximum Fast Neutron Fluence (E+19 n/cm2, E > 1.0 MeV) Projections for the WF3 Vessel Welds and Plates at 55 EFPY .............................. 4.2-5 Table 4.2-2 Predicted USE Values at 55 EFPY for WF3 RPV Beltline Materials ................ 4.2-7 Table 4.2-3 Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY ......... 4.2-11 Table 4.3-1 Projected and Analyzed Transient Cycles .................................... 4.3-4 Table 4.3-2 EAF Screening Evaluation ................................................ 4.3-12 xx.xv

( 1.0 ADMINISTRATIVE INFORMATION Waterford Steam Electric Station, Unit 3 License Renewal Application Pursuant to Part 54 of Title 10 of the Code of Federal Regulations (1 O CFR Part 54), this application seeks renewal for an additional 20-year term of the facility operating license for Waterford Steam Electric Station, Unit 3 (Waterford 3). The facility operating license for Waterford 3 (Docket Number 50-382, License Number NPF-38) expires at midnight on December 18, 2024. The application also applies to renewal of those Nuclear Regulatory Commission (NRC) source material, special nuclear material, and by-product material licenses that are subsumed ot combined with the facility operating license. The application is based on guidance provided by the U.S. Nuclear Regulatory Commission in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 201 O, and Regulatory Guide (RG) 1.188, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," Revision 1, September 2005, and guidance provided by the Nuclear E11ergy Institute (NEI) in NEI 95-10, Industry Guidelines for Implementing the. Requirements of 1 O CFR 54 -The License Renewal Rule, Revision 6, Ju.ne 2005. *

The license renewal application is intended to provide sufficient information for the NRC to *complete its tec:hnical and environmental reviews. pursuant tc:> 1 O CFR Parts 54 and 51, respectively. The license renewal application is designed to allow the NRC to make the findings required by 1 O CFR 54.29 in support of the issuance of a renewed facility operating license for. Waterford 3.* 1.1 GENERAL INFORMATION The following is the general information required .bY 1 O CFR 54.17 and 10 CFR 54.19. .. 1.1.1 Name of Applicant Entergy Operations, Inc. Entergy Louisiana, LLC 1.1.2 Address of Applicant Entergy Operations, Inc. 1340 Echelon Parkway Jackson, Mississippi 39213 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, Louisiana 70121 1.0 Administrative Information Page 1-1 Address of Nuclear Facility Waterford Steam Electric Station, Unit 3 Entergy Operations, Inc. 17265 River Road Killona, Louisiana 70057-3093 1.1.3 Description of Business of Applicants Waterford Steam Electric Station, Unit 3 License Renewal Application Entergy Louisiana, LLC, is the owner of Waterford 3, located in St. Charles Parish, Louisiana. Entergy Operations, Inc. (EOI) is the licensed operator of Waterford 3. Entergy Louisiana, LLC, and EOI (hereafter referred to as Entergy) are the holders of Waterford 3 operating license NPF-38 and for purposes of this application are considered the applicant. Entergy Utility Holding Company, LLC, a Texas limited liability company, is an intermediary holding company for Entergy Corporation and the direct parent company of Entergy Louisiana, LLC. Entergy Louisiana, LLC, is one of Entergy Corporation's five retail electric utility subsidiaries. These companies generate, transmit, distribute and sell electric power to retail and wholesale customers in Arkansas, Louisiana, Mississippi, and Texas. EOI is engaged principally in the business of operating nuclear power facilities. Entergy Corporation is an integrated energy company engaged primarily in electric power production and retail distribution operations. 1.1.4 Legal Status and Organization EOI, a Delaware limited liability company, is *a wholly owned subsidiary of Entergy Corporation. The principal office is located in Jackson, Mississippi. EOI is not owned, controlled or dominated by an alien, a foreign corporation, or foreign government. The names and addresses for EOI directors and principal officers are listed below. All are U.S. citizens. Timothy G. Mitchell Director President and Chief Executive Officer Donna Jacobs Director Chief Operating Officer-South 1.0 Administrative Information Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Page 1-2 J /

William F. Maguire Director Vice President, Operations Support Marcus V. Brown Executive Vice President and General Counsel Jeremy G. Browning Vice President, Operations (Arkansas Nuclear One) Michael R. Chisum Vice President, Operations (Waterford 3) Vincent Fallacara Vice President, Operations Support William J. James, Jr. Vice President, Major Fleet Projects Steven C. McNeal Vice President and Treasurer Kevin J. Mulligan Vice President, Operations (Grand Gulf Nuclear Station Eric W. Olson Vice President, Site (River Bend Station) Waterford Steam Electric Station, Unit 3 License Renewal Application Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy* Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Louisiana, LLC is the owner of Waterford 3. As discussed in Section 1.1.3, Entergy Utility Holding Company, LLC is the direct parent company of Entergy Louisiana, LLC. The principal office of Entergy Louisiana, LLC is located in Jefferson, Louisiana. Entergy Louisiana, LLC is not owned, controlled or dominated by an alien, a foreign corporation, or foreign government. 1.0 Administrative Information Page 1-3 Waterford Steam Electric Station, Unit 3 License Renewal Application The names and addresses for Entergy Louisiana, LLC, directors and principal officers are listed below. All are U.S. citizens. Phillip R. May Director and Chairman of the Board President and Chief Executive Officer Theodore H. Bunting, Jr. Director Group President, Utility Operations Paul D. Hinnenkamp Director Andrew S. Marsh Director Executive Vice President and Chief Financial Officer Marcus V. Brown Executive Vice President and General Counsel Joseph T. Henderson

Senior Vice President and General Tax Counsel
Timothy G. Mitchell Senior Vice President and Chief Nuclear Officer Alyson M. Mount Senior Vice President and Chief Accounting Officer Dennis P. Dawsey Vice President, Customer Service John P. Hurstell Vice President, System Planning 1.0 Administrative Information Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, *LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC
4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121
Page 1-4

/ I Waterford Steam Electric Station, Unit 3 License Renewal Application. Mark D. Kleeharnmer Vice President, Regulatory and Public Affairs Steven C. McNeal Vice President and Treasurer Jody Montelaro Vice President, Public Affairs 1.1.5 Class and Period of License Sought . Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 The applicant requests renewal of the facility operating license for Waterford 3 (facility operating license Docket Number 50-382, License Number NPF-38) for a period of 20 years. The license was issued under Section 103 of the Atomic Energy Act of 1954 as amended. License renewal would extend the Waterford 3 facility operating license from midnight, December 18, 2024, to December 18, 2044. This application also applies to renewal of thoseNRC source material, special nuclear material, and by-product material licenses that are subsumed or combined with the facility operating license. *

1.1.6 Alteration Schedule Entergy does not propose to construct or alter any production or utilization faCility in connection with this renewal application. *
1.1.7 Regulatorv Agencies with Jurisdiction Regulatory agencies with jurisdiction over the station are listed below. Federal Energy Regulatory Commission* 888 First St. N. E. * *
Washington, DC 20426 Department of Environmental Quality-(DEQ) P.O. Box 4313 Baton Rouge, Louisiana 70821-4313 1.0 Administrative Information Page 1-5 Louisiana Public Service Commission P.O. Box 91154 Baton Rouge, Louisiana 70821-9154 Parish President Council St. Charles Parish P.O. Box 302 Hahnville, Louisiana 70057 1.1.8 Local News Publications St. Charles Parish Herald Guide 14236 U.S. 90 Boutte, LA 70039 The Times-Picayune 365 Canal St. New Orleans, LA 70130 The New Orleans Advocate 1010 Common Street Suite 3030 New Orleans, LA 70112 Waterford Steam Electric Station, Unit 3 License Renewal Application 1.1.9 Conforming Changes to Standard Indemnity Agreement 10 CFR 54.19(b) requires that license renewal applications include "conforming changes to the standard indemnity agreement, 1 O CFR 140.92, Appendix B, to account for the expiration term of the proposed renewed license." The current Indemnity Agreement (No. B-92) for Waterford Steam Electric Station, Unit 3, states in Article VII that the Agreement shall terminate at the time of expiration of the license specified in Item 3 of the Attachment (to the Agreement), which is the last to expire. Item 3 of the Attachment to the Indemnity Agreement, as revised through Amendment No. 7, lists Waterford 3 facility operating license number NPF-38. Entergy has reviewed the original Indemnity Agreement and the Amendments. Neither Article VII nor Item 3 of the Attachment specifies an expiration date for license number NPF-38. Therefore, no changes to the Indemnity Agreement are deemed necessary as part of this application. Should the license number be changed by NRC upon issuance of the renewed license, Entergy requests that NRC amend the Indemnity Agreement to include conforming changes to Item 3 of the Attachment and other affected sections of the Agreement. 1.0 Administrative Information Page 1-6 1.1.10 Restricted Data Agreement Waterford Steam Electric Station, Unit 3 License Renewal Application This application does not contain restricted data or national security information, and the applicant does not expect that any activity under the renewed license for Waterford 3 will involve such information. However, if such information were to become involved, the applicant agrees to secure such information appropriately and not to permit any individual to have access to, or any facility to possess, such information until the individual or facility has been approved under the provisions of 1 O CFR Parts 25 or 95, respectively. 1.2 PLANT DESCRIPTION The Waterford 3 site is located on the west (right descending) bank of the Mississippi River near Taft, Louisiana, in the northwest portion of St. Charles Parish. About 3 miles westward is the eastern boundary of St. John the Baptist Parish. The coordinates for the reactor are 29° 59' north latitude and 90° 28' 16" west longitude. Kenner, the nearest population center, is 13 miles east of the site. Approximately 25 miles east-southeast of the site is the city of New Orleans, and approximately 50 miles north-northwest is the city of Baton Rouge. The exclusion radius is taken as 915 meters, and the low population zone is a 2-mile radius. The Nuclear Steam Supply System (NSSS) is a pressurized water reactor designed by Combustion Engineering; Incorporated. The containment structure, designed by Ebasco Services Incorporated, is comprised of a steel containment vess*e1 surrounded by a reinforced concrete shield building. * . WF3 is a pressurized-water reactor plant of the Combustion Engineering design. Since March 1985, WF3 has had two increases in reactor core power level, which has resulted in an increase in design net electrical output from 1, 104 megawatts electric (MWe) to 1, 188 MWe. The first reactor core power level increase from 3,390 megawatts thermal (MWt) to 3,441 MWt occurred in March 2002 and resulted in an increase in design net electrical output of approximately 16 MWe. The second reactor core power level increase from 3,441 MWt tq 3,716 MWt, starting with* Operating Cycle 14, resulted in another increase in design net electrical output of approximately 68 MWe. The principal structure at th.e site is the Nuclear Plant Island Structure (NPIS), which is a reinforced concrete box structure with solid exterior walls. All safety-related components are housed in the NPIS, which is flood protected up to El. +29.27 ft. mean sea level (MSL) (see Section 2.1.1.1 for further information). The NPIS provides a common structure for the reactor building, reactor auxiliary building (which includes the* control room), fuel handling building, and component cooling water system structures (cooling tower areas), as well as a common foundation mat for support of these structures. 1.0 Administrative Information Page 1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Main structures outside the NPIS are the turbine building, water treatment building, condensate polisher building, fire pump house, radioactive material storage building, chiller building, service building, administration building, maintenance support building, and intake and discharge structures, as well as the independent spent fuel storage installation (ISFSI) and various nonsafety-related storage_ tanks (fuel oil, fire water, demineralized water, condensate; and primary water). 1.0 Administrative Information Page 1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RESULTS This chapter describes the process for identification of structures and components subject to aging management review (AMR) in the Waterford 3 integrated plant assessment (IPA). For those_ systems, structures, and components (SSCs) within the scope of license renewal, 1P CFR 54.21 (a)(1) requires the license renewal applicant to identify and list structures and components subject to AMR. Furthermore, 10 CFR 54.21 (a)(2) requires that methods used to identify these structures and components be described and justified. Technical information in this section serves to satisfy these requirements. The scoping and screening method is described in Section 2.1. This method is implemented in accordance with NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR 54 -The License Renewal Rule, Revision 6, June 2005. The results of the _assessment to ** identify the systems and structures within the scope of license renewal (plant level scoping) are in S!3ction 2.2. The results of the identification of the cor:nponents and structural components subject to aging management review (screening) are in Section 2.3 for mecha11ical systems,: Section 2.4 for structures, and Section 2.5 for eleCtrical and instrumentation and control (l&C)'. systems. ' Table 2.0-'1 gives the definitions of component intended functions used in this application for components and structural components. Tables in the application may refer to either the intended function name or to the abbreviation. The term "piping" in component lists includes.pipe and pipe fittings (such as elbows, flued heads and reducers). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results 2.0-1 Abbreviation CE EN FB FC FD FLB FLT HS HT IN MB NA PB Table 2.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Intended Functions: Abbreviations and Definitions Intended Function Definition Conducts electricity Provide electrical connections to specified sections of an electrical circuit to deliver voltage, current or signals. Enclosure protection Provides enclosure, shelter or protection for in-scope equipment (including high-energy line break [HELB], radiation shielding, pipe whip restraint, and thermal shielding). Fire barrier Provide rated fire barrier to confine or retard a fire from spreading between adjacent areas. Flow control Provide control of flow rate or establish a pattern of spray. Flow distribution Provide distribution of flow. Flood barrier Provide flood :Protection barrier. for internal or external flooding events. Filtration Provide removal of unwanted material. Heat sink Provide heat sink during station blackout (SBO) or design basis accidents (includes source of cooling Water for plant shutdown). Heat transfer Provide ability to transfer heat. Insulation Insulate and support an electrical conductor (electrical) or provide insulating characteristics to reduce transfer (structural). Missile barrier Provide barrier against internally or externally generated missile. Neutron absorption Absorb neutrons. Pressure boundary Provide pressure boundary integrity such that adequate flow and pressure can be delivered or provide fission product barrier for containment pressure boundary. This function includes maintaining structural integrity and preventing leakage or spray for 10 CFR 54.4(a)(2) (mechanical). Provide pressure boundary or essentially leak-tight barrier (structural). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.0-2 .r J _,; Abbreviation SNS SRE SSR STR STRSP Table 2.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Intended Functions: Abbreviations and Definitions Intended Function Definition Support for Criterion Provide structural or functional support to nonsafety-related (a)(2) equipment equipment whose failure could prevent satisfactory accomplishment of required safety functions (includes II/I considerations) [10 CFR 54.4(a)(2)]. Support for Criterion Provide structural or functional support to equipment required (a)(3) equipment to meet the Commission's regulations for any of the five regulated events in 10 CFR 54.4(a)(3). Support for Criterion Provide structural or functional support for safety-related (a)(1) equipment equipment. Structural integrity Maintain structural integrity of reactor vessel internals components such that loose parts are not introduced into the system. Structural support Provide structural or functional support for reactor coolant system components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.0-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1 SCOPING AND SCREENING METHODOLOGY 2.1.1 Scoping Methodology The license renewal rule, 10 CFR 54 (Ref. 2.1-1 ), defines the scope of license renewal. Section 54.4(a) requires systems, structures, and components (SSCs) to be included in the license renewal process if they are-( 1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions-* (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or * (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in§ 50:34(a)(1), § 50.67(b)(2), or § 100.11 of this chapter, as applicable. (2) All nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of any of the functio11s identified in paragraphs (1 )(i), (ii), or (iii) of this section. (3) All systems, structures, and components relied on in safety analyses or plant evaluations to perform a function that demonstrates complian*ce with the Commission's regulations for fire protection (10 CFR 50.48), . environmental qualification (1 O CFR 50.49), pressurized thermal shock (10 CFR 50.61), anticipated transients without scram (10 CFR 50.62), and station blackout (1 O CFR 50.63). NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule (Ref. 2.1-8), provides industry guidance for determining what SSCs are within the scope of license renewal. The process used to determine the systems and structures within the scope of license renewal for Waterford 3 followed the recommendations of NEI 95-10. Consistent with NEI 95-10, the scoping process developed a list of plant systems and structures and identified their intended functions. Intended functions are those functions that are the basis for including a system or structure within the scope of license renewal (as defined in 10 CFR 54.4(b)) and are identified by comparing the system or structure function with the criteria in 10 CFR 54.4(a). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-1 *. J Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The Waterford 3 equipment database was used to identify the system codes in use at the plant. The equipment database is a controlled list of plant components, with each component assigned to one plant system code. The list of plant systems for license renewal scoping was then developed based on the plant system* codes, flow diagrams, and system functions as identified in maintenance rule scoping documents and design basis documents. Systems described in the FSAR do not necessarily correspond to equipment database system codes or the system names used for license renewal: The system descriptions in Section 2.3 explain as needed how the system names relate to system descriptions in the FSAR. For mechanical system scoping, a system is defined as the collection of components required to perform the system's functions. These components are identified in the equipment database, on flow diagrams, and in descriptions of the systems in maintenance rule scoping documents, design basis documents, and system training material. While structural commodities, such as supports, are included in the equipment database and assigned system codes, these components are evaluated with the structural bulk commodities. Component numbers on flow diagrams do not always correlate with component identifications in the equipment database. On some flow diagrams, the original Ebasco component identification numbers are used. Other diagrams show the Entergy component identification that is used in Entergy's Asset Suite, which is the software product used by the Entergy operating fleet for work management, document management, engineering changes, etc. Stiil other diagrams show both component identifications, the Ebasco number and the Entergy-number. For the purposes of system level scoping, plant electrical and l&C systems as well as electrical and l&C components in mechanical systems* are included within the scope of license renewal. Intended functions for electrical and l&C systems are not identified since this bounding scoping approach (i.e., all electrical and l&C components are included in scope by default) makes it unnecessary to determine if an electrical and l&C system has an intended function. Switchyard equipment, which is not part of the plant's electrical and l&C systems, was reviewed for station blackout (SBO) intended functions based on NRC guidance. For further discussion of Waterford 3 scoping for SBO, see Section 2.1.1.3.5. See Section 2.5 for additional information on electrical and l&C scoping. As the starting point for structural scoping, a list of plant structures was developed from a review of plant layout drawings, the FSAR, maintenance rule documentation, and relevant design basis documents. The structures list includes structures that potentially support plant operations or could adversely impact that support plant operations (i.e., seismic II/I). In addition to buildings and facilities, the list of structures includes other structures that support plant operation (e.g., electrical manholes and foundations for freestanding tanks). See Section 2.4 for the results of structural scoping. Intended functions for structures and mechanical systems were identified based on reviews of applicable plant licensing and design documentation. Documents reviewed included the FSAR, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information design basis documents, maintenance rule scoping documents, the post-fire safe shutdown analysis, and, as necessary, system training materials and various station drawings. Each mechanical system and structure function was evaluated against the criteria of 1 O CFR 54.4 as described in the following sections. Section 2.1.1.1 discusses the evaluation of the safety:-related criteria *in 1 O CFR 54.4(a)(1 ). Section 2.1.1.2 discusses the of the criteria of 1 O CFR 54.4(a)(2). Section 2.1.1.3 discusses the evaluation of the *in 1 O CFR 54.4(a)(3). The results of these evaluations for pfant system and structures are presented in Section 2.2.
2.1.1.1 Application of Safety-Related Scoping Criteria '.* A system or structure is within .the scope of iicense 'renewal if it performs a safety function during.* and following a design basis event as defined in 10 CFR 54.4(a)(1). Design basis events are defined in 1 O CFR 50.49(b)(1 )(ii) as conditions of normal operation, including anticipated operational occurrences, design basis accidents, exterilai events, and hatural phenomena for which the plant must be. designed to ensure functions identified in 10 'CFR 54.4(a)(1 )(i) through (iiij. . An Entergy corporate procedure and a site engineering staildard provide control of component and structure quality classification. The procedures design basis events consistent with 10 CFR 50.49 (b)(1 )'and define the ql!alify assurance classification of "safety-related" as follows: -Those structures, systems and components that are relied upon to remain functional during and following design basis events to assure:.* 'I ' * (1) The integrity of the reactor coolant pres&ure boundary. (2) The capability to shut down the reactor and maintain it in a safe shutdown
condition. .. * ' (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the, applicable guideline exposures set forth. in 10 CFR 50.34(a)(1), 10 5.0:67, or 10 CFR 100.11. This is the sa.me definition used for safety-related SSC used in *1 O CFR 54.4(a)(1), with a slight difference in wording: where Entergy procedures use "the applicable guideline.exposures set forth in ... .,;' 10 CFR 54.4(a)(1)(iii) uses the phrase, ... those referred to in ....... The two phrases are equivalent. The original specifications for Waterford 3 used a somewhat different definition for Safety Class 3 for equipment whose failure would "result in significant release of radioactivity to the environment." Use of the term "significant release" instead of the requirements of
50.34(a)(1 ), 50.67(b)(2), or 100.11 resulted in components that are classified as Safety Clas.s 3 at Waterford 3 but do not meet the criteria of 10 CFR 54.4(a)(1). Waterford 3 Safety Class 3 components "Yere evaluated to determine if they supported system functions meeting the 2:0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-3

\. --Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information requirements of1 O CFR 54.4(a)(1 ). Those that did not were further evaluated for the criteria of 1 O CFR 54.4(a)(2) and (a)(3). The Waterford 3 equipment database maintains the controlled component level list of quality classifications. Mechanical system safety functions were obtained from the FSAR, maintenance rule scoping documents, and design criteria documents. Mechanical systems whose only safety-related components are electrical and l&C components or structural components are not included in scope for this criterion; however, the electrical and l&C portions of the system are included in scope by default, and structural components are included in the structural evaluations. Structural safety functions include providing containme'nt or isolation to mitigate post-accident site doses and providing support or protection to safety-related equipment. Structures with *safety functions are identified in the maintenance rule scoping documents. All structures with a safety function or that support or protect a safety.,.related component are included within the scope of license renewal on the basis of 10 CFR 54.4(a)(1). Structures ar:id structural components that provide protection to safety-related equipment from external events and natural phenomena are included in the scope of license renewal on the .basis of 10 CFR 54.4(a)(1 ). As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. *

At Waterford 3, all safety-related equipment is housed within the nuclear plant island structure* .(NPIS). The NPIS is a reinforced concrete box structure with solid walls that provide flood protection up to El. +29.?7 feet MSL. The NPIS is th.e common structure of the reactor building, reactor auxiliary building, fuel handling building, and component cooling. water system
All exterior doors and penetrations be.low +29.27 feet MSL that lead to areas containing-safety-related equipment are watertight. * *
The original design flood level of the NPIS was El. 30.0 ft. MSL During the initial phase of_ construction from 1975 to 1978, the plant settled approximately 9 inches. therefore; the -estabiished *elevations of the plant on design drawings are higher by approximately 9 inches than the actual elevations. The top of the exterior walls (flood walls) of the NPIS were surveyed in . 1991 to be at El. 29.27 ft. MSL. The design flood level of the NPIS is reduced to El. 29.25 ft. MSL from El. 30.0 ft. MSL, a 9-inch*difference. The safety;-related equipment housed within the NPIS is still protected from disastrous floods. since the highest level the-water wilr teach at the NPIS is. El. 27.6 ft. f\!JSL in the. most severe conditions. Several site documents (including the FSAR and descriptions ir:i this application) still use the original design flo.od level of +30 feet correction for the 9-inch discrepancy. *
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1.1.2 Application of Criterion for Nonsafety-Related SSCs Whose Failure Could Prevent the Accomplishment of Safety Functions This review identified nonsafety-related systems and structures containing components whose failure could prevent satisfactory accomplishment of a safety function. The guidance of NEI 95-10 Appendix Fis used to define the SSCs included in scope for physical interaction. Consideration of hypothetical failures that could result from system interdependencies that are
not part of the current licensing basis and that have not been previously experienced is not required. The impact of nonsafety-related SSC failures on safety functions can be either functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of a nonsafety-related SSC in physical proximity to a safety-related SSC. 2.1.1.2.1 Functional Failures of SSCs At Waterford 3, with few exceptions, systems and structures required to perform a function to support a safety function are classified as safety-related and* have been included in the scope of license renewal per Sectipn 2.1.1.1. For the few exceptions where nonsafety-related equipment is required to remain functional to support a safety function (e.g., the dry cooling tower sump* pumps, makeup to spent fuel pool), the system containing the equipment has been included in scope, and the function is listed as an intended function.for 10 CFR 54.4(a)(2) for the system. Flooding analyses were reviewed to determine systems with functions credited to mitigate effects of external or internal flooding. 2.1.1.2.2 Physical Failures of Nonsafety-Related SSCs Some nonsafety-related components co.uld affect safety-related components due to their physical proximity; that is, their physical location can result in interaction between the components should the nonsafety-related component fail. Based on the license renewal rule and the guidance in NEI 95-10 (Ref. 2.1-8), physical failures of nonsafety-related SSCs in scope based on 10 CFR 54.4(a)(2) fit into the following two categories. (1) Nonsafetv-Related SSCs [)irectly Connected to Safetv-Related SSCs For nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems), components within the scope of license renew;;:il include the nonsafety-related piping, components and supports up to and including the first seismic or equivalent anchor or base-mounted component beyond the safety-to-nonsafety interface such that the safety-related portion of the piping will be able to perform its intended function. *See Section 2.1.2.1.2 for further discussion of screening these components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-5 Waterford Steam Electric Station, Unit3 License Renewal Application Technical Information (2) Nonsafety--RelatedBSCs with the Potential for Spatial Interaction with Safetv-Related SSCs Spatial interactions can occur as (a) physical impact or flooding; (b) pipe whip, jet impingement, or harsh environments (such as caused by a HELB); or (c) leakage or spray. (a) Physical Impact or Flooding This category concerns potential spatial interaction of nonsafety-related SSCs falling on or otherwise physically impacting safety-related SSCs (e.g., by causing flooding) such that safety functions may not be accomplished. Structural components that meet the criterion of 10 CFR 54.4(a)(2) include missile barriers, flood barriers, HELB protection, and nonsafety-related supports for seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safefy-related equipment. This.also includes seismic Category I supports provided for nonsafety-related components, such as ducting. Structural compo_nents that protectsafety-related equipment are within the scope of license renewal and are evaluated in the structural aging management review for the structure in which they are located-or *in the bulk commoditiE;!S aging management review (Section 2.4). (b) Pipe Whip, Jet Impingement, or Harsh Environments Nonsafety-related portions of high-energy lines were evaluated against the criterion of 10 CFR 54.4(a)(2). Documents reviewed included the FSAR and other relevant site documentation. High-energy systems were evaluated to ensure identification of components that are part of nonsafety-related high-energy lines that can affect safety-related equipment. If a HELB analysis assumes that a nonsafety-related piping system does not fail or assumes failure only at specific locations, then that piping system is within the scope of license renewal per 1 O CFR 54.4(a)(2) and subject to aging management review in order to provide reasonable assurance that those assumptions remain valid through the period of extended *operation.-(c) Leakage or Spray Moderate-and low-energy systems have the potential for spatial interactions of leakage or spray. Nonsafety-related systems and nonsafety-related portions of safety-related systems with the potential for leakage or spray that _could prevent safety-related SSCs from performing their required safety function are in the scope of license renewal and subject to aging management review. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Operating experience indicates that nonsafety-related components containing only air or gas have experienced no failures due to aging that could impact the ability of safety-related equipment to perform required safety functions. There are no aging effects for these components when the environment is a dry gas. Therefore, a system containing only air or gas is not in the scope of license renewal based on the potential for spray or leakage. The review used a spaces approach for scoping of nonsafety-related systems with potential spatial interaction with.safety-related SSCs. The spaces approach focuses on the interaction between nonsafety-related and safety-related SSCs that are located in the same space. A "space" is defined as a room or cubicle that is separated from other spaces by substantial objects (such as wall, floors, *and ceilings). The space is defined such that any potential interaction between nonsafety-related and safety-related SSCs, including flooding, is limited to the space. Nonsafety-related systems that contain water, oil, or steam with components located inside structures containing safety-related SSCs are potentially in scope for possible spatial interaction under criterion 10 CFR 54.4(a)(2). These systems were evaluated further to determine if system components were located in a space such that safety-related equipment could be affected by a component failure. Equipment that has been retired in place and is no longer functional was included in this evaluation. The retired equipment was evaluated for potential spatial interaction. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. 2.1.1.3 Application of Criterion for Regulated Events The scope of license renewal includes those systems, structures, and components relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48), environmental qualification (10 CFR 50.49), pressurized thermal shock (10 CFR 50.61), anticipated transientswithout scram (to CFR 50.62), and station blackout (10 CFR 50.63). This section discusses the approach used to identify the systems and structures within the scope of license renewal based on this criterion. The systems and structures that perform intended functions in support of these regulated events are identified in the descriptions in Sections 2.3, 2.4, and 2.5. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1.1.3.1
Commission's Regulations for Fire Protection (1 O CFR 50.48) On July 16, 2004, the NRC amended 10 CFR 50.48 to add a new subsection, 10 CFR 50.48(c), that established acceptable fire protection requirements. The change to 1 O CFR 50.48 endorses with exceptions the National Fire Protection Association's (NFPA) Standard 805, Based Standard forFire Protection for Light. Water Reactor Electric Generating Plants, 2001 Edition, as a voluntary alternative for demonstrating compliance with 10 CFR 50.48 Sections (b) and (f). Waterford 3 is in the process of transitioning to the NFPA 805 risk-informed, performance-based fire protection program. However, as this process has not been completed, this license renewal application is based on the site's requirements under 10 CFR 50.48 and Appendix R.-Systems and structures in the scope of lice*nse rene\Yal for fire protection include those r_equired for compliance with 1 O CFR 50.48 and Appendix R. Equipment relied on for fire protection includes SSCs credited with fire prevention, detection, and mitigation in areas containing equipment important to safe operation of the plant as Well as systems that contain plant components credited for safe shutdown following a fire. To identify this equipment, Waterford 3 fire protection documents were reviewed. * *
FSAR Section 9.5 the fire protection program and fire protection systems for the . *current licensing basis, including a detailed comparison to Appendix A of the Branch Technical Position APCSB 9.5-1, Rev. 0. Section 9.5.1.3.2 provides a fire area-by-fire area analysis of the fire hazards in each area, including a listing of equipment located in the fire area/zone which may be used to athieve and maintain safe shutdown following a fire elsewhere in the plant and a of measures provided for fire control. The Waterford.3 post:-fire safe shutdown is documented in a site calculation. This calculation was performed in the context of the post-fire safe shutdown system separation requirements defined by Branch Technical Position (BTP) CMEB 9.5.1 and 1 d CFR 50, Appendix R, and with Section 111.G and 111.L of Appendix R to 1 o CFR 50. The calculation also incorpo"rates analyses performed in preparation for the transition to NFPA 805. A site administrative procedure describes responsibilities, controls and implementing requirements for the Waterford 3 Fire Protection Program. The Fire Protection Program assures that a defense-in-depth program is. provided to (1) prevent fires from starting, (2) detect rapidly, control, and extinguish fires that do occ.ur, and (3) provide protection for structures, systems and components important to safety so that a fire that ls not promptly extinguished by the fire
suppression activities will not prevent the safe shutdown of the plant.
Based on the review of the Waterford 3 current licensing pases for fire protection, the system intended functions performed in support of the fire protection program requirements were determined. Section 2.3 contains the results of the review for the Waterford 3 mechanical 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information systems and identifies systems that contain passive mechanical components that are required for fire protection and safe shutdown of the plant. Structures required to provide support, shelter or protection to equipment meeting the criterion of 1 O CFR 54.4(a)(3) based on the requirements of 10 CFR 50.48 are considered to be within the scope of license renewal based on 1 O CFR 54.4(a)(3). Structural commodities credited as fire barriers are included in the structural aging management reviews. Section 2.4 contains the results of the scoping review for the Waterford 3 structures. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. 2.1.1.3.2 Commission's Regulations for Environmental Qualification (10 CFR 50.49) Electric equipment important to safety that is required to be environmentally qualified to mitigate certain accidents that result in harsh environmental condition*s in the plant is defined in 1 O CFR. 50.49. The Waterford 3 Environmental Qualification Program controls the maintenance of the EQ Component List (EQCL), which is contained within the equipment database. The EQCL identifies electrical equipment and components that are required to function during and subsequent to design basis events. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. This includes equipment relied upon to perform a function that demonstrates compliance with the Commission's regulations for environmental qualification. 2.1.1.3.3 Commission's Regulations for Pressurized ThermaLShock (10 CFR 50.61)
The pressurized thermal shock (PTS) rule, 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," requires that licensees of pressurized water reactors evaluate the reactor vessel beltline materials against specific criteria to ensure protection from brittle fracture. 10 CFR 50.61 specifiesJhe calculation method to determine an analytical reference temperature, RT PTS* which is compared to PTS screening criteria specified
in the rule. RT PTS values have been extrapolated through the period of extended operation, or 55 effective full power years (EFPY). The limiting reference temperature after 60 years of operation is. below the screening criteria. As a result, no flux reduction programs or modifications to equipment, systems or operation are.necessary to prevent potent!al failure of the reactor vessel. The only system currently relied upon to meet the PTS regulation is the reaCtor coolant system, which contains the reactor vessel. There are no electrical systems or structures relied upon to meet the PTS regulation. For further information on PTS evaluation, see Section 4.2.3. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-9 2.1.1.3.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Commission's Regulations for Anticipated Transients without Scram C10 CFR 50.62) An anticipated transient without scram (ATWS) is an anticipated operational occurrence that is accompanied by a failure of the reactor trip system to shut down the reactor. The ATWS rule, 10 CFR 50.62, requires specific improvements in the design and operation of commercial nuclear power facilities to reduce the probability of failure to shut down the reactor following anticipated transients and to mitigate the consequences of an ATWS event. FSAR Section 7.8 describes the ATWS mitigation systems. The ATWS mitigation systems are designed to mitigate the consequences of anticipated operational occurrence (AOO's) such as a loss of feedwater, loss of condenser vacuum, or loss of offsite power coupled with a failure of the reaCtor protection system to trip the reactor. The A TWS mitigation systems are comprised of two essentially independent subsystems: the Diverse Reactor Trip System (ORTS) and the Diverse Emergency Feedwater Actuation System (DEFAS). ORTS has the function of tripping the reactor, and DEFAS has the function of initiating emergency feedwater (EFW) to the steam generators when required by an ATWS condition.* Inherent to ORTS design is a turbine trip independent and diverse from the plant protection system, which is initiated by undervoltage conditions sensed in the control element assembly (CEA) drive control system. This arrangement, which is the diverse turbine trip system in FSAR Section 7.8, satisfies ATWS rule requirements for a diverse turbine trip. Based on Waterford 3 current licensing bases for ATWS, system intended functions performed in support of ATWS requirements were determined. System scoping evaluations in Section 2.3 contain the results of the review for Waterford 3 systems. There are no mechanical systems with an intended function in support of ATWS requirements. The structure scoping evaluations in Section 2.4 contain the results of the review for the Waterford 3 structural systems. Structures providing support, shelter or protection to equipment meeting the criterion of 10 CFR 54.4(a)(3) based on the requirements of 10 CFR 50.62 are considered to be within the scope of license renewal based on 10 CFR 54.4(a)(3). As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. Consequently, electrical and l&C equipment that supports the requirements of 10 CFR 50.62 is included in the scope* of license renewal. 2.1.1.3.5 Commission's Regulations for Station Blackout (10 CFR 50.63) 1 O CFR 50.63, "Loss of All Alternating Current Power," requires that each light-water-cooled nuclear power plant be able to withstand and recover from an SBO. As defined by 10 CFR 50.2, an SBO is the loss of offsite power and on-site emergency alternating current (AC) electric power to the essential and non-essential switchgear buses in a nuclear power plant. It does not include the loss of AC power fed from inverters powered by station batteries or by alternate AC sources, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.1-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information nor does it assume a concurrent single failure or design basis accident. The objective of this requirement is to assure that nuclear power plants are capable of withstanding an SBO and maintaining adequate reactor core cooling and appropriate containment integrity for a required duration. FSAR Appendix 8.1A summarizes the licensing bases for SBO at Waterford 3. Waterford 3 has developed a four-hour coping analysis to address the requirements of 10 CFR 50.63. Based on the current licensing bases for SBO, system intended functions performed in support of 10 CFR 50.63 requirements were determined. System scoping evaluations in Section 2.3 contain the results of the review for Waterford 3 systems. Based on NRC guidance in NUREG-1800, Section 2.5.2.1.1 (Ref. 2.1-2); certain switchyard components required to restore offsite power are conservatively included within the scope of license renewal even though those components are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for SBO (10 CFR 50.63).
The indiv.idual structure scoping evaluations in Section 2.4 contain the results of the review for the Waterford 3 structural systems. Structures providing support, shelter or protection to equipment meeting the criterion of 1 O CFR 54.4(a)(3) based on the requirements of 10 CFR 50.63 or the restoration of offsite power are considered to be within the scope of license renewal based on*10 CFR 54.4(a)(3). r As described in Section 2.1.1, plant electrical and l&C are included in the scope of license renewal by default. Consequently, electrical equipment that supports the requirements of 10 CFR 50.63 is included in the scope of license renewal. Section 2.5 contains the results of the review for electrical and l&C systems. 2.1.2 Screening Methodology Screening is the process for determining which components and structural elements require aging management review. Screening is governed by 10 CFR 54.21(a), which reads as follows: (1) For those systems, structures, and components within the scope of this part, as delineated in § 54.4, identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components-* (i) That perform an intended function, as described in § 54.4, without moving parts or without a change in configuration or properties [i.e., passive components]. These structures and components include, but are not limited to, the reactor vessel, the reactor coolant system pressure boundary, steam generators, the pressurizer, piping, pump casings, valve bodies, the core shroud, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-11

\ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (2) (3)' component supports, pressure retaining boundaries, heat exchangers, ventilation ducts, the containment, the containment

liner, electrical and mechanical penetrations, equipment hatches, seismic Category I structures, electrical cables and connections, cable trays, and electrical cabinets, excluding, but not limited to, pumps (except casing), valves (except body), motors, diesel generators, air compressors, snubbers, the control rod drive, ventilation dampers, pressure transmitters, pressure indicators, water level indicators, switchgears, cooling fans, transistors, batteries .. breakers, relays, switches, power inverters, circuit boards, battery charg.ers, and power supplies; and (ii) That are not subject to replacement based .on a qualified life or specified time period [i.e., long-lived components]. Describe and justify the methods used in paragraph (a)(1) of this section. For each struc.ture and component identified in paragraph (a)(1) of this section, demonstrate that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. NEI 95-10 (Ref. 2.1-8) provides industry guidance for screening structures and components to identify the passive, long-lived structures and components that support an intended function. The screening process for Waterford 3 followed the recommendations of NEI 95-10. Within the group of systems and structures that are in scope, passive long-lived corriponents or structural elements that perform intended functions require aging management review. Components or structural elements that support an intended function do not require aging *. management review if they are either active or subject to replacement based on a qualified life. Although the requirements for the integrated plant assessment are the same for each system and structure, in practice the screening process differed for mechanical systeD-is, electrical systems, and structures. The three separate screening processes are described below. 2.1.2.1 Screening of Mechanical Systems As required by 10 CFR 54.21 (a); tlie screening process identified those components that are subject to aging management review for each mechanical system within the scope of license renewal. Section 2.3 presents the results for mechanical systems. Mechanical component intended functions are included in Table 2.0-1. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-12 2.1.2.1.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Identifying Components Subject to Aging Management Review Within the system, components are subject. to aging.management review if they perform an intended function without moving parts or a change in configuration or properties and if they are not subject to replacement based on a qualified life or specified time period. In making the determination that a component performs an intended function without moving parts or a change in configuration or properties, it is not necessary to consider the piece parts of the component. However, in the case of valves, pumps,. and housings for fans and dampers, the valve bodies, pump casings, and housings may perform an intended function by maintaining the pressure boundary and may therefore be subject to aging management review. Replacement programs are based on vendor recommendations, plant experience, or any means establishes a specific service life, qualified life, or replacement frequency under a controlled program. Components that are subject to replacement based on qualified life or specified time period are not subject to aging management review. Where flexible elastomer hoses/expansion joints or other components are periodically replaced, these components are not subject to aging management review. Safety-related instrument air solenoid valves that open to relieve pressure and fail to a* safe position upon loss of pressure boundary do not require aging management review because maintaining a pressure boundary is not a component intended function for these valves. 2.1.2.1.2 Identifying Components Subject to Aging Management Review Based on Support of an Intended *Function for 1 O CFR 54.4(a)(2) As discussed in Section 2.1.1.2, systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function could impact a safety function. A physical failure is one where a safety function could be. impacted by the loss of structural or mechanical integrity of an SSC. For systems with a function identified as meeting the criteria for 1 O CFR 54.4(a)(2) basec{ on a functional failure, components supporting the function are subject to aging management review. As. discussed in Section 2.1.1.2, physical interactions of nonsafety-related systems in scope based on 10 CFR 54.4(a)(2) fit into the following two categories:
Nonsafety-related systems or components directly cbnne.cted to safety-related systems (typically piping systems); or
Nonsafety-related systems or components with the potential for spatial interaction with safety-related SSCs. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-13 /

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Appropriate flow diagrams for the systems were reviewed to identify safety-to-nonsafety interfaces. Piping isometrics were also used to identify seismic anchors and equivalent anchors (restraints or supports) when required to establish scope boundary. For each interface, the boundary was* determined by one of the following: * (1) The first seismic anchor, which is defined as a device or structure that ensures thatforces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in _each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted *component. (4) An endpoint of a plant-specific piping design analysis to ensure that forces and moments are restrained in three orthogonal directions.

This is consistent with the guidance in, NEI 95-10, Appendix F. All component types required or conservatively considered to provide structural support for safety-related portions of systems are included in aging management reviews.
The following modes of spatial interaction, described in Section 2.1.1.2, were considered in the
screening process .. Physical Impact or Flooding Nonsafety-re!ated supports for non-seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safety-related structures or components (SCs) are subject to aging management review based on the criteria of 10 CFR 54.4(a)(2) and 54.21 (a). These supports and components are addressed in a commodity fashion with the structural evaluations in Section 2.4. Reviews of earthquake experience identified no occurrences of welded steel pipe segments falling due to a strong motion earthquake. Falling of piping segments is extremely rare and only occurs when there is a failure of the supports. This conclusion applies for new and aged pipe. Therefore, as long as the effects of aging on the supports for piping systems are managed, falling of piping sections is not credible except due to flow-accelerated corrosion, and the piping section itself is not in scope for 10 CFR 54.4(a)(2) due to a physical impact hazard (but may be in scope due to the potential for leakage or spray). (Ref. 2.1-8) 2.0 Scoping and Screening Methodology for Identifying Structures and Componerits Subject to Aging Management Review and Implementation Results Page 2.1-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Missiles can be generated frorn internal or external events such as failure of rotating equipment. Nonsafety-related design features that protect safety-related equipment from missiles are subject to aging management review based on the criteria of 1 O CFR 54.4(a)(2) and 54.21 (a). These features are addressed.with the structural evaluations in Section 2.4. Overhead-handling systems (e.g., cranes) whose failure could result in damage to a system that could prevent the accomplishment of a safety function are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Specific co*mponents in these systems are subject to aging management review. These features are addressed with the structural evaluations for the structure in which the components are.located. Walls, curbs, doors, etc., that provide flood barriers to safety-related equipment are subject to aging management review based on the criteria of 1 O CFR 54.4(a)(2) and 54.21 (a). These structural components have been included in the evaluation of the building in which they are located or in the evaluation of structural bulk commodities. Structures and structural components are reviewed in Section 2.4. Pipe Whip. Jet Impingement. or Harsh Environments To ensure the nonsafety-related portions of high-energy lines were included in the 1 O CFR 54.4(a)(2) the Waterford 3 FSAR and associated site documentation were reviewed. Many high-energy lines are safety-related components in systems that are already within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(1 ). During review of the Waterford 3 systems for 10 CFR 54.4(a)(2), high energy systems were considered. If a HELB analysis assumes that a nonsafety-related piping system does not fail or assumes failure only at specific locations, then that piping system is within the scope of license renewal per 10 CFR Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. Nonsafety-related components in high-energy lines are included in the appropriate system table for the 10 CFR 54.4(a)(2) review (Sections 2.3.1.5, 2.3.2.4, 2.3.3.15 and 2.3.4.5). Leakage or Spray Screening nonsafety-related components for a potential impact to safety functions due to leakage or spray is performed using three steps:. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-15 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 1. Determine if the components only contain air or gas. For these systems, a review of operating experience is performed to confirm that there have been no failures of air/gas' systems that could have adversely impacted the ability of equipment to perform required safety functions. The operating experience review performed for WF3 confirmed that there have been no failures of air/gas systems that could have adversely impacted the ability of equipment to perform required safety functions. Based on this review, components containing only air or gas do *not have a potential impact to safety functions due to leakage or spray an.d are therefore not subject to aging . management review for 1 O CFR for leakage or spray. 2*. Using a "spaces" approach. determine if the system has components in a safetv-related structure. *
Structures containing safety-related components were identified. and systems reviewed to verify the locations of components in the.system. 3. Determine if components in safety-related structures have the* potential for
spatial interaction with a safety-related component from leakage or spray. For structures that contain safety-related SCs, there may be selected rooms (spaces) that do not contain safety-related components .. Nonsafety-related components in such spaces not have the potential for leakage or spray onto .. safety-r,eJated components. However, no such spaces were identified for WF3. ---' -*Therefore, nonsafety-related components containing water, oil, or steam and located.in structures containing safety-related equipment were subjectto aging management review . . The following. structures contain safety-related components,
Component Cooling Water System Structure (Cooling Tower A and B)
Fuel Handling Building
Manholes and duct banks
Nuclear Plant Island Structure
Plant Stack
Reactor Auxiliary Building
Reactor Building
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-16 2.1.2.1.3 Waterford Steam Electric Station, Unit 3 License Renewal Application _,.* Technical Information Abandoned equipment that has not been verified to be isolated and drained that is located in a space with safety-related equipment is included within the scope of license renewal in accordance with 1 O CFR 54.4(a)(2). The scope of abandoned equipment was determined from discussions with *site. personnel and from reviews of the site equipment database and relevant documents, such as design change notices, system and structure scoping results, and piping and instrumentation diagrams that denote abandoned equipment using hash marks and notes. Mechanical System Drawings License renewal drawings were prepared to indicate portions of systems that support system intended functions within the scope of license renewal. Components subject to aging management' review (i.e., passive, long-.lived components that support system intended functions) are highlighted using color coding to indicate which aging management review evaluated the components. Flexible elastomer hoses/expansion joints and other components that are periodically replaced and therefore not subject to aging management review are indicated as such on the drawings. Safety-related instrument air solenoid valves that open to relieve pressure and fail to a safe position upon loss of pressure boundary do not require aging management review and thus are not highlighted. *
2.1,2.2 Screening of Structures For each structure within the scope of license renewal, the structural components and commodities *were evaluated to determine those subject to aging management review. This evaluation (screening process) for structural components and commodities involved a review of design and licensing basis documents (FSAR, design basis documents, design specifications, site drawings, etc.) to identify specific structural components and commodities that make up the . structure. Structural components and commodities subject to aging management review are those that (1) perform an intended function without moving parts or a change in configuration or properties, and (2) are not subject to replacement based on qualified life or specified time period. Section 2.4 presents the results for structures. 2.1.2.2.1 structural Component and Commodity Groups structurai components and commodities often have no unique identifiers such as those given to mechanical components. Therefore, grouping structural components and commo.dities based on materials of construction provided a practical means of categorizing them for aging management reviews. Structural components and commodities were categorized by the following groups based on materials of construction.
steel and other metals
Bolted connections 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Concrete .
Other materials (e.g., fire barrier material, elastomers, wood) 2.1.2.2.2 Evaluation Boundaries Structural evaluation boundaries were established as described below. ASME and Non-ASME Component Supports-Mechanical Components The evaluation boundaries for mechanical component were established in accordance with rules governing inspection of component supports (i.e., American Society of Mechanical Engineers (ASME) Section XI, Subsection IWF). Component support examination boundaries for integral and non-integral (i.e.; mechanically attached) supports are defined in*Article IWF-1300, Figure IWF-1300-1. In general, the support boundary extends to the surface of the building structure, but does not include the building structure. Furthermore, the support boundary extends to include integral attachments to piping and equipment, but does not include integral attachments to the same.
Compone_nt Supporls-_:Electrical Components 2.1.2.2.3 Supports for electrical components inClude cable trays, conduits, electrical panels, racks, cabinets and other enclosures. The evaluation boundary for these items includes supporting elements, including integral attachments to the building structure. Other Structural Members Evaluation boundaries for other structural members whose function is to carry dynamic loads caused by postulated design basis events are consistent with the.method for establishing boundaries for supports specified above. That is, the boundary includes the structural component and the associated attachment to the building structure. The portion of the attachment embedded in the building structure is considered part of the *
structure. Intended Functions Structural components and commodities* were evaluated to determine intended functions as they relate to license renewal. NEI 95-10 (Ref. 2.1-8) provides guidelines for determining the .intended functions of structures, structural components and commodities. Structural component and commodity intended functions include providing protection and providing structural or functional support. structural components either _have the potential for spatial interaction with safety-related equipment (e.g., cranes, hoists) or serve as mitigating features for potential spatial interactions. Mitigating features include missile barriers, flood . . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review ahd Implementation Results Page 2.1-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information barriers, HEL8 protection, and nonsafety-related supports for non-seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safety-related equipment. Structural component intended functions are included in Table 2.0-1. 2.1.2.3 Electrical and Instrumentation and Control Systems The electrical and l&C aging management review evaluates com'modity groups containing components with similar characteristics. Screening applied to commodity groups determines* which electrical and l&C components are subject to aging management review. An aging management review is required for commodity groups that perform an intended function, as described in 1 O CFR 54.4, without moving parts or without a change in configuration or properties (passive) and that are not subject to replacement based on a qualified life or specified time period (long-lived). Section 2.5 presents the results for electrical systems. Electrical and l&C component intended functions are included in Table 2.0-1. 2.1.2.3.1 Passive Screening NEI 95-10, Appendix 8, "Typical Structure, Component and Commodity Groupings and Active/ Passive Determinations for the Integrated Plant Assessment," identifies electrical commodities considered to be passive. Waterford 3 electrical commodity groups were compared to the NEI 95-10, Appendix 8 electrical and l&C commodity groups. Waterford 3 passive electrical commodity groups correspond to Item 77 of the NEI 95-10 passive electrical and l&C commodity groups. Item 77 of NEI 95-10, Appendix 8 meets the 10 CFR 54.21 (a)(1)(i) criterion (i.e., components that perform* an intended function without moving parts or without a change in. configuration);
Cables and connections, bus, electrical portions of electrical and l&C penetration assemblies, fuse holders outside of cabinets of active electrical components. The 230 kV switchyard commodities are not included in the Waterford 3 equipment database because Transmission and Distribution is responsible for their maintenance. However, the following additional switchyard 'commodities meet the 10 CFR 54.21(a)(1)(i) screening criterion:
High voltage insulators (corresponds to Item 87 of NEI 95-10, Appendix 8).
Switchyard bus and connections.
Transmission conductors and connections. All of these commodity groups were subdivided as shown in Table 2.5-1. Other Waterford 3 electrical and l&C commodity groups are active and do not. require aging management review. Electrical and l&C components whose primary function is electrical can also have a mechanical pressure boundary function. These components may include items such as elements, resistance temperature detectors, sensors, thermocouples, transducers, solenoid valves, heaters, and 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-19 _)

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information dryers. According. to Appendix B of NEI 95-10, the .electrical portions of these components are active per 10 CFR 54.21 (a)(1)(i) and are therefore not subject to aging management review. Only the pressure boundary of such an componen(is subject to aging management review, and the pressure boundary function for electrical and l&C components is addressed iri the mechanical review. Electrical components are supported by structural commodities (e.g., cable trays, electrical conduit, or cable trenches.),_which are included in the structural aging management reviews. 2.1.2.3.2 Long-Lived Screening Electrical components and electrical and l&C penetration assemblies included in the Ea'*program per 1 O CFR 50.49 are subject to replacement based on their qualified life.* Therefore, in accordance with* 10 CFR 54.21 (a)(1 )(ii), EQ electrical and l&C compor:ients are not subject fo 'aging management review. EQ electrical and. l&C components are covered by analyses or . calculations that may be time-limited aging analyses (TLAAs) as defined in 1 O CFR Only .that are not in EQ_prog-ram are subject to aging management review-.. 2.1.2.4 Consumables Consumables incluc;te'-such items as packing, gaskets, component sea.ls, 0-rings, structural sealants, oil, grease, component filters, system filters, fire extinguishers, fire hoses, and air. packs. Con.sumables have been evaluated consistent with the information presented in Table 2.1-3.of NUREG-1800. Consumables have t::>een divided into the following four categories for the purpose of license renewal: (a) packing, gaskets, component seals; and 0-rings; (b) structurarsealants; (c)'oil, grease, ;;1nd component filters; and (d) $YStem filters, fire . extinguishers, fire hoses, and air packs. . -: -. . 2.1.2.4.1 Packing. 'Gaskets. Component Seals. and 0-Rings Packing, gaskets, component mechanical seals, and 0-rings are typically used*to-provide a proof seal when components are mechanically joined together. These items are commonly found in components suc_h as valves, pumps, heat exchangers, ventilation *lJni_ts or ducts, and piping segments. * * * ---In accordance with American National Standards Institute (ANSI) 831.1 and the ASME Boiler and Pressure Vessel Co<;le Section Ill, the subcomponents of pressure' retaining components as shown above are not considered pressure-retaining parts. Therefore, these subcomponents not relied on to perform a llcense renewal intended function and are not subject to aging management review. --2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results

Page 2.1-20 2.1.2.4.2 Structural Sealants Waterford Steam E:lectric Station, Unit 3 License Renewal Application Technical Information Elastomers and other materials used as structural sealants are subjeCt to aging management review if they are not periodically replaceq and they perform an intended function, tYpically supporting a pressure boundary; flood barrier, o"r rated fire barrier. Seals and sealants are considered in the aging management review of bulk commodities (Section 2.4.4). 2.1.2.4.3 Oil. Grease. and Component Filters Oil, grease, and component filters have been treated as consumables because either (1) they _are periodically replaced or (2) they are monitored and replaced-based on condition. -_ 2.1.2.4.4 _ System Filters. Fire Extinguishers. Fire Hoses. and Air Packs Components such as system filters, fire hoses, fire extinguishers, self-contained breathing apparatus (SCBA), 'and SCBA cylinders are considered to be consumables and are routinely -tested, inspected, and replaced when* necessary. Fire protection equipment performance criteria at Waterford 3 comply with the applicable safety standards (e.g., 10 CFR 50, Appendix R/ Appendix A to Branch Technical Position BTP-APCSB 9.5. 1 or NFPA 805 (2001 Edition) in accordance with 10 CFR 48(c), NFPA 10 for fire extinguishers, fire hoses and SCBA air _ cylinders, and 29 CFR 1910.134 for respiratory protection), which specify performance and condition monitoring programs for the'se specific components. Fire hoses and fire extinguishers are inspected and hydrostatically periodically and must be_replaced if they do 'not pass test or inspection. SCBA and cylinders are inspeded and periodically tested and must be repaired or replaced if they do not pass the test or inspection. Fire protection and radiation protection procedures specify the replacement criterion of these components that are routinely checked by tests or inspections to assure operability. Therefore, while these consumables are in the scope of license re-newal, they do _not require an aging management review. -. -2.1.3 Interim Staff Guidance Discussion As discussed in NEI 95-10 (Ref. 2.1-8), the NRC has encouraged applicants for license renewal to address proposed interim staff guidance (ISGs) in the LRA. The majority of license related ISGs have been resolveq (Ref. 2.1-9, 2.1-10) with the issuance of revisions to the license renewal guidance documents (Ref. 2.1-2), NUREG-1801(Ref.2.1-3), RG 1.188 (Ref. 2.1:-4), RG 4.2 (Ref. 2.1-11), and NEI 95-10. The remaining ISGs are addressed as follows. LR-ISG-2011-01 Aging Management of Stainless Steel Structures and Compon_ents in Treated Borated Water (Revision 1) This ISG recommends guidance for aging management presented as revisions to selected tables of NUREG-1800 (Ref. 2.1-2) and NUREG-1801(Ref.2.1-3). The revised guidance has been \ 2.0. Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information considered in the integrated plant assessment and is reflected iri the aging management results presented in Section 3. LR-ISG-2011-02 Aging Management Program for Steam Generators This ISG recommends the use of guidance provided in Revision 3 of NEI 97-06, Steam
Generator Program Guidelines, issued after NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3). The ISG also updates NUREG-1800 to reference Revision 3 of Electric Power Research Institute (EPRI) 1019038, Steam Generator Integrity Assessment Guidelines. The Waterford 3 Steam Generator Integrity Program (Section B.1.37) is based on these current steam generator inspection program guidance documents. LR-ISG-2011-03 Generic Aging Lessons Learned (GALL) Report Revision 2 '[Aging Management Program] AMP Xl.M41, "[3uried and Underground Piping and Tanks" . This ISG provides expanded guidance for managing the effects of aging of buried and
underground piping and tanks within the scope of license renewal. This guidance is presented as revisionsto NUREG-1800 (Ref. 2.1-2) and (Ref. 2.1-3). The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program description presented in Appendix B, Section B.1.3, Buried and Underground Piping and Tanks Inspection: LR-ISG-2011-04 Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors *
This ISG updates the guidance for the aging_ management of reactor vessel internals presented in NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3) to be consistent with EPRI 1022863, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," and the associated NRG safety evaluation report. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 .and the aging management program descripti9n. presented in Appendix B, Section B.1.33, Reactor Vessel Internals. ' . . . . LR-ISG-2011-05 Ongoing Review of Operating Experience This ISG establishes a framework for the consideration of operating experience concerning aging management and age-related degradation during the term of a renewed operating license. The ISG provides interim revisions to NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3) to *present new NRC review criteria for the operating experience review. program. Th.e revised guidance is reflected in the description of the process for the review of operating**experience presented in Appendix B, Section B.0.4, Operating Experierice. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation ResuJts Page 2.1-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LR-ISG-2012-01 Wall Thinning due to Erosion Mechanisms This ISG provides additional guidance for managing the effects of wall thinning due to aging mechanisms other than flow-accelerated corrosion (FAG). The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program descriptions presented in Appendix B. LR-ISG-2012-02 Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation This ISG provides guidance on a variety of topics as indicated by the title. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging
management results presented in Section 3 and the aging management program descriptions presented in Appendix B. LR-ISG-2013-01 Aging Management of Loss of Coating or Lining Integrity for Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks This ISG provides guidance related to. loss of coating integrity. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program descriptions presented in Appendix B.
LR-ISG-2015-01 (Draft) Changes to Buried and Underground Piping and Tank Recommendations This ISG provides proposed guidance related to managing loss of mate.rial for the external of buried and underground piping and tanks. Due to the draft nature c:if the ISG and the. timing of its issuance, it was not feasible to include recommended activities from this ISG into the Waterford 3 LRA. 2.1.4 Generic Safety Issues In accordance with the guidance in NEI 95-10. (Ref. 2.1-8), review of _NRC generic safety issues * (GSls) as part of the license renewal process is required to satisfy the finding required by 1 O CFR 54.29. GSls designated as unresolved safety issues (US ls) and High-and Medium-priority issues in NUREG-0933, Append.ix B (Ref. 2.1-5), that involve aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations are to be *addressed in the LRA. A review of the version of NUREG-0933 current six months prior to the license renewal application submittal, including the applicable Generic Issue Management Control System Report (Ref. 2.1-6), determined that there were nq outstanding USls or High-or Medium-priority GSls. Two GSls designated as Active in NUREG-0933, Appendix B, 186 and 193, were reviewed to assure they did not involve aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Item 186, Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants, involves issues related to crane design and operation. Aging effects are not central to these issues. The issue does n*ot involve time limited aging analysis evaluations, including typical crane related TL:AAs such as cyclic loading analyses. This issue was closed on January 27, 2012. (Ref. 2.1-7) Item 193, [Boiling Water Reactor] BWR [Emergency Core Cooling System] ECCS Suction Concerns, addresses the possible failure of low presswe emergency core cooling systems due to unanticipated, large quantities of entrained gas in the suction piping from suppression pools in BWR Mark I containments. This issue is not applicable to Waterford 3. Therefore, there are_ no GSls involving aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations that are relevant to the Waterford 3 license renewal. process. 2.1.5 Conclusion The methods described in Sections 2.1.1 and 1.2 *were used at Waterford 3 to identify systems and structures that are within the scope of license renewal and to identify those
structures and components requiring _aging management review. The methods are -consistent with and satisfy the requirements of 1*0 CFR 54.4 and 10 CFR 54,.21(a)(1). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging .Management Review and Implementation Results 2.1.6 References . .* Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1-1 10 CFR 54_, Re.newal of Operating Licenses for Nuclear Power Plants. 2.1-2 Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. NUREG-1800. U.S. Nuclear Regulatory Commission (NRC). Revision 2. December 2010. 2.1-3 Generic Aging Lessons Learned (GALL) Report. NUREG-1801. U.S. NRC. Revision 2 . . December 2010. 2.1-4 Standard Format and Content for Applications to Nuclear Power Plant Operating Licenses, Regulatory Guide 1.188. U.S. NRC. Revision 1. September.2005. 2.1-5 Resolution ofGeneric Safety Issues (Formerly entitled A Prioritization of Generic Saf(Jty Issues'?. NUREG-0933. (Appendix 8, Applicability of NUREG-0933 to Oper;;lting and Future Reactor Plants, Revision 25, September 30, 2011). U.S. NRC. December"2011, 2.1-6 Generic Issue Management Control System Report For Fiscal Year 2015 3rd Quarter, NRC Agencywide Documents Access and Management System [ADAMS] Accession* number ML 15175A059. 2.1-7 Leeds, E. J., Director, NRC Office of Nuclear Reactor Regulation, to R. W. Borchardt, NRC Executive Director for Operations, "Completion of Generic Issue 186, 'Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants."' Memorandum dated January 27, 2012. NRC ADAMS Accession number ML 113050589. 2.1-8 Industry Guideline on Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule. NEI 95-10. Nuclear Energy Institute. Revision 6. June 2005. 2.1-9 Kuo, P. T. (NRC) to A. Marion (NEI) and D. Lochbaum (Union of Concerned Scientists), Summary of the 2001-20.05 Interim Staff Guidance for License Renewal. Letter dated February 6, 2007. 2.1-10 Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800. NUREG-1950. Table A-8, Summary of Changes to the Updated License Renewal Documents as a Result of License Renewal Interim Staff Guidance (LR-ISG). U.S. NRC. April 2011. 2.1-11 Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications. Regulatory Guide 4.2, Supplement 1. U.S. NRC. Revision 1. June 2013. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation* Results Page 2.1-25 2.2 PLANT LEVEL SCOPING RESULTS Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Tables 2.2-1, 2.2-3, and 2*.2-4 list the mechanicc:il systems, electrical and l&C systems, and structures, that are within the scope of license renewal for Waterford 3. For mechanical systems, a reference is given to the section which describes the system. For electrical systems, no description is necessary since plant electrical systems are in scope by default (see Section 2.5), but a reference to the FSAR is provided where applicable. For structures, a reference is given to the section that includes the structure in the evaluation. Tables 2.2-2 and 2.2..:5 list the systems and structures, respectively, that do not meet the criteria specified in 10 CFR 54.4(a) and are therefore excluded from the scope* of license renewal. For each item on lists, the table also provides a reference (if applicable) to the section of the FSAR that describes the system or structure. For structures with no FSAR reference, a brief description of the building function is given. None of these structures house safety-related equipment nor are they situated such that a failure of the structure would impact a safety function. The list of systems used in these tables and determination of system boundaries is based on the Waterford 3 equipment database. The equipment database is a controlled list of plant systems and components, with each component assigned to one plant system. System intended functions are identified in the section referenced in Table 2.2-1. As needed, system components
are grouped functionally for the aging management review. For example,'ASME Class 1 components in various systems are evaluated with the ASME Class 1 reactor coolant pressure boundary in Section 2.3.1.3, and containment penetrations from various systems are grouped into one containment penetrations review in Section 2.3.2.3. For each system, the discussion under "Components Subject to Aging Management Review" provides further information.* The LRA section describing the system provides references to relevant sections of the FSAR. If the system is described in the FSAR with a different syste'm or under a different system name, an explanation is given. As described in the FSAR, safety-related piping and valves support the pressure boundaries between the containment vessel and the shield building (primary containment), through the . shield building (secondary containment) and across the auxiliary building secondary containment enclosure (secondary containment). For license renewal, these barriers are functionally equivalent and will be referred to as "containment pressure boundary." The safety-related piping and valves have a safety function to "support containment pressure boundary." Nonsafety-related components whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] due to the potential for a physical interaction (see Section 2.1.1.2) are evaluated together by system in the (a)(2) aging management reviews (AMRs). The (a)(2) AM Rs include nonsafety-related components with the potential for spatial interaction with safety-related components as well as components in safety-related systems outside the safety 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information class pressure boundary, such as piping, valves, pumps, and support elements, that are required to be structurally sound in order to maintain the integrity of safety class piping. That is, the system intended function, "Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function" includes the function of components that provide structural/seismic support to directly connected components. The (a)(2) system reviews are presented at the end of the mechanical system sections: Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2); Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2); Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2); and Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Components subject to aging management review are highlighted on license renewal drawings. A list of drawings is provided for each aging management review. For further discussion of license renewal drawings, see Section 2.1.2.1.3. The list of plant structures was developed from a review of plant layout drawings, the FSAR, maintenance rule documentation, and relevant design basis documents. Structure intended functions are identified in the section referenced in Table 2.2-4. Structural commodities associated with mechanical systems, such as pipe supports and insulation, are evaluated with the structural bulk commodities. Because of the bounding approach used for scoping electrical and l&C equipment, all plant electrical and l&C commodities contained in electrical and mechanical systems are in scope by default. Descriptions of each electrical system are not provided. In addition to plant electrical systems, certain switchyard components in the offsite power systems are in scope for support of offsite power recovery following a station blackout. For further information on electrical and l&C systems, see Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Control Systems. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-2 System Code AE ARR ANP ACC AS BD BAM BM svs eve .. CF CHW RFR SCH sec cw cc IA SA CD Waterford Steam Electric Station, Unit 3 License Renewal Application Technical lnformati9n
Table 2.2-1 Mechanical Systems Within the Scope of License Renewal .. System Name LRA Section Describing System *
Air Evacuation Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Airborne Radioactivity Removal Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Annulus Negative Pressure Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Auxiliary Component Cooling Water Section 2.3.3.3, Compon-ent Cooling and Auxiliary Component Coolif')g Water Auxiliary Steam Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Slowdown Section 2.3.4.4, Main Steam Boric Acid Makeup Section 2.3.3.1, Chemical and Volume Control Boron Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Cable Vault & Switchgear Ventilation Section 2.3.3.12, Miscellaneous HVAC * .Chemi.cal and Volume Control Section 2.3.3.1, CheniiC'.al and Volume Control Chemical Feed Section 2.3.3.15, Auxiliary Systems in-Scope for 10 CFR 54.4(a)(2) Chilled Water Section 2.3.3.2, Chilled Water Circulating Water SeCtion 2.3.3.3, Component Cooling and Auxili.ary Component Cooling Water Component Cooling Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water Compressed Air Section 2.3.3.4, Compressed Air Condensate . Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Page 2.2-3 Subject to Aging Management Review and Implementation Results
Waterford Steam Electric station, Unit 3 i License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Code . System LRA Section Describing System CMU Condensate Makeup and Storage Section 2.3.4.1, Condensate Makeup and DW Storage CAP *Containment Atmosphere Purge Section 2.3.3.15, Aµxiliary Systems in Scope for 10 CFR 54.4(a)(2) CAR . Containment Atmosphere Release Section 2.3.3.12, Miscellaneous I-WAC CB Containment Building Section 2.3.3.4, Compressed Air (mechanical components) ccs Containment Cooling heating, ventilation, Section 2.3.3.5, Containment Cooling HVAC and air condi_tioning (HVAC) cs Containment Spray Section 2.3.2.1, Containment Spray CVR Containment Vacuum Relief Section 2.3.2.3, Containment Penetrations CED Control Element Drive Section 2.3.1.1, Reactor Vessel CDC Control Element Drive Mechanism Section.2.3.3.3, Componeht Cooling and* Cooling Auxiliary Compone_nt Cooling Water . HVC Control Room HVAC Section 2.3.3.6, Control Room HVAC DF Decontamination Facility Section 2.3.3.15, Auxiliary Systems in Scope (mechanical components) for 10 CFR 54.4(a)(2) DFO Diesel Fuel Oil Section 2.3.3.8, Fire Protection: Water EBA Emergency Breathing Air Section 2.3.3.4, Compressed Air EFW Emergency Feedwater Section 2.3.4.2, Emergency Feedwater EG Diesel Generator Section 2.3.3.7, Emergency Diesel Generator EGA EGC E:GF EGL FW Feedwater Section 2.3.4.3, Main Feedwater _ FP Fire Protection Section 2.3.3.8, Fire Protection: Water OFP FHS Fuel Handling and Storage Section 2.3.2.3, Containment Penetrations 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-4 System Code HVF FS GWM HVD HRA LRT LWM MS NG PAS PW PMU PSL ARM PRM HVR RCC RC Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Name LRA Section Describing System Fuel Handling Building HVAC Section 2. 3.3.12, Miscellaneous HVAC Fuel Pool Cooling and Purification Section 2.3.3.10, Fuel Pool Cooling and Purification Gaseous Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Hot Machine Shop and Decon Facility Section 2.3.3.15, Auxiliary Systems in Scope Ventilation for 10 CFR 54.4(a)(2) Hydrogen Recombiner and Analyzer Section 2.3.2.3, Containment Penetrations Leak Rate Testing Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Liquio Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Main Steam Section 2.3.4.4, Main Steam Nitrogen Section 2.3.3.11, Nitrogen Post Accident Sampling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Potable Water Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Primary Makeup Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Primary Sampling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Radiation Monitoring Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Reactor Auxiliary Building HVAC Section 2.3.3.12, Miscellaneous HVAC Reactor Cavity Cooling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Reactor Coolant Section 2.3.1, Reactor Coolant System Section 2.3.3.9, Reactor Coolant Pump Oil Collection 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-5 Waterford Steam Electric Station, Unit 3 ' License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Code System Name LRA Section Describing System RS Reheat Steam Section 2.3.4.4, Main Steam RWM Resin Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) SI Safety Injection Sectiori 2.3.2.2, Safety Injection SAN Sanitation System S!3ction 2.3.3.14, Plant Drains SSL Secondary Sampling Section 2.3.3.15, Auxiliary Systems in Scope CTB for 10 CFR 54.4(a)(2) -SBV Shield Building Ventilation Section 2.3.3.12, Miscellaneous HVAC SS Site Security Section 2.3.3.13, Auxiliary Diesel Generator SWM Solid Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) SG Steam Generator Section 2.3.1.4, Steam Generators PME Sump Pump Section 2.3.3.14, Plant Drains SP TW Treated Water Section 2.3.3.8, Fire Protection: Water BO TC Turbine Building Cooling Water Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) HVT Turbine Building HVAC . Section 2.3.3.12, Miscellaneous HVAC 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2*6 System Code AB ABC ABF ABS AFW co CHV CDP CP EH ES LOF 'FHD FHV FPV GG GS HG LOS HVP so HVS SB sew TSW TUR Table 2.2-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Mechanical Systems Not Within the Scope of License Renewal System Name FSAR Reference Auxiliary Boiler None Auxiliary Feedwater System Section 10.4.7 Carbon Dioxide None Chiller Building Ventilation None Condensate Polisher Section 10.4.6 (condensate clean-up system) Electro-Hydraulic Fluid Section 10.2.2.2. 7 Extraction Steam Section 10.2.2.2.6 Feed Pump Lube Oil None Feedwater Heater Drains and Vents Section 10.4.7 Fire Pump House Ventilation None Generator Gas None Gland Seal Section 10.4.3 Hydrogen Section 9.3.7 Lube Oil Storage and Transfer None Polisher Building HVAC None* Seal Oil None Service Building HVAC None Stator Coil Water None Traveling Screens and Wash Section 10.4.5 Turbine Section 10.2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-7 System Code LOG WHV Table 2.2-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Mechanical Systems Not Within the Scope of License* Renewal System Name FSAR Reference Turbine Generator Lube Oil None WaterTreatment Building Ventilation None 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-8 System Code DC . LVD 4KV SSD 7KV ANN ATS CHS CMF CMP CMR CMT COL CPC CRN ELV ESF EM ' ENI FPO GEN HT INI IC ID Table 2.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Plant Electrical and l&C Systems Within the Scope of License Renewal
System Name FSAR Reference 125V DC Distribution Section 8.3.2 208V/120V Low Voltage Distribution
Seetion 8.3.1 4.16KV Electrical Distribution Section 8:3.1 480V Station Service Distribution Section 8.3.1 6.9KV Electrical Distribution Section 8.3.1 Annunciator Section 7.5.1.9.2 / Anticipated Transients without Scram (ATWS) Section 7.8 Chiller Builqing None
Communication Systems Section 9.5.2 Core Operating Limit Supervisory System Section 7:7.1.5 Core Protection Calculator Section 7.2.1.1.2.5 Cranes and Hoists . None. Elevators None Emergency Lighting . Section 9,5.1.2.5 Eng Safety Features Actuation Section 7.3 .. Environmental (Meteorological) Monitoring Section 2.3.3.2 Excore Nuclear Instrumentation Section 7.2.1.1.2.3 Fire Protection Detection Section 9.5.1.2.2 Generator and 25.KV Distribution Section 8.2.1 Heat Tradng None In-Core Nuclear Instrumentation Section 7.7.1.7 Instrument Cabinets None Inverters and Distribution Section 8.3.1 2.0 Scoping and Screening Methodology for Identifying structures and Components
Subject to Aging Management Review and Implementation Results
Page 2.2-9 System Code MT MNl8 *LTN PMC PPS PAC RMS RMC RXC RR RF SM ST [None] UAT VLP WTB Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-3 (Continued) Plant Electrical and l&C Systems Within the Scope of License Renewal .. System Name FSAR Reference Main Transformer Section 8.2.1 Movable In-Core Nuclear Instrumentation None Normal Lighting Distribution Section 9.5.3 Plant Monitoring Computer Appendix7.5A Plant Protection Section 7. 1.1 . 1 Process Analog Control None Radiation Monitoring Section 11.5.2.1 . . Radiation Monitoring Computer Section 11.5.2.1 Reactor Power Cutback Section 7.7.1.9 Reactor Regulating Section 7.7.1.1.1 Refueling None .. Seismic Monitoring Section 3.7.4 Startup Transformer Section 8.2.1 Switchyard Section 8.2.1 Unit Auxiliary Transformer Section 8.2.1 Valve and Loose Parts Monitor Sect,ion 4.4.6.1 Water Treatment. Building None a. Although the MNI system has been abandoned in place, there are still a few electrical components not abandoned. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-10

\ Table 2.2-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical lnforrT)ation Structures Within the Scope of License Renewal Structure Name LRA Section Battery House.230kV Switchyard Section 2.4.3, Turbine Building and Other Structures Component Cooling Water System Structure Section 2.4.2, Nuclear Plant Island Structure Control House 230kv Switchyard. Section 2.4.3; Turbine Building and Other Structures Cranes, Trolleys, Monorails and Hoists Cranes, trolleys, monorails and hoists are evaluated as structural components or * . ' commodities of the structure in which they are located. Fire Pump House Section 2.4.3, Turbine Building and Other Structures '. Fire Water Storage Tank Section i4.3, Turbine Building arid Other. Structures Fuel Handling Building Section 2.4.2, Nuclear Plant Island Structure . . Manholes, Handholes, and Duct banks Section 2.4.3, Turbine Building and Other Structures Nuclear Plant Island .. Structure Section 2.4.2, Nuclear Plant Island Structure . Plant Stack Section 2.4.1, Reactor Building Reactor Auxiiiary Building Section 2.4.2, Nuclear Plant Island Structure Reactor Building Section 2.4.1, Reactor Building . Transformer and Switchyard Support Section 2.4.3, Turl;>ine Building and Other Structures and Foundations T1.,1rbine Building Section 2.4:3, Turbine Buildirig and Other Structures 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-11 Table 2.2-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Structures Not Within the Scope of License Renewal Structure Name Structure Function or FSAR Reference Administration Building Provide space for administrative and support personnel. Administration Building Access Facility Provide office space for security and access for personnel into the protective area. Auxiliary Boiler Foundation Provide support of the oil-fired boiler and accessories for supplying hot water to the plant for heating p_urposes. Batch Oil Tanks Foundation FSAR Section 9.5.1*.1.3 Bulk Chemical Storage Building Provide space for the site bulk chemicals. Chemical Storage Building Provide space for the site water treatment chemicals for the wet cooling tower. Chiller Building Provide space for heating, ventilation and electrical switchgear equipment. Condensate Polisher Building Provide support for the condensate polisher systems* six demineralizer vessels. Condensate Storage Tank Foundation FSAR Section 1.9.37, 9.2.6.2 Construction Support Building Provide office space for construction and various other station personnel. .. Demineralized Water Storage Tank . FSARSection 9.2.3.2 .. Foundation Discharge Structure Provide for a release for water from the condensers and the heat exchangers to be discharged into the Mississippi River downstream of the intake structure. ,Dress Out Building Provide support for personnel dress-out (anti-contamination) measures. Fuel Oil Storage Tank Foundation Provide support for one 100,000 gallon fuel oil storage tank. Generation Support 13uilding Provide space for office and support personnel. Independent Spent Fuel Storage FSAR Section 1.2.2.6, 9.1.5 Installation (ISFSI) Cask Storage Pad Intake Structure FSAR Section 2.4. 1.1, 10.4.5.2 Low-Level Radwaste Storage Facility FSARSection 11.4.10.5 ' Low Volume Waste Water Basin Hold wastewater containing wide ranges in pH and above-normal concentrations of heavy rnetais. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-12 . --- Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-5 (Continued) Structures Not Within the Scope of License Renewal Structure Name Structure Function or FSAR Reference Maintenance Building 230kV Switchyard Provide a work area and office space for the switchyard. Maintenance Support Building Provide space for the electronic repair facility, personnel equipment, and maintenance and storage space for spare parts. Mechanical Maintenance Impound Provide space for the storage of maintenance equipment Building and weld shop. Multiplexer Enclosures FSAR Appendix 7.5A Oil Separator and Separator Pit Provide support for the waste oil collection tank and associated equipment and provide a collection point for the site industrial waste.oil for separation of the oil. Primary and Back-up Meteorological FSAR Section 2.3.3.2 Tower Primary Water Storage Tank Foundation Provide support for a 260,000-gallon water storage tank, which supplies water for various makeup and flushing operations. Radioactive Material Storage Building FSAR_ Section 12.5.2.1 Secondary Make-up Water Degas and Provide support for the degas tank and the associated Transfer Pumps Foundation pumps. Service Building Provide office space and work area for administrative and support personnel. . *; Solidification Facility FSAR Section 11.4.4, 11.4.8 Switching Station Control House Provide a.protected area for the relay panels and batteries .w.hich control the switching station. Tool Room Provide storage area for tools and other equipment used for maintenance. Waste Oil Facility Provide support for the components related to waste oil collection. Water Treatment Building Provide support for the primary water treatment plant and portions of the demineralized water system. West Side Access Facility Provide access to the controlled access area and work space for' radiation protection personnel. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS 2.3.1 Reactor Coolant System System Description The reactor coolant system (RCS) is a pressurized wateneactor with tWo coolant loops. The reactor coolant system circulates coolant in a closed cycle, removing heat from the reactor core and internals and transferring it to the steam generators. In the equipment database, the reactor coolant (RC) system code encompasses the reactor vessel and internals, the reactor coolant loops and pumps, and the pressurizer and related equipment. The steam generators are included in a separate system code (SG). For the purposes of the renewal integrated plant assessment, the equipment in the RC system code will be described and evaluated in three parts: the reactor vessel, the reactor vessel internals, and the remaining reactor coolant system piping and components. The reactor coolant pump (RCP) oil collection system is reviewed in Section 2.3.3.9, Reactor Coolant Pump Oil Collection. The RC system has the following intended functions for 1 O CFR 54.4(a)(1 ).

Provide sufficient core cooling during normal plant evolutions and anticipated operational occurrences to preclude the occurrence of significant core damage. _
Provide a barrier against the release of fission products from the reactor core to the environment.
Support containment pressure boundary. The RC system has the followir:ig intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. -The RC system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (RCP oil collection) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Support the evaluation that demonstrates compliance with the Commission's regulations for pressurized thermal shock (10 CFR 50.61). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Perform functions (maintain pressure boundary and provide core cooling) that demonstrate compliance with the Commission's regulations for fire protection (1 O CFR 50.48) and for station blackout (1 O CFR 50.63). FSAR References Section 3.9.5 Section 4.1 Chapter 5 Section 9.5.1.2.6 (oil collection system) ComoonentS Subject to Aging Management Review The reactor coolant system is reviewed as the following subsystems. The fuel assemblies are periodically replaced based on burnup and are not subject to aging management review.
Section 2.3.1.1, Reactor Vessel
Section 2.3.1.2, Reactor Vessel Internals
Section 2.3.1.3, Reactor Coolant Pressure Boundary.
Section 2.3.1.4, Steam Generators -Norisafety.:.related components of the system not included in other review;:; whose failure could prevent satisfactory accompiishment of safety are reviewed in 2.3.1.5, RCS Systems in Scope for 1 O CFR 54.4(a)(2). * -* < '
r ' 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-2 2.3.1.1 Reactor Vessel Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The review of the reactor vessel includes the vessel (a component in the RC system code) and the control element drive system (system code CED). Reactor Vessel The purpose of the reactor vessel is to enclose and support the reactor vessel internals and the reactor core and to provide a barrier to the release of radioactive materials from the core. The reactor vessel forms part of the reactor coolant pressure boundary, containing the flow path of reactor coolant through the vessel internals and reactor core. The reactor vessel head provides penetrations for the control element assembly (CEA) extension and drive shafts, venting, and in-core instrumentation. The reactor vessel is a right circular cylinder with two hemispherical heads". The lower head is permanently welded to the lower end of the reactor vessel shell. The closure head (also known as the reactor vessel closure head) can be removed to provide access to the reactor vessel *internals. The head flange is drilled to match the vessel flange stud bolt locations. The stud bolts are fitted with spherical washers located between the closure nuts and the head flange. These washers m(3intain stud alignment during bolt-up when flexing of the head must be accommodated. The lower surface of the head flange is machined to provide a mating surface for the vessel closure seals. The vessel flange is a forged ring with a machined ledge on the inside surface to support the core support barrel, which in turn supports the reactor internals and the core. The flange is drilled and tapped to receive the closure studs and is machined to provide a mating surface for the reactor vessel closure seals. An externally tape.red transition section connects the flange to the cylindrical shell. Sealing is accomplished by using two silver-plated, nickel-chromium-iron (NiCrFe) alloy, self-energized 0-rings. Nozzles are provided in the closure head for nuclear instrumentation and control element drive mechanisms. The four inlet and two outlet nozzles are located radially on a common plane just below the vessel flange. Ample thickness in this vessel course provides most of the reinforcement required for the nozzles. Additional reinforcement is provided for the individual nozzle attachments. A boss located around the outlet nozzles on the inside diameter of the vessel wall provides a mating surface for the core support barrel and guides the outlet coolant flow. This boss and the outlet sleeve on the core support barrel are machined to a common contour to minimize reactor coolant bypass leakage. Shell sections are joined to the nozzle region by a transition section.
Snubbers built into the lower portion of the reactor vessel shell limit the amplitude of flow-induced vibration!? in the core support barrel. 2.0 Scoping and Screening Methodology for Identifying *structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The flow skirt (baffle) is a cylinder, perforated with flow holes, and reinforced at the top and bottom with stiffening rings. The flow skirt is used to reduce inequalities in core inlet flow distributions and to prevent formation of large vortices in the lower plenum. The skirt is welded to the bottom head of the pressure vessel. Reactor vessel intended functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. Control Element Drive The purpose of the CED system is to control the position of the control element assemblies as a means of controlling core reactivity and reactor power. The CED system code includes the control element drive mechanism control system components, the control element drive mechanisms (CEDM), and the CEAs. The CEDMs are reviewed as part of the reactor vessel. The CEDMs are magnetic jack type drives used to vertically position and indicate the position of the CEAs in the reactor core. The CEDM pressure housings are part of the reactor coolant pressure boundary. The motor housing assembly of the CEDM is attached to the reactor vessel head nozzle by means of a threaded joint and is seal welded. The upper pressure housing is threaded into the top of the motor housing assembly and seal welded. The upper pressure housing encloses the CEDM extension shaft and contains a vent. The upper pressure housing is threaded into the top of the motor housing assembly and seal welded. The upper pressure housing encloses the CEDM extension shaft and contains a vent. The top of the upper pressure housing is closed by means of a Versa-Vent tube. The CED system has the following intended function for 10 CFR 54.4(a)(1).
Support the reactor coolant pressure boundary. The CED system has no intended functions for 10 CFR 54.4(a)(2) or (a)(3). FSAR References Section 5.3 Section 3.9.4 Section 4.2.2.4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review The following subassemblies of the reactor vessel are subject to aging management review:
Vessel shell
Primary coolant nozzles and nozzle safe ends
Reactor vessel closure head and nozzles
CEDM assembly
lncore instrumentation/heated junction thermocouple-core exit thermocouples (ICl/HJTC-CET)
Interior and exterior attachments The CEAs are periodically replaced based on burnup; as short-lived components, the CEAs are not subject to aging management review. Table 2.3.1-1 lists the component types that require aging management review. Table 3.1.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G172 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-1 Reactor Vessel Componen.ts Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary ICl/HJTC-CET assemblies
Swageloc modified bodies
Compression collar
Hold down nuts Closure head Pressure boundary * .Center dome
Flange Closure head penetrations Pressure boundary
Vent pipe nozzle
CEDM and ICI nozzles Closure head bolting Pressure boundary
Studs
Nuts *Washers Control rod drive assembly Pressure boundary
CEDM motor housing (tube) and upper end fitting *Versa vent assembly
CEDM motor housing lower end fitting ICI assembly Pressure boundary
Flange adaptor *Seal plug
Swageloc* modified body
Compression collar/nut Flow skirt Pressure boundary Nozzles (including safe ends) Pressure boundary
Inlet/outlet 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-1 (Continued) Reactor Vessel Components Subject to Aging Management Review Component Type Intended Function Vessel external attachment Structural support
Vessel support pads Vessel external attachment Pressure boundary
Closure head lifting lugs Vessel internal attachments Structural support
Core stabilizing lugs
Core stop lugs Vessel flange (including core barrel Pressure boundary support ledge) Structural support* Vessel shell assembly (including Pressure boundary welds)
Bottom head -Torus -Dome *Upper shell
Intermediate shell *Lower shell 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-7

/ 2.3.1.2 Reactor Vessel Internals Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the reactor vessel internals is to properly distribute the flow of coolant delivered to the vessel, and to align, support and protect the fuel assemblies. The components of the reactor internals are divided into three major parts consisting of the core support structure assembly, the upper guide structure assembly, and the in-core instrumentation support structure. The flow skirt, although functioning as an integral part of the coolant flow path, is separate from the internals and is welded. to the bottom head of the pressure vessel.

The core support structure assembly consists of the core support barrel and the lower support structure. The core support structure assembly is supported at its upper end by the upper flange of the core 'support barrel, which rests on a ledge in the reactor vessel. The core support barrel has four alignment keys, which align the core support barrel assembly relative to the reactor vessel and reactor vessel head. The lower flange of the core support barrel supports, secures, and positions the lower support structure. The lower support structure provides support for the core by means of a core support plate supported by columns mounted on support beams that transmit the load to the core support barrel lower flange. The core support plate provides support and orientation for the lower ends of the fuel assemblies via alignment pins. The lower end of the core support barrel is restricted from excessive lateral and torsional movement by six snubbers interface with the pressure vessel wall. The core shroud, which provides a flow path for the coolant, is also supported and positioned by the core support plate. The core shroud provides an envelope for the core and limits the amount of coolant bypass flow. The shroud consists of two ring sections welded together and at the bottom to the core support plate. *The upper guide structure assembly consists of the upper guide structure support plate assembly, control element assembly shrouds, holddown spring, and fuel alignment plate. The upper guide structure assembly aligns and supports the upper end of the fuel assemblies, maintains the CEA spacing, holds down the fuel assemblies during operation, and supports the in-core instrumentation plate assembly. The upper end ofthe assembly is a structure consisting of a support flange welded to the top of.a cylinder. A support plate is welded to the inside of the cylinder approximately in the middle. The support plate aligns and supports the upper end of the CEA shrouds. The shrouds extend from the fuel alignment plate to an elevation above lhe upper guide structure support plate. The CEA shrouds consist of a cylindrical upper section welded to a base and a flow channel structure shaped to provide flow passage for the coolant through the fuel alignment plate. The shrouds are bolted to the fuel alignment plate. At the upper guide structure support plate, the shrouds are connected to the plate by spanner nuts. The fuel alignment plate is designed to align the upper ends of the fuel assem.blies and to support and align the lower ends of the* CEA shrouds. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The in-core instrumentation support system begins outside the reactor pressure vessel, penetrates the vessel head, and terminates at the lower end of the fuel assembly. The core instrumentation nozzles are located around the perimeter of the* reactor vessel head. Each instrumentation path is supported over its full length by the external guidance conduit, internal guide tubes, thimble support plate, and thimbles that extend down into selected fuel bundles. The in-core instrumentation is routed so that the detectors are located and spaced throughout the core. The guide tubes and the in-core thimbles are attached to and supported by the thimble support plate assembly. The thimble support plate assembly fits within the confines of the reactor vessel head and rests in the recessed section of the upper guide structure assembly. Above the thimble support plate, the guide tubes bend and are gathered to form stalks that extend into the reactor vessel head instrumentation nozzles. The thimble support plate assembly is raised and lowered during refueling to withdraw and insert all instruments and their thimbles simultaneously. The pressure boundaries for the in-core instrumentation is at the reactor vessel head instrument nozzle closure, where the external electrical connections to the in-core instruments are made. Reactor vessel internals intended functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. FSAR References Section 3.9.5 Components Subject to Aging Management Review The core support structure assembly, the upper guide structure assembly, and the incore instrument support structure are subject to aging management review. Table 2.3.1-2 lists the component types that require aging management review. Table 3.1.2-2 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying* Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-2 Reactor Vessel Internals Components Subject to Aging Management Review *component Type Intended Function Reactor vessel internal connector Structural support components
Bolts, studs, nuts, washers
Locking bars, caps and keys *Dowels *Cap screws .. Lower support structure-assembly Flow distribution
Core support plate Structural support Lower support structure assembly Structural support
Fuel alignment pins
Core support column welds
Deep core support beams
Core support beams * .. .. Core support barrel assembly Structural support
Upper cylinder, including welds
Lower cylinder girth welds .
Lower cylinder axial welds
Upper section flange
Upper section flange weld
Lower section flange
Lower section flange weld
Alignment keys
Snubber assembly shims and pins
Snubber assembly bolt Upper internals assembly ' *Structural support
Upper guide structure SUP,port plate assembly
Fuel alignment plate 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Res'ults Page 2.3-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-2 (Continued) Reactor Vessel Internals Components Subject to Aging Management Review Component Type Intended Function Core shroud assembly Structural support
Shroud vertical plates
Shroud former plates *Welds Core shroud lug and lug inserts Structural support Core shroud lug dowel pins Structural support Upper internals CEA shroud assembly Structural support
Peripheral instrument tubes
Non-peripheral instrument tubes Upper internals assembly Flow distribution
Flow bypass insert assembly Upper internals assembly Structural support
Socket head cap screw (also referred to as CEA shroud bolts) CEA shroud assembly Structural. support
Modified shroud ext. shaft guide sub-assembly -extension shaft *Tube CEA extension shaft guides Structural support Holddown spring Structural support ICI Structural support
Thimble -lower part Reactor vessel internal components not Flow distribution addressed in another line item Structural support 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-11 2.3.1.3 Reactor Coolant Pressure Boundary Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the RCS is to contain and circulate reactor coolant between the reactor core and steam generators and to provide a barrier to the release of radioactive materials from the core. The major components of the system include two parallel heat transfer loops, each containing one steam generator and two reactor coolant pumps; a pressurizer connected to one of the reactor vessel outlet pipes; and associated piping. Effluent discharges from the pressurizer safety valves are condensed and cooled in the quench tank. System pressure is controlled by the pressurizer, Where steam and water are maintained in thermal equilibrium. Steam is formed by energizing immersion heaters in the pressurizer or conden*sed by the pressurizer spray to limit pressure variations caused by contraction or expansion of the reactor coolant. The average temperature of the reactor coolant varies with power level and the fluid expands or contracts, changing the pressurizer water level. The charging pumps and letdown control valves in the chemical and volume control system are used to maintain the programmed pressurizer water level. A continuous but variable letdown purification flow is maintained to keep the RCS chemistry within prescribed limits. Two charging nozzles and a letdown *nozzle are provided on the reactor coolant piping for this operation. The charging flow is also used to alter the boron concentration or correct the chemistry of the reactor coofant. Other reactor coolant loop penetrations are the pressurizer surge line in one reactor vessel outlet pipe; the four safety injection inlet nozzles, one in each reactor vessel inlet pipe; one outlet no.zzle to the shutdown cooling system jn each reactor vessel outlet pipe; tWo pressurizer spray nozzles; vent and drain connections; and sample cor:mections and instrument connections. Overpressure protection for the reactor coolant pressure boundarY is provided .by two loaded safety valves connected to the top of the** pressurizer. These* valves discharge to the quench tank, where the steam is released under water.to be condensed and cooled. If the steam discharge exceeds the capacity of the quench tank, it is relieved to the containment atmosphere through a rupture disc. As stated in FSAR Section 5.2, the reactor coolant pressure boundary (RCPB) is defined in accordance with 10 CFR 50.2(v) to include all pressure* retaining components such as pressure
vessels, piping, pumps, and valves that are: a. Part of the RCS, or 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information b. Connected to the RCS, up to and including any and all of the following: 1. The outermost containment isolation valve in piping which penetrates primary reactor containment. 2. The second of the two valves normally closed during normal reactor operation in system piping which does not penetrate primary reactor containment. 3. The RCS safety valves. -The major Class 1 components of the reactor coolant pressure boundary addressed in this review include the reactor coolant pumps (RCP), reactor coolant piping, pressurizer, pressurizer safety valves, and the Class 1 portions (piping and valves) of systems connected to the RCS, which are the safety* injection system and the chemical and volume contrql system. This review also includes non-Class 1 components of the RCS that have an intended function for license renewal but were not included in another aging management review. RCPB intended -functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. FSAR References Chapter 5 Components Subject to Aging Management Review . . . The non-Class 1 sections of the safety injection system and the chemical and volume control systems are reviewed In Section 2.3.2.2, Saf£;?ty Injection, and Section 2.3.3.1, Chemical and Volume Control; respectively., Nonsafety-related components of the RCPB not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2). Remaining RCPB components are reviewed as listed below.
Table 2.3.1-3 lists the component types that require aging management review Table 3.1.2-3 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-13 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for RCPB components subject to aging management review are provided in the following license renewal drawings. Reactor Coolant Svstem LRA-G172 LRA-G179 LRA-G160 sh 4 (RCP oil coolers, cooling air heat exchangers, and thermal barrier heat exchangers) Safetv Injection Svstem LRA-G167 sh 2 LRA-G 167 sh 4 Chemical and Volume Control Svstem LRA-G 168 sh 1 LRA-G168 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element (non-Class 1) Pressure boundary Heat exchanger coil Pressure boundary (RCP lower oil cooler) Heat exchanger water jacket Pressure boundary (seal heat exchanger) Heat exchanger (channel head) Pressure boundary (RCP upper oil cooler) Heat exchanger (shell) Pressure boundary . (RCP upper oil cooler) Heat exchanger (tube sheet) Pressure boundary (RCP upper oil cooler) Heat exchanger (tubes) Pressure boundary (RCP upper oil cooler) Heat exchanger (tubes) Pressure boundary (RCP motor air cooler) Heat exchanger (channel head) Pressure boundary (RCP motor air cooler) Heat exchanger (tube sheet) Pressure boundary (RCP motor air cooler) Orifice Flow control Pressure boundary Piping 4 inch nominal pipe Pressure boundary size (NPS) Piping < 4 inch NPS Pressure boundary Piping (non-Class 1) Pressure boundary Piping (non-Class 1) Pressure boundary (RCP lower oil cooler) Piping (non-Class 1) Pressure boundary (RV flange leak off lines) 2.0 Scoping and Screening Methodology for Identifying Structures and Components. Subject to Aging Management Review and Implementation Results Page 2.3-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 (Continued) Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Pressurizer heater sheath Pressure boundary Pressurizer heater sleeve end Pressure boundary caps Pressurizer heater plug, heater Pressure boundary sleeves and heater sheath to sleeve welds Pressurizer heater internal Structural support support structures Pressurizer instrument nozzle Pressure boundary Pressurizer lower head Pressure boundary Pressurizer manway cover Pressure boundary . Pressurizer manway gasket Pressure boundary' retainer plate Pressurizer nozzles (spray Pressure boundary_ nozzle, surge nozzle, safety nozzle) Pressurizer shell and upper Pressure boundary head Pressurizer spray head Flow control Pressurizer support skirt Structural support Pressurizer welds
Pressure boundary -Instrument.sleeve to instrument -Nozzle to safe-end weld overlays RCS piping hot leg -Overlay welds Pump casing (RCP) Pressure boundary Pump cover (RCP) Pressure boundary RCS cold leg Welds Pressure boundary 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-16 Waterford Steam El.ectric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 {Continued) Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Safe end (pressurizer spray, Pressure boundary , drain, pressurizer instrument nozzles) Safe end (hot leg and Pressure boundary pressurizer surge, shutdown cooling and pressurizer safety) Thermal sleeve (charging, Structural integrity safety injection, surge, pressurizer spray) Therm owe II Pressure boundary Tubing (hon-Class 1) Pressure boundary Valve body::, 4 inch NPS Pressure boundary Valve body < 4 inch NPS Pressure boundary Valve body (non-Class 1) Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.1.4 Steam Generators Description The purpose of the steam generator (SG) system is to transfer heat from the RCS to the* secondary system coolant. Feedwater heated in the steam generators is converted to steam that drives the main turbine generator. Each steam generator is a vertical, inverted U-tube heat exchanger. Reactor coolant flows through the tubes while the secondary system coolant is on the shell side. Reactor coolant enters at the bottom of each steam generator through the single inlet nozzle, flows upward throl1gh the U-tubes, and leaves through the two outlet nozzles. A vertical divider plate separates the inlet and outlet plenums in the lower head. enters the steam generator through the feedwater nozzle where it is distributed via a feedwater distribution ring. The feedwater ring is constructed with discharge nozzles which discharge at the top of the feedwater ring. The down comer in the steam generator is *an annular passage fanned by the inner surface of the steam generator shell and the cylindrical shell that encloses the vertical U-tubes, Upon exiting from the bottom .of the down comer, the secondary flow is directed upward over the vertical U-tubes. Heattrahsferred from the primary side converts a portion of the secondary flow into steam. Upon leaving the vertical U-tube heat transfer surface, the steam-water mixture enters the -* centrifugal-type separators. These impart a centrifugal motion to the mixture and separate the water particles from the steam. The water exits from the perforated separator housing and combines with the feedwater to repeat the cycle. Final drying of the is accomplished by passage of the steam *through the single-tier banked dryers. . . The steam. generators contain an integral flow limiting .device consisting of seven venturis installed in the steam outlet nozzle. This flow restr:ictor reduces energy release to containment and foads oh the steam generator internals during a postulated steam line break while also limiting the RCS cooldown rate.
Manways and handtioles are provided for access to the steam.generator internals. The SG system has the following intended fun.ctions for 10 CFR 54.4(a)(1). . .
Transfer heat from the reactor coolant system to the secondary system. 2.0 Scoping anc;I Screening Methodology for Identifying Structures and Components Subject to Af!ing Management Review and Implementation Results Page 2.3-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Limit steam release after a steam line guillotine break to reduce energy release to containment, reduce loads 'on the steam generator internals, and limit RCS cooldown following steam line rupture.
Maintain secondary system pressure boundary.
Provide a source of steam for the turbine-driven emergency feedwater pump.
Maintain the reactor coolant pressure boundary. The SG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SG system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 5.4.2 Components Subject to Aging Management Review Reactor coolant inlet and outlet piping and Class 1 instrumentation is reviewed in Section 2.3.1.3, Reactor Coolant Pressure Boundary. Other SG instrumentation components are reviewed in Section 2.3.4.3, Main Feedwater. SG blowdown and sampling components are evaluated in Section 2.3.4.4, Main Steam. Nonsafety-related SG components whose failure could prevent satisfactory accomplishment of safety functions not reviewed in other reports are reviewed in Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2). Remaining steam generator components are reviewed as listed below. Table 2.3.1-4 lists the steam generator components that require aging management review and their intended functions. Table 3.1.2-4 provides the results of the aging management review for steam generator components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-19 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for steam generator components subject to aging management review are provided in the following license renewal drawings. Reactor Coolant Svstem LRA-G172 Main Steam Svstem LRA-G151 sh 1 LRA-G 164 sh 5 Main Feedwater Svstem LRA-G 153 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 Steam Generators Components Subject to Aging Management Review Cc;>mponent Type Intended Function Pressure boundary closure Pressure boundary bolting Tubesheet Pressure boundary Tube to tubesheet weld Pressure boundary Channel head Pressure boundary Partition plate Pressure boundary Primary inlet and outlet nozzle Pressure boundary transition pieces Primary side pressure nozzle Pressure boundary Inlet and outlet nozzle dam Pressure boundary rings Primary manway drain tube Pressure boundary Primary manway cover Pressure boundary Primary manway insert Pressure boundary Tubes Heat transfer Pressure boundary ' Tube plugs Pressure boundary Secondary shell (elliptical head Pressure boundary with integral steam nozzle, upper, intermediate and lower shells, transition cone) Flow limiter insert Pressure boundary Feedwater nozzle Pressure boundary Feedwater nozzle thermal Pressure boundary sleeve Instrument and sampling Pressure boundary nozzles Slowdown nozzle Pressure boundary 2.0 s'coping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-21
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 (Continued)
Steam Generators Components Subject to Aging Management Review Component Type Intended Function Secondary manway, handhole, Pressure boundary inspection port, and recirculation nozzles -* Seeondary manway, .. boundar-Y inspection port, and recirculation nozzle cover plates<a)
Handhole ancl inspection port cover plates(b) Pressure boundary Hand hole and inspection* port Pressure boundary diapnragmi; External shell attachments Pressure boundary Tube support plates, anti-Structural integrity vibration assembly bars Wrapper barrel, associated Structural integrity components Recirculation sleeve, Structural integrity wrapper plug seal plates Anti-vibration assembly end
Structural integrity caps, retaining rings, retaining bars, stayrod washer, tube support plate shim Stayrods, wedges, tube Structural integrity support components Feedwater header and support Structural integrity components Feedwater spray nozzles, Structural integrity nozzle caps, filler plates Primary separator assembly Structural integrity components Drain bucket assembly Structural integrity components 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 (Continued) Steam Generators Components Subject to Aging Management Review Component Type Intended Function Lower deck components StruCtural integrity Middle deck components Structural integrity Sludge collector assembly Structural integrity Secondary separator Structural integrity components Pedestal support Structural support Snubber lug, key bracket Structural support a. Cover plates in this line apply only to ones without seal welded diaphragms.
b. Cover plates in this line apply only to ones with seal welded diaphragms. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-23

\. 2.3.1.5 RCS Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Phvsical Failure This section summarizes the scoping and screening results for RCS systems based on 1 O CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.2 and 2.1.2.1.2. Phvsical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-24 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information criterion affected RCS. systems, those systems are within the scope of license renewal per 10 CFR 54.4(a)(2). Leakage or Spray Nonsafety-related portions o.f safety-related systems containing water, oil, or steam are considered within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. RCS systems meeting this criterion are within the scope of license renewal per 1 O CFR 54.4(a)(2). The RC system and the SG system are within the scope of licen_se renewal based on the criterion of 10 CFR 54.4(a)(2) for physical interactions. System Descriptions The RC system is described in Section 2.3.1, Reactor Coolant System and Section 2.3.1.3, Reactor Coolant Pressure Boundary. The SG system is described in Section 2.3.1.4, Steam Generators. ' Certain nonsafety-related components in these systems are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) because of the potential for physical interactions between nonsafety-related components and safety-:related equipment. FSAR References FSAR references are provided in the sections referenced above. Components Subject to Aging Management Review

For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-25
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (4) An endpoint of a plant-specific piping design analysis to ensure that forces and moments are restrained in three orthogonal directions. For spatial interaction, components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 1 O CFR 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in a system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 10 CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related SSCs directly connected to safety-related SSCs. Series 2.3.1-5-x tables list the RCS. component types that require aging management review for 1 O CFR 54.4(a)(2) based on potential for physical interactions. . . Series* 3.1.2-5-x tables provide the results of the aging management review for the RCS for 10 CFR 54.4(a)(2) based on potential for physical interactions. System Code System Name Component Types AMR Results RC Reactor Coolant Table 2.3.1-5-1 Table 3.1.2-5-1 SG Steam* Generators Table 2.3.1-5-2 Table 3.1.2-5-2 License Renewal Drawings Additional details for components subject tq aging management review are provided in the following license renewal drawings.
System Code System Name LRA Drawings RC Reactor Coolant LRA-G172 LRA-G179 SG Steam Generators LRA-G162 sh 2 LRA-G164 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-26 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting_ Pressure boundary Filter housing Pressure boundary Flex hose Pressure boundary Orifice Pressure boundary Piping Pressure boundary . Pump casing Pressure boundary Rupture disc Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-27 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-5-2 Steam Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-28 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.2 Engineered Safety Features The following Engineered Safety Features systems are described in this section.
Section 2.3.2.1, Containment Spray
Section 2.3.2.2, Safety Injection
Section 2.3.2.3, Containment Penetrations
Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-29 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.2.1 Containment Spray System Description The purpose of the containment spray (CS) system is to remove heat from containment following an accident inside containment. In conjunction with the containment cooling heating, ventilation and air conditioning (HVAC) system, the CS system maintains the containment pressure and temperature within design limits and limits offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CS system also limits offsite radiation doses by the reduction of iodine in the post-accident containment atmosphere. The CS system consists of two independent and redundant loops, each containing a CS pump, shutdown cooling heat exchanger, piping, valves, spray headers, and spray nozzles. There are two headers, each with four spray rings. Each header conforms to the shape of the containment dome. When actuated following an accident, the system has two modes of operation: the injection mode and the recirculation mode. In the injection mode, the system pumps borated water from the refueling water storage pool (RWSP) into the spray headers and through the spray nozzles in the containment dome. When the water reaches the containment floors, it drains toward the safety injection system sump. After low level is reached in the RWSP, the recirculation mode is initiated in which suction for the CS pumps is aligned to the* safety injection system sump. During the recirculation mode, the spray water is cooled by the shutdown cooling heat exchangers prior to its discharge into the containment. The shutdown cooling heat exchangers are cooled by the component cooling water system. The pH of water that is circulated within the containment during the recirculation mode is controlled to minimize re-evolution of iodine scrubbed from the containment atmosphere by the spray. Trisodium phosphate dodecahydrate (TSP) is stored in the containment in multiple stainless steel baskets located on the-11 ft. MSL elevation. TSP is dissolved by the containment spray water and other water draining toward the safety injection system sump and thus raises pH of the recirculated water. The CS system has the following intended functions for 10 CFR 54.4(a)(1).
Remove heat to maintain the containment pressure and temperature within design limits and limit offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment.
Remove iodine from the containment atmosphere and retain it in solution to limit dose consequences. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Support containment pressure boundary. The CS system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory *accomplishment.of a safety function. The CS system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (shutdown cooling heat exchanger) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.2.2 Section 6.5.2 Components Subject to Aging Management Review The TSP baskets are evaluated as structural components in Section 2.4.1, Reactor Building. The RWSP is a structural component and is reviewed in Section 2.4.2, Nuclear Plant Island Structure. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2). Remaining CS system components are reviewed as listed below.
Table 2.3.2-1 lists the_component types that require aging management review. Table 3.2.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 3 LRA-G163 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-1 Containment Spray System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Heatexchanger(channelhead) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heat exchanger (water jacket) Heat transfer Pressure boundary Nozzle Flow control Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Separator Filtration Pressure boundary Therm owe II Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-32 2.3.2.2 Safety Injection System Description Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information The purpose of the safety injection (SI) system is to provide core cooling following a design basis accident. The system is designed to inject borated water into the reactor coolant system to flood and cool the reactor core and to provide heat removal from the core for extended periods following a loss of coolant accident (LOCA). The system is also designed to inject borated water into the reactor coolant system to increase the shutdown margin following a rapid cooldown due to a main steam line break. In addition to its accident related functions, portions of the safety injection system are used as part of the shutdown cooling system, which removes heat from the RCS during norm.al plant cooldown and refueling. The safety injection system is comprised of.the following three separate subsystems:
High pressure safety injection system (HPSI)
tow pressure safety injection system (LPSI)
Safety injection tanks (SITs) The components of these subsystems are arranged ih two redundant, full-capacity trains; each functionally identical to the other. rhe major components of t!iis system are three HPSI pumps, two LPSI pumps, four safety injection tanks, high-pressure injection valves, low-pressure injection valves, and the refueling water storage pool (RWSP). In addition, the system uses the shutdown cooling heat *exchangers, which are part of the containment spray system. The SI system is in standby during normal operation: SI system operation is initiated by either low reactor coolant system pressure or high containment pressure. Actuation of the system starts the.HPSI and LPSI pumps and opens the valves that provide a flow path from the RWSP through these pumps to the reactor coolant system. When a low level is sensed in the RWSP,. the LPSI pumps are stopped, .and the HPSI pump suction is diverted to the safety injection sump in containment for recirculation of coolant. The safety injection tanks contain borated water pressurized by nitrogen cover gas. When RCS pressure drops below the SIT cover pressure, the SITs automatically discharge their contents into the RCS. The primary function of the HPSI system is to inject borated water into the RCS if a break occurs in the RCS boundary. For small breaks, the RCS pressure remains high for a long period of time following the accident, and the HPSI system ensures that the injected flow is sufficient to maintain core cooling. The HPSI system is also used to maintain a borated water cover over the core for extended periods during recir?ulation mode following a LOCA. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The HPSI system is arranged in two redundant trains. The HPSI pump in each train can supply water to the RCS from either the RWSP or the safety injection sump. From the HPSI pump discharge, each header splits into four RCS cold leg injection lines and one hot leg injection line.
Upon initiation of safety injection, the HPSI pumps will discharge to all four RCS cold legs. For long-term core cooling, the HPSI system is realigned for simultaneous hot and cold leg injection. A third HPSI pump, which may be aligned to either train, is provided as an installed spare. Each pump is also supplied with a recirculation flow path back to the RWSP to ensure minimum flow rates .through the pump when operating at shut-off head conditions. The LPSI system serves two functions. One is to inject large quantities of borated water into the RCS in the event of a large pipe rupture. The LPSI system delivers water from the RWSP to the RCS, via the RCS safety injection nozzles, when system pressure falls below pump shut..:off head. The other function is to provide shutdown cooling flow through the reactor core and shutdown cooling* heat exchanger for nornial plant shutdown cooling operation or as required for long-term core cooling for small breaks. During shutdown cooling, a portion of the reactor coolant from the RCS _hot legs is circulated by the LPSI pumps through the shutdown cooling
heat exchangers to the LPSI headers and is returned to the RCS cold legs through the safety injection nozzles. The HPSI and LPSI systems are similarly aligned to the RWSP and safety injection sump.* However, the discharge of each LPSI pump is directed to only two oHhe four RCS cold legs. The LPSI pumps are also supplied _with a minimum recirculation flow path to the RWSP. The four safety injection tanks used to flood the core with borated water following depressurization as a result of a LOCA or main steam line *break . Flow from each of the tanks is directed through a check valve and outlet valve to a single RCS cold leg via a safety
injection nozzle located on the RCS piping near the reactor vessel inlet. The SI system has the following intended functions for 10 CFR 54.4(a)(1).
Inject borated water into the reactor coolant system to flood and cool the reactor core and to provide heat removal from the core for extended periods following a LOCA.
Inject borated water into the reactor coolant system to increase the shutdown margin following a rapid cooldown due to an MSLB.
Provide shutdown cooling flow through the reactor core and shutdown cooling heat exchanger for normal plant shutdown cooling operation.
Maintain integrity of reactor coolant pressure boundary.
Support containment pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-34 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The SI system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SI system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (shutdown cooling mode) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.3 Section 9.3 .. 6 (shutdown cooling) Components Subject to Aging Management Review Class 1 components supporting the reactor coolant pressure boundary are reviewed in Section
2.3.-1.3, Reactor Coolant Pressure Boundary. The RWSP is a structural component and is reviewed in Section 2.4.2, Nucilear Plant Island Structure. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.2.4, ESF Systems in Scope for 10 CFR 54.4(a)(2).
Remaining SI system components are reviewed as listed below.
Table 2.3.2-2 lists the component types that require aging management review. Table 3.2.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 3 LRA-G 162 sh 1 LRA-G163 LRA-G 167 sh 1 LRA-G 167 sh 2 LRA-G167 sh 3 LRA-G 167 sh 4 LRA-G 168 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-35 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-2 Safety Injection System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Flow control Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-36 2.3.2.3 Containment Penetrations System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As described in FSAR Chapter 3, Section 3.8, the primary containment is a free-standing steel pressure vessel which is surrounded by a reinforced concrete shield building. The containment vessel is a cylindrical steel pressure vessel with hemispherical dome and ellipsoidal bottom that houses the reactor pressure vessel, the reactor coolant piping, the pressurizer, the quench tank, the reactor coolant pumps, the steam generators, and the safety injection tanks. It is completely enclosed by the reinforced concrete shield building. An annular space is provided between the walls and domes of the containment vessel and the concrete shield building to permit construction operations and in-service inspection. The containment vessel and shield building contain mechanical penetrations that provide openings for process fluids to pass through the containment boundaries and still maintain containment integrity. The mechanical penetrations, their associated isolation valves, and related design features that are not included in another aging management review are included in this review. The grouping of containment isolation valves from various plant systems into a consolidated review is appropriate for scoping as indicated in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Section 2.1.3.1. Systems described or referenced below have the following intended function for 10 CFR 54.4(a)(1 ).
Support containment pressure boundary .. With the exception of the containment vacuum relief (CVR) system, the systems described below. have no other system intended *functions. Systems described elsewhere in the application have additional intended functions included in other aging management reviews as referenced. Containment Vacuum Relief The purpose of the containment vacuum relief (CVR) system is used to prevent excess external pressure on the primary containment steel shell. The system consists of two redundant penetrations that connect the shield building annulus with the containment atmosphere. The penetrations provide a flow path for air to pass from the annulus to the containment. Each flow path is provided with its own set of isolation valves, which remain closed during normal operation. In the event that the air pressure inside containment drops below that of the annulus, system instrumentation opens the automatic isolation valves, which allow air pressure in the annulus to bleed into the containment. Pneumatic operated butterfly valves are installed on the annulus side of the containment penetrations. These valves serve as both automatic relief valves and containment isolation 2.0 Scoping and Screening rviethodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-37 i \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information valves. The valves are provided with backup air accumulators that will allow valve operation in the event of a loss of instrument air. Check valves are installed on the containment side of the penetrations and serve as containment isolation valves. The valves have magnetic latches that hold the valve in the close position, but the valves will open quickly against a small differential pressure. In addition to the intended function of supporting containment pressure boundary, the CVR system has the*following .intended function for 10 CFR 54.4(a)(1).
Protect the containment vessel from external pressure by limiting the pressure differential between the shield building annulus and containment atmosphere. Fuel Handling and Storage The purpose of the fuel handling and storage (FHS) system is to. provide the ability to defuel and refuel the reactor core. The FHS system provides a safe, effective means of transporting, handling and storing fuel and control element assemblies. The majority of the components in the FHS system code are structural components and are covered in the structural aging management reviews. The fuel transfer tube and blind flange-are considered part of this system code. These components form part of the containment pressure boundary. Hvdroqen Recombiners and Analyzers
The purpose of the hydrogen recombiners and analyzers (HRA) system is to monitor the hydrogen gas concentration in the containment and limit that concentration by recombination with oxygen. The stationary thermal recombiners each consist of an inlet pre-heater section,* a heater-rec.ombination section, and a louvered exhaust chamber. They are designed and . operated on the principle of natural convection, requiring no moving parts. The system includes two hydrogen analyzers. Each consists of sample and return lines, isolation valves, and a hydrogen analyzer that includes sample coolers, moisture separators, and sample pumps. For each unit there are seven sample lin.es which take six separate samples of the containment atmosphere and one sample of the annulus atmosphere. Each set of six lines has a common header inside the containment and penetrates the containment in a separate penetration assembly.*
The hydrogen recombiners and analyzer components are classified as*safety-related. However, consistent with changes to 1 O CFR 50.44, Amendment 192 to the Waterford 3 operating license eliminated the requirement for these components to mitigate the consequences of a design basis accident. Consequently, apart from support of the containment pressure boundary, the HRA system has no safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplementa'tion Results Page 2.3-38 Waterford Steam Electric Station, Unit 3 License Renewal Application Tec_hnical Information Other Systems Described Elsewhere in the Application The following systems have containment penetrations included in this review of containment penetrations. Each of these systems is described in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). System Code ANP ARM BM CAP GWM LRT PMU PSL FSAR References Section 3.8 Containment Vacuum Relief Section 3.8.2.3 Section 6.2.1.1.2 System Name Annulus Negative Pressure Area Radiation Monitoring (see Radiation Monitoring) Boron Management Containment Atmosphere Purge Gaseous Waste Management Leak Rate Testing Primary Makeup Primary Sampling Fuel Handling and Storage Section 9.1.4 Hydrogen Recombiners and Analyzers Section 6.2.5.2.1 Section 6.2.5.2.2 Components Subject to Aging Management Review The structural portions of the containment penetrations (penetration pipe sleeves) are addressed in Section 2.4.1, Reactor Building. The internals of electrical penetration assemblies are reviewed in Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Control Systems. Containment penetration components that support intended functions for other systems are evaluated with their respective systems. Containment penetration components in the Class 1 boundary are reviewed in Section 2.3.1.3, Reactor Coolant Pressure Boundary. Remaining containment penetration components are reviewed as listed below. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-39 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-3 lists the component types that require aging management review. Table 3.2.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G161 sh 2 LRA-G 164 sh 1 LRA-G 170 sh 4 LRA-G853 sh 1 LRA-G 162 sh 2 LRA-G 164 sh 2 LRA-G171 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-40 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-3 Containment Penetrations Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-41 2.3.2.4 ESF Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SS Cs which could* impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Physical Failures This section summarizes the scoping and screening results for ESF systems based on 10 CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures may be related to structural support or t6 spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. _Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically
piping systems) are within the scope of license renewa.1 based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.2 and 2.1.2.1.2. Physical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are . reviewed in Section 2.4, Scoping and Screening Results: Structures.
Pipe Whip. Jet Impingement, or Harsh Environments Systems conta!ning nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-42 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information criterion affected ESF systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Sprav Nonsafety-related portions of safety-related systems containing water, oil, or steam are considered within the scope of license renew,al based on the criterion of 1 O CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. ESF systems meeting this criterion are within the scope of license renewal per 10 CFR 54.4(a)(2). The following ESF systems, described in the referenced sections, are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) for physical interactions.
Section 2.3.2.1, Containment Spray
Section 2.3.2.2, Safety Injection System Descriptions The ESF systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) because of the potential for physical interactions between nonsafety-related components and safety,..related equipment are described in the sections referenced above. FSAR References For FSAR references for these systems, see the sections referenced above. Components Subject to Aging Management Review For each safety-to-nonsafety interface, nonsafety-related components connected to re.lated components were included up to one of the foJlowing: (1) The first seismic anchor, which is defined as a devi".e or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point thaf encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-43 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (4) An endpoint of a plant-specific piping design analysis to ensure that forces and. moments are restrained. in three or:thogonal directions. For spatial interaction, ESF system components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 10 CFR 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in an ESF system does not fail or assumes failure only at specific locations, then that piping is Within the scope of license renewal per 1 O CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 1 a* CFR 54..4(a)(2), the intended function of pressure . boundary includes maintaining structural integrity for components that are included for related SSCs d_irectly connected to safety-related SSCs. . . Series 2 .. 3.2-4-x tables list the component types for ESF systems.that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. Series 3.2.2-4-x fables provide the results of the aging management review for ESF systems for 10 CFR 54.4(a)(2) based on potential for physical interactions. Code System Name Component Types AMR Results cs Containr:nent Spray Table 2.3.2-4-1 Table 3.2.2-4-1 SI *Safety Injection Table 2.3.2-4-2 Table 3.2.2-4-2 License Renewal Drawings Additipnal details for components subject to aging management review are provided in the following license renewal drawings. System Code System Name LRA [)rawings cs Containment Spray LRA-G163 SI Safety Injection LRA-G-167 sh 1 LRA-G-167 sh 2 LRA-G-167 sh 3 2.0
Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-44 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .. ---Component Type Intended Function Bolting Pressure boundary Orifice. Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tubing Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review anci Implementation Results page 2.3-45 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-4-2 Safety Injection System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-46 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information 2.3.3 Auxiliarv Systems The following systems are described in this section.
Section 2.3.3.1, Chemical and Volume Control
Section 2.3.3.2, Chilled Water
Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water
Section 2.3.,3.4, Compressed Air
Section 2.3.3.5, Containment Cooling HVAC
Section 2.3.3.6, Control Room HVAC
Section 2.3.3.7, Emergency Diesel Generator
Section 2.3.3.8, Fire Protection:.Water
Section 2.3.3.9, Reactor Coolant Pump Oil Collection
Section 2.3.3.10, Fuel Pool Cooling and Purification
Section 2.3.3.11, Nitrogen
Section 2.3.3.12, Miscellaneous HVAC
Section 2.3.3.13, Auxiliary Diesel Generator
Section 2.3.3.14, Plant Drains
Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-47 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.1 Chemical and Volume Control System Description This review includes the chemical and volume control system and the boric acid makeup system. Chemical and Volume Control The purpose of the chemical and volume control (system code CVC) system is to control the reactor coolant system (RCS) inventory, purity arid chemistry. Parfof the reactor coolant is bypassed through the CVC system via regenerative and letdown heat exchangers, which reduce the reactor coolant temperature before it passes through a filter and ion exchangers to purify the coolant. The purified coolant qm be sent to the volume control tank or diverted to the boron manage-ment system if necessary to reduce RCS inventory. Chemicals or additional coolant (e.g., primary water and boric acid) can be added to the volume control tank to adjust RCS che-mistry or increase inventory.* The charging pumps take suction from the volume control tank and pump the coolant back into the reactor coolant system. Discharge from the charging pumps is normally returned through the regenerative heat exchanger-to the reactor coolant system flow stream betWeen the reactor coolant pumps and the -reactor vessel. Charging pump flow can also be returned to the system as auxiliary pressurizer spray for operator control of RCS pressure during final stages of shutdown and to allow -pressurizer cooling* during normal operation and following an accident. -* The eve system also collects controlled bleed-off from the reactor coolant pump seals. The bleed-off flow is routed to the volume 9ontrol tank and then returned to the RCS. Degasification of the reactor coolant can be performed by venting the volume control-tank to'the gas surge header of the gaseous waste management system. Chemicals such as zinc (Zn) and hydrazine can be added after the volume control tank and pumped directly into the RCS via'the charging pumps. *The boric acid makeup (BAM) system works With the eve system to control reacfor coolant boron concentration. Concentrated boric acid from the BAM system can be added to the volume control tank to mix with the reactor coolant, or it can be delivered to the suction of the charging pumps for rapid injection into the RCS on receipt of a safety injection actuation signal. Some components of the CVC system form part of the reactor coolant pressure boundary. Other CVC system components are part of the containment pressure boundary. The CVC system has the following intended functions for 10 CFR 54.4(a)(1).
Maintain the rea_ctor coolant system inventory. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.3-48 Waterford Steam Electric Station, Unit 3 ( License Renewal Application Technical Information
Control boron concentration in the reactor coolant system.
Provide auxiliary pressurizer spray.
boric into the reactor coolant system upon a safety injection actuation signal.
Maintain integrity of reactor coolant pressure boundary.
Support containment pressure boundary. The CVC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity. of nonsafety-related components such that no physical interaction with safety-related components could prevent satisf(!ctorY. accomplishment of a safety function. The CVC system has the following intended functions for 10 eFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48); * . Perform a function* (letdown isolation) that demonstrates compliance with the Commission's reguiations for station blackout (1 O eFR 50.63). Boric Acid Makeup The purpose of the boric acid makeup (BAM) system is to provide a source of concentrated boric acid for RCS reactivity control and shutdown margin requirements. As .part of the chemical and volume control (CVC) syster:n, the BAM system can supply boric acid to the RCS through the
volume control tank and charging pumps for normal makeup, or directly through the charging pumps if necessary for load changes or shutdown margin control following an.accident. The BAM system includes the boric acid batching tank, boric acid makeup tanks, bori.c acid makeup pumps, and th\3 related piping,, valves, instruments and controls. The BAM system has the following intended function for 10 CFR 54.4(a)(1).
Provide a source of concentrated boric acid to the eve system for RCS reactivity control and shutdown margin requirements. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-49 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The BAM system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The BAM system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 9.3.4 *Section 9.3.4.2.1.2 (BAM described as a makeup system) Components Subject to Aging Management Review Class 1 components supporting the reactor coolant pressure boundary are reviewed in Section 2.3.1.3, Reactor Coolant Pressure BoundaJ"Y. CVC system components. that support safety injection system intended functions are reviewed in Section 2.3.2.2, Safety Injection. related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2). Remaining eve and BAM system components are reviewed as llsted below. Table 2.3.3-1 lists the component types that require aging management review. Table 3.3.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 1 LRA-G 162 sh 5 LRA-G163 LRA-G167 sh 3 LRA-G 168 sh 1 LRA-G 168 sh 2 LRA-G 168 sh 3 LRA-G171 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-50 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-1 Chemical and Volume Control System Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundaiy Bolting Pressure boundary Demineralizer Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Gear box housing Pressure boundary Heatexchanger(channel head) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exqhanger (tubes) Heat t(ansfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer: Filtration Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-51 --.,

2.3.3.2 'chilled Water System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the chilled water system is to provide chilled water for air handling systems in various parts of the reactor auxiliary building. There are two separate chilled water systems, the essential chilled water system and the supplementary chilled water system, with components from four different system codes: CHW (chilled water), RFR (refrigeration), SCC (supplementary chiller condensing) and SCH (supplementary chilled water). Essential Chilled Water Svstem The purpose of the essential chilled water system is to provide chilled water for those air handling systems which cool spaces containing equipment required for safety-related operations: The essential chilled water system furnishes chilled water for space cooling purposes and rejects heat through the component cooling water system. The essential chilled water system includes components in system codes CHW and RFR. The system consists of three full-capacity water chiller subsystems, each consisting of one chiller, pump, and expansion tank with level control actuated makeup,* and instrumentation and controls, piping and valves. Additionally, for corrosion protection, each subsystem provided with an individual and integral chemical feed system consisting. of a chemical feed tank, chemical feed and drain piping .. arid all necessary valves, fittings, accessories and appurtenances. The chiller's cool water is pumped to the cooling coils of the air handling units in various parts of the reactor auxiliary building. The safety-related chilled water loads are separated into two loops. The flow path can be aligned so that any two of the three water chiller subsystems can supply chilled water to the two cooling loops. Supplementarv Chilled Water Svstem The purpose of the supplementary chilled water system is to provide chilled water to related air handling units located in the reactor auxiliary building. The supplementary chilled water system consists of a chilled water recirculation loop with two packaged chiller units operating in series in a "lead/lag" configuration. The system components are located in the yard behind the chiller building with the chilled water supply and return piping routed underground to the reactor auxiliary building. The supplementary chilled water system includes components in system codes SCH, SCC and RFR. The SCC cooling towers were abandoned in place when the packaged chiller units were installed. The chilled water recirculation loop consists of two half-capacity chiller units, two full..:capacity pumps, eight air handling unit cooling coils, expansion tank, chemical addition pot, piping, valves, instrumentation and controls. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-52 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information The essential chilled water system has the following intended function for 10 CFR 54.4(a)(1).

Prov_ide chilled water for those air handling systems which cool spaces containing equipment required for safety::related operations ... The essential and supplementary chilled water systems have the following intended function for 10 CFR 54.4(a)(2):.*
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The essential chilled water system has the following intended function for. 1 O:CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commissior}'s regulations for fire protection (10 CFR 50.48). FSAR References Section 9.2.9 (essential chilled water system) No.ne for supplementary chilled water system. Components Subject to Aging Management Review Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory-accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2). Remaining chilled water systems components are reviewed as listed below. / ' Table lists the component types that require aging management review. table 3.3.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings.
LRA-G 160 sh 6 LRA-G853 sh 3 LRA-G853 sh 4 LRA-G853 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-53 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-2 Chilled Water System Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Therm owe II Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-54 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.3 Component Cooling and Auxiliary Component Cooling Water System Description This review covers the component cooling water system and the auxiliary component cooling water system. This review also includes supporting functions of the circulating water system and the control element drive mechanism 'cooling system. Component Cooling Water The purpose of the component cooling water (CC) system is to remove heat from the reactor coolant and the auxiliary systems during normal operation, shutdown, or emergency shutdown following a loss of coolant accident (LOCA) or a main steam line break inside containment. CC system cooling water is pumped through the dry cooling towers and the tube side of the component cooling heat exchangers, through the components being cooled, and back to the pumps. There are two redundant, independent, full-capacity CC system trains. Each CC system frain is provided with an auxiliary component cooling (ACC) system loop. The CC system includes two component cooling water heat exchangers, three full-capacity pumps, two dry cooling towers, one surge tank (baffled), one chemical addition tank, piping, valves, instrumentation and controls. The demineralized cooling water is pumped by the component cooling water pumps through two heat sinks: the dry cooling towers, where heat is dissipated to the atmosphere, and the component cooling water heat exchangers, where heat is removed by the ACC system. Component cooling water is distributed by four loops, two related and two*nonsafety-related. The coolant is then returned to the pumps. The component cooling water surge tank, connected to the suction side of the pumps, accommodates fluid expansion and contraction. The CC system has the following intended functions for 10 CFR 54.4(a)(1 ).
Dissipate the heat removed from the reactor and its auxiliaries during normal unit operation, d\,Jring refueling, or after a design basis accident.
Support containment pressure boundary. The CC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-55 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The CC system has the following intended function for 1 O CFR 54.4(a)(3).

Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Auxiliary Component Cooling Water The purpose of the ACC system is to remove heat from the CC system, if required, during normal operation, shutdown, or emergency shutdown following*a LOCA or a main steam line break inside containment. The CC and ACC systems work together to supply sufficient cooling to safety-and nonsafety-related reactor auxiliaries under all modes of operation. This cooling is also maintained to mitigate the consequences of a design basis accident.
ACC system cooling water is pumped through the shell side of the component cooling heat exchangers, where it removes heat from the component cooling water system and rejects it to the atmosphere via the wet cooling towers. There are two redundant, independent, full-capacity ACC trains, one for each train of the component cooling water system. Each train of the ACC system includes a component cooling water heat exchanger (shell side), a full-capacity pump, and a. wet type, mechanical draft cooling tower and cooling tower basin. The ACC system takes water from the wet cooling tower basin, pumps it through the component cooling water heat exchanger where its temperature is raised, and then to the wet cooling tower for heat dissipation to the atmosphere. The ACC system is required to operate whenever the heat rejection capacity of the CC system is exceeded by accident conditions, or whenever the outside ambient conditions prevent the CC system from rejecting its required heat load by way of the dry cooling towers. If not required, the ACC system is placed in standby with the ACC pumps secured.
The ultimate heat sink consists of the CC system dry cooling towers and the ACC system wet
cooling towers with water stored in the wet cooling tower basins. Each of two 100 percent capacity loops employs a dry and wet cooling tower. Each wet cooling tower consists of two cells with each cell serviced by four induced-draft fans. Replenishment of the wet cooling tower basins from on..:site water sources and/or the Mississippi River may be required in response to a tornado event if the tornado ejects water from the cooling tower basins. If available, additional makeup for thewet cooling tower basins can be supplied from onsite storage tanks (condensate storage tank, fire water storage tanks, demineralized water storage tank, and primary water storage tank). Provisions are in place (hose connections) to draw water from these sources via a nonsafety-related, portable, diesel-driven pump, which will.supply via hose directly to the basin. Additional makeup can also be provided directly to the wet cooling tower basins using the portable pump and a .fire hose from the potable water supply through a fire hydrant. However, because these sources of water may not be available after a tornado, this function is not an intended function for the systems that include these 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-56 Waterford Steam Electric Station, Unit 3 * / , License Renewal Application
Technical Information sources. In the event these sources are not available, provisions are in place to use the portable, diesel-driven pump to supply water from the Mississippi River to the circulating water system, which has piping that can be used to gravity feed makeup to the basin. The function of providing makeup water to the wet cooling tower basin is an intended function of the circulating water system. The system includes lines from the ACC pump discharge to the suction lines of the emergency feedwater system, These lines provide a source of water to the EFW pumps if the condensate storage pool is depleted during an accident. The system also includes jockey pumps, which operate when the ACC pump is idle to keep the piping upstream of the component cooling water heat exchanger outlet temperature control valve full of water and pressurized during normal operations. Each basin is provided with an independent, nonsafety-related filtration and chemical addition system to maintain water purity and pH. This .system consists of a pump, filter, and chemical feed tank. The ACC system has the following intended functions for_ 10 CFR 54.4(a)(1).
In conjunction with the component cooling system, the ACC system dissipates the heat removed from the reactor and its auxiliaries during normal unit operation, during refueling, or after a design basis accident. '
Provide a source of water to the suction of the EFW pumps if the condensate storage pool is The ACC system has no intended function for 10 CFR 54.4(a)(2). The ACC system has the following intended function for *10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire (1 O CFR 50.48). Circulating Water The purpose of the circulating water (CW) system is to provide cooling water to the main. condenser to condense steam from the main turbine, the feedwater turbines, and other condensate drain sources. The CW system also provides cooling to the reactor coolant system by cool_ing steam dumped to the condenser through the bypass valves during plant startup and shutdown. The CW system also provides cooling to the turbine closed cooling water system heat exchangers and the.steam generator blowdown heat exchangers. The blowdown system, boron management system, liquic:I waste management system, auxiliary component cooling water system, component cooling water makeup pumps, and dry cooling tower sumps discharge through the CW system. 2.0 Scoping and Screening Methodology for Identifying Structures and Componer:its Subject to Aging Management Review and Implementation Results Page 2.3-57 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information The CW system code includes the four circulating water p*umps, the river water supply' pump, * *circulating air evacuation pumps, vacuum breakers, piping, valves, expansion joints, instrumentation and controls. Each circulating water pump takes suction from two bays at the intake structure and discharges the water into a common distribution block from which two pipes direct thewater to the condenser. Warm water from the condenser and water from auxiliary systems returns to a common distribution block and then to the discharge structure. The CW system is credited to provide emergency makeup to wet cooling towers A B following a tornado. A portable diesel-driven pump provides water from the Mississippi River to the CW system, which can then gravity feed makeup to the basin through underground piping. The CW system* has no intended functions for 10 CFR 54.4(a)(1 ). The CW system has the following intended functions for 1 O CFR 54.4(a)(2).
Provide. a source of makeup to the wet cooling tower basins following a tornado. . ., .
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The CW systern has no intended functions for 1 O CFR 54.4(a)(3). Control Element Drive Mechanism. Cooling The purpose of the control element drive mechanism cooling (CDC) system is to coo.I the magnetic jack coils of the CEDM during normal operation. The system has no safety function. The CDC system consists of four exhaust fans, four inlet dampers, water cooling coils, and associated ductwork. Two of the four fans operate to maintain a negative pressure inside the cooling shroud for the magnetic jack coil elements. The other two fans serve as standby units. Containment air is drawn _through the cooling shroud, removing heat from the CEDl\'1 magnetic jack coil. The air is drawn through the water cooling coils where the heat is rejected to the*
component cooling water system. Cooled air is then discharged to the. containment atmosphere via the system exhaust fans. The nonsafety-related cooling coils provide a pressure boundary function for the component cooling water system. The CDC system has no intended functions for 10 CFR 54.4(a)(1). The CDC system has the following intended function for 10 CFR 54.4(a)(2).
Support the component cooling water system pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Page 2.3-58 Subject to Aging Management Review and Implementation Results* .

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The CDC system has no intended functions for 10 CFR 54.4(a)(3). FSAR References Section 9.2.2 Sectiori 9.2.5 Section 9.4.5.7 Section 10.4.5 Components Subject to Aging Management Review CC system components that maintain the pressure boundary of the system from instrument air accumulators to the valve operators are reviewed in Section 2.3.3.4, Compressed Air. An isolation valve for the dry cooling tower (OCT) sumps discharge to the CW system is reviewed in Section 2.3.3.14, Plant Drains. Nonsafety-related components of the CC and CW systems not .included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining CC/ACC/CW/CDC system components are reviewed as listed below.

Table 2.3.3-3 lists the component types that require aging management review. Table 3.3.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 158 sh 1 (ACC) LRA*G158 sh.2 (ACC) 160 sh 1 (CC) LRA-G160 sh 2 (CC/ACC) LRA-G160 sh 3 (CC) LRA-G160 sh 4 (CC) LRA-G160 sh 5 (CC/ACC) LRA-G160 sh 6 (CC/ACC) LRA-G164 sh 5 (ACC) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-59 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-3 Component Cooling and Auxiliary Component Cooling Water Systems Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Coil Pressure boundary
Expansion joint Pressure boundary Fan housing boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary. Heat exchanger (fins) Heat transfer Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary
Heat exchanger (tubes) . Heat transfer Pressure boundary Nozzle Pressure boundary Orifice Flow control * -Pressure boundary Piping Pressure boundar)i Pump casing Pressure boundary Sight glass Press-ure boundary Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components SubjeQt to Aging Management Review and Implementation Results , Page 2.3-60 2.3.3.4 Compressed Air System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Tec:hnical Information The purpose of the compressed air system is to provide a reliable supply of dry, oil-free air for pneumatic instruments and controls, pneumatically operated valves and the necessary service air for normal plant operation arid maintenance. The compressed air system is comprised of components from system codes IA (instrument air system) and SA (service air system). This review also includes the emergency breathing air system and compressed air components supporting the containment building. The compressed air system consists of two instrument air compressors, one instrument air receiver, two instrument air dryers with pre-and after-filters, three station air compressors, one station air receiver, piping, valves and instrumentation. Each instrument air and station air compressor package consists of an inlet filter, compressor, moisture. separator, heat exchanger and discharge filter. Air from either the instrument air compressor or station air compressor packages is discharged into the corresponding air receiver by a common header. Air from the instrument air receiver is passed through one of the instrument air dryers and filters assemblies. The compressed air system then divides into various branches. Instrument air lines supply air to the demineralizer plant, yard area, turbine building, reactor auxiliary building, reactor building, fuel handling building, service building, and intake structure. In the turbine, reactor auxiliary and reactor buildings, these branches are divided into several sub-branches. located at various elevations. The various air valves, pneumatic instruments and controls are supplied from lines. Downstream of the station air receiver, the system is divided into various branches. Service air lines supply air to the demineralizer plant, yard area, turbine building, reactor auxiliary building; reactor building, service building, hot machine shop and decontamination room, fuel handling building and intake structure. These branches are divided into several sub-branches in all of these buildings and are located at various elevations. Service air is used for the operation of pneumatic tools, equipment used for plant maintenance, and. for occasional air lancing of the wet cooling tower basin water to control microbiological growth. *
Most components of the system serve no safety function since they are not required to achieve safe shutdown or to mitigate the consequences of an accident. Air or nitrogen accumulators are provided as backup to the normal instrument air for valves required for operation during the safe shutdown of the plant following an accident or to mitigate the consequences of an accident. Nitrogen accumulators are reviewed with the nitrogen system (Section 2.3.3.11 ). The air accumulators and associated ,components supporting safety-related air operated valves are safety-related. This includes the essential instrument air system of backup accumulators provided for post-accident operation of certain containment isolation valves during a loss of instrument air. Where nitrogen accumulators provide backup for safety-related valve operation, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-61 \ I Waterford steam Electric station, Unit 3 License Renewal Application Technical Information the compressed air system components at the interface with the nitrogen system support the nitrogen pressure boundary and are also safety-related. Where compressed air system lines enter containment, components of the system support the containment pressure boundary and are safety-related. The safety-related nitrogen accumulators are capable of providing motive air to pneumatically operated valves for 10 hours. Procedures are established for operating manual handwheel overrides or, for two accumulators, lining up backup air supplies for continued function after 10 hours. This backup air supply consists of air bottle stations that may be manually aligned to re-pressurize two accumulators following a design basis event concurrent with a loss of instrument air. These two accumulators enable control room operators to realign essential chiller cooling water valves from the wet cooling to the dry cooling towers to preserve wet cooling tower basin water inventory. * ' -The compressed air system has the following intended functions for 10 CFR 54.4(a)(1).
Provide a reserve supply of compressed air (via accumulators, backup air bottles, and related comporients) to support safety functions of air operated valves for safe shutdown . *and accident mitigation. *
Support containment pressure boundary. The_compressed air system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The compressed air system has the following intended functions for 10 CFR 54.4(a)(3). *
Perform a function (nitrogen pressure boundary) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (nitrogen-pressure boundary) that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). Emergencv Breathing Air The purpose of the emergency breathing air (EBA) system is to provide high quality breathing air for people in the control room envelope to ensure control room habitability during a fire and certain toxic gas events. The system includes an air compressor, purifier filters, four pressure air storage tanks, pressure regulators, and piping and valves for distribution to seven 2.0 Scoping and Screening Methodology for Identifying Stn,ictures and Components Subject to Aging Management Review and Implementation Results Page 2.3-62 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information manifolds around the control room envelope. Each manifold has filters, a pressure regulator, *an isolation valve, and quick discor:inect connections for up to four breathing hoses. The EBA system has no intended functions for 10 CFR 54.4(a)(1 ). The. EBA system has the following intended function for 1 O CFR 54.4(a)(2).
Provide stored, compressed air to the control room during a toxic gas release.
The EBA system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance.with the Commission.'s regulations for fire protection (10 CFR 50.48). Containment Building The primary containment and shield building are evaluated as structures, .but CB (for: . containment building) is used as a system code and includes several mechanical The purpose of the CB system mechanical components is to support the containment pressure boundary. The mechanical components include accumulators, filters, piping, and valves that support the operation and testing of seals for the maintenance hatch, the containment personnel lock, and containment escape lock. The CB system has the following intended function for 10 CFR 54.4(a)(1).
Support containment pressure boundary. The CB system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety.,.related components could prevent satisfactory accomplishment of,a safety
function. The CB system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References Section 6.3.3.5 (essential instrument air) Section (EBA) Section 6.5.3.1 Section 9.3.1 Section 9.3.9.2.1 (backup air supply) Section 9.5.1.3.1 [0.4(h)] (EBA) 2.0 Sc;oping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-63 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Instrument air system components that support the nitrogen system pressure boundary are reviewed in Section 2.3.3.11, Nitrogen. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining compressed air systems components are reviewed as listed below.
Table 2.3.3-4 lists the component types that require aging management review. Table 3.3.2-4 provides the results of the aging management review. License Renewal Drawings Adqitional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 152 sh 4 (IA) LRA-G 152 sh 6 (IA) LRA-G 1 !52 sh 9 (IA) LRA-5817-7912 (EBA) LRA-G 157 (SA) LRA-G 164 sh 2 (EBA) LRA-G 166 sh 2 (IA) LRA-B430 _M 116 (EBA) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-64 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-4 Compressed Air Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Filter housing Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Regulator body Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-65 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.5 Containment Cooling HVAC System Description The purpose of the containment cooling HVAC system (CCS) is to remove heat from the containment atmosphere, thus maintaining the containment pressure and temperature at acceptably low levels. During normal plant operations, the CCS operates continuously to maintain the pressure, temperature, and humidity. Following an accident, the CCS, in conjunction with the containment spray (CS) system, removes heat to maintain the containment pressure and temperature within design limits and limits offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CCS consists of four fan coolers that draw air from the containment and discharge it to a ring header around the top of containment. The fan cooler units consist of a vane axial fan and two banks of cooling coils supplied by the component cooling water system. The four fan cooler units are divided into two systems of two units each. During normal operation, the CCS draws containment air through the water cooling coils with the axial flow fan and discharges through a back draft damper to a duct riser. Each duct riser is common to *a pair of fan coolers and terminates with the cooled air being discharged into the ring header. From the ring header separate ducts feed cooled air to different parts of the containment. The CCS has the following intended function for 10 CFR 54.4(a)(1).
Remove heat to maintain the containment pressure and temperature within design limits and limit offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CCS has no intended function for 10 CFR 54.4(a)(2). The CCS has the following intended function for 1 O CFR 54.4(a)(3}.
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.2.2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-66 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review CCS components are reviewed as listed below. Table 2.3.3-5 lists the component types that require aging management review. Table 3.3.2-5 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the. following license renewal drawings. LRA-G853 sh 1 LRA-G 160 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-67 --___ ./

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-5 Containment Cooling HVAC System Components Subject to Aging Management Review Component Type Intended Function . Bolting. Pressure boundary Cooler housing Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Fan housing Pressure boundary Flex connection Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Piping Pressure boundary -* Thermowell* Pressure boundary Tubing Pressure boundary . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management *Review arid lmplem_entation Results Page 2.3-68 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.6 Control Room HVAC System Description The purpose of the control room heating, ventilation, and air conditioning (HVC) system is to maintain the control room envelope in a habitable condition. The HVC system is designed to establish and maintain a habitable atmosphere in the event of a toxic chemical accident or a design basis accident with its resulting radioactive environment. The control room envelope includes the control room, computer room, computer room supplementary air conditioning equipment room, HVC equipment room, emergency living quarters, emergency storage room, toilets, locker rooms, kitchen, kitchenette; supervisor's office, corridors, conference room, and vault. Control room habitability systems are required to assure that the operators can remain in the control room to operate the plant safely under normal conditions and maintain the unit in a safe condition under accident conditions. The system consists of two full-capacity redundant air handling units (AH Us), two full-capacity toilet exhaust fans, a kitchen and conference room exhaust fan, two full-capacity redundant control room emergency filtration units, redundant isolation valves for the two emergency intakes, the normal intake, and the two separate exhausts. Other HVC equipment includes individual area dampers, heaters, and redundant equipment room AHUs. The redundant air conditioning units are served by redundant loops of the essential services chilled water system. The system maintains a slight positive pressure relative to the outside atmosphere within the envelope during normal operations to prevent any outside air from bypassing the safety-related monitoring instrumentation located in the air intake path. A variety of purging operations may be conducted through various dampers and exhaust flow paths. These purging operations may be performed to remove smoke. The north and south emergency air intakes provide two sources of control room fresh air during radiological accident conditions. The HVC system has three distinct and different operating modes and associated flow paths. The operating modes are the normal operating mode, safety injection actuation signal or high radiation mode, and toxic gas (e.g., chlorine or ammonia) mode. Three smoke purge flow paths can be enabled to remove smoke from the control room and computer room. These flow paths are normally automatically aligned but may be manually aligned. The HVC system has the following intended functions for 10 CFR 54.4(a)(1).

Remove heat from the control room following an accident.
Provide filtered outside air following an accident to maintain a positive pressure in the control room. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-69 ,,,..-

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information

Maintain the control room air quality within *limits following an accident. The HVC system has no intended functions for 1 O CFR 54A(a)(2). The HVC system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). FSAR References Section 6.4
Section 9.4.1 Components Subject to Aging Management Review HVC ,system components reviewed as li_sted below. Table 2.3.3-6 lists the component types that require aging management review. Table 3.3.2-6 provides the results of the aging management review: License Renewal Drawings Addi.tional details for subject to aging 'Tlanagement review are provided in the following license renewal drawings .. LRA-G853 sh 20 LRA-G853 sh 22 LRA-G853 sh 23 LRA-G853 sh 11 LRA-G853 sh 21 LRA-G853 sh 4 LRA-G853 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-70 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-6 Control Room HVAC System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary -Fan housing Pressure boundary Filter housing Pressure boundary Flex connection Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Piping Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Reyiew and lmplemel)tation Results . Page 2.3-71 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
2.3.3. 7 Emergency Diesel Generator System* Description The purpose of the emergency diesel generator (EOG) system is to provide an emergency source of AC power to safety buses during a loss of the preferred (offsite) and standby (onsite) AC power supplies to permit the engineered safety features systems to perform their safety functions. The system includes two independent diesel generators, each with independent support systems. The diesel engines, generators, instrumentation and controls are included in system code EG (emergency generator system). The diesel support systems include components in system codes EGA (emergency diesel generator air system), EGC (emergency diesel cooling system), EGF (emergency diesel fuel system) and EGL diesel lube oil system). The EOG air system includes starting air, control and shutdown air, and the combustion air intake and exhaust. Each diesel has two identical, redundant, skid-mounted air start systems, each consisting of an air compressor, an air receiver with two air accumulation pipes (which provide air storage capacity), an air dryer, filters, and associated valves, piping, and instrumentation. The
engine is started by injecting compressed air directly into the engine cylinders in sequence. The air start system also provides air to the pneumatically operated diesel control components and the shutdown air header. A turbocharger draws outside air for diesel combustion through a filter, silencer, and shutdown valve and supplies it at positive pressure to the diesel intake manifolds via intercooler/heaters. The driving force for the turbocharger is the exhaust gases from the diesel exhaust manifold. Diesel exhaust is directed through the turbocharger turbine and an exhaust silencer to the atmosphere.
A portable Isuzu diesel-driven air compressor is available for use during a station blackout or other times when the air receivers are depleted and cannot be repressurized by normal methods. The removable flexible hose is connected to either air. receiver drain valve. The EOG cooling system consists of an engine-driven main jacket water pump, motor-driven circulating jacket water pump, water cooler cooled by component cooling water, standby jacket water heater, standpipe (surge tank), and associated piping, valves, and instrumentation. Jacket water loads include the two inlet headers for cylinder cooling, the diesel speed governor oil cooler, the turbocharger casing, and the combustion air heaters. The EOG fuel system consists of a crankshaft-driven primary fuel oil booster pump, direct-current (DC) motor-driven standby fuel oil booster pump, fuel oil cooler, fuel oil feed tank, filters, strainers, fuel oil storage tank, fuel oil transfer pump, fuel injection pumps, and associated piping, valves, and instrumentation. 2.0 Seeping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-72 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The EOG lube oil system consists of an engine-driven main lube oil pump, motor-driven standby lube oil pump, motor-driven pre-lube pump, oil coolers cooled by the component cooling water system, strainers, filters, standby lube oil heater, crankcase oil sump, maintenance lube oil storage tank, and associated piping, valves, and The EOG system has the following intended function for 10 CFR 54.4(a)(1).
Provide an emergency source of AC power to safety buses during a loss of the preferred (offsite) and standby (onsite) AC power supplies to permit the engineered safety features systems to perform their safety functions. The EOG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components. could prevent satisfactory accomplishment of a safety function. The EOG system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a fun.ction (portable air compressor) that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 8.3.1.1.1 Section 9.5.4 Section 9.5.5 Section 9.5.6 Section 9.5. 7 Section 9.5.8 Components Subject to Aging Management Review Nonsafety-related components* of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3: 15,
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining EOG system components are reviewed as listed below. Table 2.3.3-7 lists the component types th.at require aging management review .. Table 3.3.2-7 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-73 License Renewal Drawings Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 164 sh 1 LRA-1564-2044 LRA-G 164 sh 2 LRA-5817-9519 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-7 Emergency Diesel Generator System Components Subject to Aging Management Review Component Type Intended Function Blower Pressure boundary Bolting Pressure boundary Expansion joint Pressure boundary Filter housing Pressure boundary Flame arrestor Pressure boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Level indicator Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Silencer Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-75 Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical_ Information Table 2.3.3-7 (Continued) Emergency Diesel Generator-System Components Subject to Aging Management Review Component Type Intended Function Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-76 2.3.3.8 Fire Protection: Water System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical *Information The review of the fire protection: water system includes components from the fire protection system, the diesel fuel oil system, anp the treated water system. Fire Protection The purpose of the fire protection system is to ensure the capability to safely shutdown the
reactor, maintain it in a safe shutdown condition, continue to control radioactive releases to the environment, and to prevent personnel injury and property damage in the event of a fire. The fire protection system includes components in system codes FP (fire protection system) and OFP (outside fire protection). Fire protection within the protected area is provided by components in the FP system code. The FP system stores water for the control and suppression of anticipated fires and distributes the water through a network of underground mains and distribution piping to the sprinklers and hose stations. The FP system consists of two storage tanks, three fire pumps; ajockey pump, and the associated piping and valves to supply water to sprinklers, standpipes and hydrants. The diesel fuel oil tanks and other diesel support equipment are included in the DFO (diesel fuel oil) system code.
The three fire pumps, one motor driven and two diesel driven, can take suction from either or both of the storage tanks. The jockey pump maintains fire main pressure. The firewater-pumps discharge into the distribution system. The water distribution system consists of underground yard piping serving all plant yard fire hydrants, sprinkler systems, water spray systems, and interipr standpipe systems. The underground piping forms a complete fire loop around the plant. The main fire loop supplies two other fire loops: the reactor auxiliary building *. which in turn supplies the containment building, and the turbine building. If available following a tornado, inventory from the fire water storage tanks may be used to replenish the wet cooling tower basin; however, because these tanks are not protected from tornado missiles, this is not an intended function for the tanks. The credited source is the Mississippi River through the circulating water system. The fire protection system also includes a separate fire suppression system, with a storage tank, pumps, piping, valves, sprinklers, hydrants, and hose houses. This separate system, which includes components of system codes OFP and FP, provides fire protection for selected buildings outside the protected area. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-77 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The fire protection system includes fire dampers that are either installed in ductwork or mounted in walls. Fire dampers mounted in walls are included in the evaluation of structural commodities. Where necessary to support a license renewal intended function, fire dampers installed in ductWork are included in the evaluation of the related HVAC *system. Waterford 3 does not use a Halon fire suppression system or a carbon dioxide suppression ,system. The fire protection system h*as the following intended function for 1 O CFR 54.4(a)(1 ).
Support containment pressure boundary. The fire protection system has no intended functions for 10 CFR 54.4(a)(2). The fire protection system has the following intended function for _10 CFR 54.4(a)(3). * . Perform a function that demonstrates compliance with the Commissiqn's regulations for fire.protection (10 CFR 50.48). Diesel Fuel Oil The purpose of the diesel fuel oil (DFO) system is to provide a supply of fuel oil for the operation of the two diesel-driven fire pumps and the auxiliary diesel generator (also referred to as the security diesel generator). The system includes tanks, piping, valves, instruments, and controls to support operation of the diesels. The auxiliary diesel generator supports lighting requirements for'a station blackout.
The DFO system does not support operation of the emergency diesel generators or the auxiliary boiler, which have separate fuel oil systems (EGF and ABF respectively). The DFO system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The DFO system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Treated Water The purpose of the treated water system is to provide a water source for the fire water storage tank, demineralized water system, and sealing and cooling water for various pumps. The treated water system includes components from the system codes TW (treated water system) and BO (BOZE system, the primary water treatment package). The treated water system is no longer used for processing raw water from the Mississippi River. The treated water system has been inactivated except for the clearwell tank, clearwell transfer pumps, bearing lubrication water pumps for the circulating water pumps, and associated piping, valves, instrumentation, and controls. Certain components (piping and valve bodies) in the treated water system support the pressure boundary of the fire protection system. Some of these components are also in the flow path for the potable water supply to the wet cooling tower basin. However, because the availability of the potable water supply to the site is not assured following a tornado, this is not an intended function for the TW system. The credited source is the Mississippi River through the circulating water system using the portable pump. No components of the treated water system are located where physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The treated water system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The treated water system has the following intended function for 10 CFR 54.4(a)(3).
Support the fire protection system pressure boundary. FSAR References Section 9.5.1 Section 9.2.3 (treated water, referred to primary water treatment plant) Components Subject to Aging Management Review FP system dampers installed in ductwork that are necessary to support a license renewal intended function are.reviewed in Section 2.3.3.12, Miscellaneous HVAC, and Section 2.3.3.6, Control Room HVAC. Components in the DFO system that support operation of the auxiliary diesel generator are reviewed in Section 2.3.3.13, Auxiliary Diesel Generator. Remaining components are reviewed as listed below. *
Table 2.3.3-8 lists the component types that req1,1ire aging management review. Table 3.3.2-8 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-79 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G161 sh 1 LRA-G161 sh 5 LRA-G 164 sh 3 LRA-G161 sh 3 LRA-G161 sh 6 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-80 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-8 Fire Protection: Water System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Expansion joint . Pressure boundary Flame arrestor Pressure boundary Flex hose Pressure boundary Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Hydrant Pres_sure boundary Piping Pressure boundary Pump casing Pressure boundary Silencer Pressure boundary Sprinkler Flow control Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tank Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary Vortex breaker Flow control 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-81 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information 2.3.3.9 Reactor Coolant Pump Oil Collection System Description . The purpose of the reactor coolant pump (RCP) oil collection system is to ensure that failure of the oil collection system does not lead to fire during normal operations or design basis accident conditions. The oil collection system consists of enclosures which encompass all externally located oil bearing components such that potential oil leakage from components will be contained and drained to an oil collection tank in a safe location. RCP oil collection components use the RC system code.
An RCP oil collection system is provided for each pump to direct lube oil to a collection tank from pressurized and unpressurized leakage sites, such as lift pump and piping, overflow lines, lube qil cooler, oil fill and drain lines and plugs, flanged connection in oil lines, and lube oil reservoirs. A gravity drain piping system transports any accumulated oil from ttie drip pan enclosures to oil collection tanks. There are two 200-gallon oil collection tanks. The tanks are located inside the reactor containment building outside the biological shield wall. Each tank is vented and provided with a flame arrester and a glass liquid level gauge to provide local indication of the existence of oil in the tank. Each tank is. capable of collecting oil from one RCP oil lube system(195 gallons). The RCP oil collection system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The RCP .oil collection system has the following intended function 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 9.5.1.1.3 Section 9.5.1.2.6 Components Subject to Aging Management Review RCP oil collection system components are reviewed as listed below. Table 2.3.3-9 lists the component types that require aging management review. Table 3.3.2-9 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-82 License Renewal Drawings Waterford Steam Electric Station, Unit 3 -License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G 164 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-83 Waterford Steam Electric Station, Uriit 3 License Renewal Application Technical Information 2.3.3-9 RCP Oil Collection System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Drip pan Pressure boundary Enclosure Pressure boundary Flame arrestor Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer Filtration Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-84 2.3.3.10 Fuel Pool Cooling and Purification System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the fuel pool cooling and purification (FS) system is to provide cooling and purification equipment to maintain spent fuel pool temperature, purity, and clarity within design requirements. The FS system consists of a cooling loop and a purification loop. These loops are independent and provide flow paths for transfer, purification, and draining of the refueling cavity, refueling canal, spent fuel cask decontamination area, spent fuel pool, and the refueling water storage pool. The cooling portion is a closed loop system comprised of two half-capacity pumps and one capacity heat exchanger cooled by the component cooling water system. A backup spent fuel pool heat exchanger is also available when the spent fuel pool heat exchanger is out of service. The fuel pool water is drawn from the fuel pool near the surface through a strainer and is circulated by the fuel pool pumps through the fuel pool heat exchanger. From the outlet of the fuel pool heat exchanger (or backup fuel pool heat exchanger), the cooled fuel pool water is returned to the fuel pool. The purification loop consists of the fuel pool purification pump, filter, ion exchanger, and strainers. Clarity and purity of the spent fuel pool, refueling cavity, and refueling water storage pool are maintained by these components. The purification flow is drawn from the spent fuel pool through a strainer and circulated by the pump through a filter which removes particulates, then through an ion exchanger to remove ionic material, and finally through a strainer that prevents resin beads from entering the fuel pool. The refueling cavity and refueling water storage pool also have connections to the purification loop. The connection to the refueling water storage pool through the purification loop also may be used to provide makeup to the fuel pool. This provides a backup makeup supply to the spent fuel pool
that has a seismic Category I makeup water source, the refueling water storage pool. The FS system includes two nonsafety-related valves associated with the spent fuel cask decontamination pit that are credited as flood boundaries for the design basis flood. The FS system includes four nonsafety-related valves that provide drainage of containment spray fluid from the refueling cavity post-LOCA. The spent fuel storage racks are free standing and go wall-to-wall in the spent fuel pool and spent fuel cask storage area. The spent fuel storage racks are grouped into two design styles, designated as Region 1 and Region 2. Both rack styles contain Baral as the active neutron absorbing poison. The neutron absorbers and storage racks are subject to aging management review and are included in this review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-85 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The FS system has the following intended functions for 10 CFR 54.4(a)(1).
Remove decay heat from spent fuel assemblies.
Support containment pressure boundary.
Provide neutron absorption in the spent fuel.pool. .
Provide structural support of fuel assemblies in the spent fuel pool. The FS system has the following intended functions for 10 CFR 54.4(a)(2).
Provide a backup makeup water supply to the spent fuel pool from a seismic Category I source.
Provide for containment spray fluid drainage from the refueling cavity post-LOCA.
Provide flood barrier for design basis flood.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The FS system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References Sections 9.1.2, 9.1.3 (referred to as fuel pool system or spent fuel pool cooling and cleanup system) Components Subject to Aging Management_ Review* The refueling cavity drainage portion of the FS system is reviewed in Section 2.3.3.14, Plant Drains. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed *in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining system components are reviewed as listed below. Table 2.3.3-10 lists the component types that require aging management review. Table 3.3.2-10 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-86 License Renewal Drawings Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 1 LRA-G163 LRA-G 160 sh 4 LRA-G169 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-87 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-1 O Fuel Pool Cooling and Purification System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Heatexchanger(channel head) Pressure boundary Heat exchanger (shell) Pressure boundarY Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Neutron absorber Neutron absorption " Piping Pressure boundary Pump* casing Pressure boundary Rack Support for Criterion (a)(1) equipment Thermowell Pressure boundary Tubing Pressure boundary Valve body . Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-88 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.11 Nitrogen System Description The purpose of the nitrogen (NG) system is to provide nitrogen gas for normal plant operation and maintenance and for charging nitrogen accumulators associated with safety-related components.
The nitrogen system has a completely automated storage and supply network with resupply coming from a vendor tanker/trailer. The* system withdraws liquid. nitrogen from a* storage tank via one of two positive displacement pumps. The liquid nitrogen is converted into a gas by a vaporizer unit and is stored in three high pressure storage cylinders connected to the supply header. From the supply header, nitrogen is delivered directly to the main steam isolation valve (MSIV) nitrogen charging connections located just below the MSIV actuators and to a pressure control manifold. The pressure control manifold then reduces the nitrogen pressure for distribution to various plant loads.
Nitrogen is distributed to the reactor auxiliary building, reactor containment building, and turbine generator building. Nitrogen.pressure is reduced as needed to meet load requirements. The following major loads are supplied by the nitrogen system:
Safety injection tanks
Reactor drain tank and quench tank
Accumulators used as backup air sources for safety-related air operated valves
Gas surge tank, gas decay tanks, and equipment drain tank_
Volume control tank
Boron management flash tank and holdup tanks
Demineralized water storage tank, primary water storage tank
Condensate storage tank
Steam generators for blanketing and purging Safety-related relief valve NG-1523 is installed to protect safety-related nitrogen accumulators and a containment penetration from over-pressurization should nonsafety-related pressure reducing valves and nonsafety-related pressure relief valves fail to function properly. Two valves in the NG system support the main steam pressure boundary. This nitrogen flow path provides a nitrogen blanket to the steam generators during outages. Valve NG-432 supplies nitrogen to the holdup tanks in the boron management system and is. classified as Safety Class 3. However,-since the holdup tanks do not perform a safety function, NG-432 does not perform a safety function in accordance with 10 CFR 54.4(a)(1 ). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page ?*3-89 i .:

( Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The NG system has the following intended functions for 1 O CFR 54.4(a)(1 ). *

Provide a reserve supply of compressed nitrogen (via accumulators and related components) to support safety functions of air operated valves for safe shutdown and accident mitigation.
Support pressure boundaries of safety-related systems that use nitrogen.
Support containment pressure boundary. The NG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety
function. The NG system has the following intended functions for 1 O CFR 54.4(a)(3).
Perform a function (accumulators for air operated valves) that demonstrates compliance with 'the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (accumulators for air operated valves) that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). FSAR References Section 9.3.9 Components Subject to Aging Management Review NG system components that support SI system intended functions are reviewed in Section 2.3.2.2, Safety Injection. Two valves supporting the main steam pressure boundary are reviewed in Section 2.3.4.4, Main Steam. Safety-related valve NG-1523 does not require aging management review because the valve fails to its desired position (pressure boundary integrity is not required). Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining NG system components are reviewed as listed below. Table 2.3.3-11 lists the component types that require aging management review. Table 3.3.2-11 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-90 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings.
LRA-G 166 sh 1 LRA-G 166 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-91 Table 2.3.3-11 Nitrogen System Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Flex hose Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Regulator body Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results * ' Page 2.3-92 2.3.3.12 Miscellaneous HVAC System Description Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information This review includes the following site HVAC systems with intende.d functions for license renewal.
Cable vault and switchgear ventilation
Containment atmosphere release
Fuel handling building HVAC
Reactor auxiliary building HVAC
Shield building ventilation
Turbine building HVAC For other HVAC systems not addressed here, see Section 2.3.3.5, Containment Cooling HVAC, and Section 2.3.3.6, Control Room HVAC. Cable Vault and Switchgear Ventilation The purpose of the cable vault and switchgear ventilation system (SVS) is to maintain a suitable operating environment for electrical equipment and prevent the accumulation of a combustible concentration of hydrogen in the battery rooms during normal and accident conditions. The SVS also provides for smoke purge in the electrical areas in the event of a fire. The cooling part of the SVS is made up of two separate air handling subsystems, each with two full-capacity air handling units consisting of a medium efficiency filter, chilled water cooling coil, and centrifugal fan. Electric heating coils are included in the air handling units of_ one of the air handling subsystems. The remainder of the SVS consists of two full-capacity battery room exhaust fans for each battery room, two exhaust fans for smoke purging, one exhaust fan used during normal operation and smoke purging, and tw.o full-capacity ventilation*fans. The SVS has the following intended functions for 10 CFR 54.4(a)(1).
Maintain a suitable operating environment for electrical equipment during accident conditions.
Prevent the accumulation of a combustible concentration of hydrogen in the battery rooms during accident conditions. I, The SVS has no intended functions for 10 CFR 54.4(a)(2). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-93

\ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SVS has the following intended function for 1 O CFR 54.4(a)(3).

Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Containment Atmosphere Release The purpose of the containment atmosphere release (CAR) system is to purge containment at low containment atmosphere pressure. As described in FSAR Section 6.2.5, the CAR system is part of the combustible gas control system, which consists of three systems: the CAR system, a hydrogen analyzer system, and a hydrogen recombiner system (see description* of the hydrogen analyzer and recc:imbiners in Section 2.3.2.3, Containment Penetrations).
The CAR system serves as a long-term post-accident'clean up system. When post-LOCA containment pressure has reduced sufficiently, the CAR system transfers gases from inside containment to the reactor building annulus. CAR system operation following a design basis accident allows fission products to be released to the shield building annulus for fission-product removal by the shield building ventilation system. When containment pressures have been
reduced to* approximately atmospheric, the CAR system can be started to purge containment The CAR system consists of two full-capacity exhaust trains and two full-capacity supply trains. Each supply train draws air from the reactor auxili.ary building and discharges to the contain merit. Each exhaust train draws a controlled amount of air from the containment and discharges into the shield building ventilation system recirculation ducting leading to the shield building annulus. The system includes containment isolation valves. The CAR system has the following intended functions for 10 CFR 54.4(a)(1).
Support post-accident fission product transport to the shield building annulus for removal by the shield building ventilation system.
Support containment pressure boundary. The CAR system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The CAR system has no intended functions for 1 O CFR 54.4(a)(3). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation-Results Page 2.3-94 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Fuel Handling Building HVAC The purpose of the fuel handling building HVAC, (HVF) system is to provide a suitable environment for personnel, equipment and controls in the fuel handling building during normal operation. During normal operation, outside air is distributed to the fuel handling building by the normal supply fan and exhausted from the building by the normal exhaust fans. The ducting for the normal flow path is designed to assure that airflow is directed from areas of low potential radioactivity to areas of progressively higher potential radioactivity. Following a fuel handling isolation dampers isolate the areas of the fuel handling building where a fuel handling accident can occur.
Emergency filtration exhaust fans take suction on the spent fuel handling area of the fuel handling building with each fan pulling the air through a heater, a medium efficiency filter, high efficiency particulate air (HEPA) filters, and a charcoal adsorber. The filtered gases are then exhausted to the atmosphere. , The components of the HVF system designed to operate in response to a fuel handling aQcident are classified as safety-related (safety class 3). The fuel handling accident analysis V)las revised for the implementation of the alternate source term. The revised analysis does not credit the HVF filtration system for mitigation of the event. the ventilation isolation function is conservatively included as an intended function for the system. The HVF system has the following intended function for 1 O CFR 54.4(a)(1 ).
Isolate the normal ventilation in the fuel handling area envelope in the event of a fuel. handling accident. The HVF system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The HVF system has no intended functions for 10 CFR 54.4(a)(3). Reactor Auxiliary Building HVAC The reactor auxiliary building {RAB) HVAC (HVR) system consists of the following subsystems:
RAB normal ventilation
RAB miscellaneous HVAC
RAB controlled ventilation area
Emergency diesel ventilation
RAB H&V equipment room ventilation 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-95 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RAB Normal Ventilation System The purpose of the RAB normal ventilation system is to cool and heat parts of the reactor auxiliary building during normal operation. The RAB normal ventilation system includes a ventilation supply and ventilation exhaust system. The ventilation supply system includes filters, heating and cooling coils, two full-capacity fans, dampers, and ducting to distribute outside air throughout the reactor auxiliary building. The ventilation exhaust system includes filters, charcoal adsorbers, dampers, two full-capacity fans, and ducting to exhaust reactor auxiliary building air to the plant stack. The system includes a connection from the containment atmosphere purge system to transfer the purge exhaust to the plant stack. The RAB normal-ventilation system has individual safety-related and nonsafety-related air handling units located inside equipment rooms. The safety-related air handling units,
consisting of a fan section, cooling coil and filters, operate during accident conditions when the equipment in their respective room is operating to maintain an acceptable environment for the equipment. air handling units are located inside the following equipment rooms:
Component cooling water pump rooms A, B and AB
Component cooling water heat exchanger rooms A and B
EFW pump rooms A and B *
Charging pump rooms A, B and AB
Shutdown heat exchanger rooms A and B
Safeguard pump room A and B
HPSI pump room AB These units circulate room air through the filters and cooling coil and discharge the cooled air directly to the room where they are located. The fari coolers do not include any distribution ductwork. The essential chilled water system supplies chill water to the safety-related fan coolers. RAB Miscellaneous HVAC System The purpose of the RAB miscellaneous HVAC system is to maintain a desirable operatin*g environment for equipment and to provide comfort for pers.onnel during normal operations. The RAB miscellaneous HVAC is not required to operate during or after a design basis accident or to assist in the safe shutdown of the reactor. The system consists of dampers, filters, heating and cooling coils, fans and distribution ducting. The system provides ventilation for various administrative areas, the hot machine shop, decontamination area, central alarm station area, and other work and storage areas. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-96 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RAB Controlled Ventilation Area System The purpose of the RAB controlled ventilation area system (CVAS) is to provide high efficiency filtration and iodine adsorption for air exhausted from the controlled ventilation
areas following a design basis accident. The controlled ventilation areas contain equipment such as the shutdown heat exchangers,_ containment spray pumps, the high and.low pressure safety injection pumps, containment penetrations, and post-accident sampling equipment. The CVAS exhausts air from the controlled ventilation area following a LOCA to create and maintain a negative pressure relative to surrounding areas. The system limits the post-accident radiological releases to maintain dose consequences below the guidelines of 1 O CFR 50.67. The CVAS consists of exhaust ducts, isolation valves, inlet and suction valves, filter trains, exhaust fans, gravity and bypass dampers and connecting ductwork to the main exhaust duct wh_ich leads to t.he plant stack. The filter trains consist of a demister, electric heating coil, prefilter, upstream HEPA filter, charcoal adsorber, and downstream HEPA filter. Emergency Diesel Ventilation System The purpose of the EOG ventilatiqn system is to remove the heat associated with diesel operation from the EOG A and B rooms. During normal plant operations, the RAB normal ventilation system maintains temperature in the EOG rooms. The EOG ventilation system remains in standby during normal. operation, starting in conjupction with a diesel start. Each EOG room has its own separate ventilation system consisting of an outside air intake damper, an axial flow exhaust fan, a gravity damper, and an outside air exhaust louver. RAB H& V Equipment Room Ventilation System The purpose of the RAB heating and ventilation °{H&V) equipment room ventilation system is to maintain a suitable operating environment for the equipment located in the H&V equipment room during normal or accident conditions. The RAB H&V equipment room is supplied by two full-capacity air handling units. Each unit includes a filter, heating coil, and centrifugal fan. The fans take suction either from the outside air intake or from the RAB H&V equipment room itself, depending on room temperature. Air is exhausted directly from the RAB H&Vequipment room by two full-capacity exhaust fans discharging through a duct containing a gravity damper. The reactor auxiliary. building HVAC system has the following intended functfons for 1 O CFR 54.4(a)(1 ).
Maintain an acceptable operating environment for safety-related equipment. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-97 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Provide high efficiency filtration and iodine adsorption for all air exhausted from the controlled ventilation areas following a design basis accident. The reactor auxiliary building HVAC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The reactor auxiliary building HVAC system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (EOG ventilation, RAB H&V ventilation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). ' Shield Building Ventilation The purpose of the shield building ventilation (SBV) system is to control the release and removal of fission products from the shield building annulus atmosphere and to maintain annulus pressure within the assumptions of the radiological analyses following a design basis accident. The SBV system is not normally in operation. During accident conditions, this system maintains a negative pressure in the shield building annulus by mixing shield building in-leakage with the air in the annulus and discharging it through a filter train that includes charcoal and HEPA filters. The system provides holdup and removal of fission products by recirculation and filtration using two full-capacity redundant fan and filter systems which exhaust the annular space and discharge back to the annulus or through the plant stack to the afmosphere as required to
maintain a negative pressure in the annulus. On the suction side of each fan, the air is drawn sequentially through a demister, electric heating coil, prefilters, HEPA filter, charcoal adsorber and HEPA afterfilter. A backdraft damper located on the discharge side of the exhaust fan precludes backflow through the system. Downstream of the backdraft dampers, two flow paths are provided to enable discharge through the plant stack or recirculation through a supply tieader in the annulus.
The SBV system has the following intended functions for 10 CFR 54.4(a)(1).
Control the release and removal of fission products from the shield building annulus atmosphere.
Maintain annulus pressure within the assumptions of the radiolog.ical analyses.
Support containment pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-98 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SBV system has no intended functions for 10 CFR 54.4(a)(2) or (a)(3). Turbine Building HVAC The purpose of the turbine building ventilation (HVT) system is to provide a suitable operating environment for equipment and personnel during *normal operation. The ventilation system, except for the switchgear room described below, is a single-pass type and consists of ventilation air intake louvers and dampers, supply fans, exhaust fans, and exhaust louvers and dampers distributed about the periphery of the building. The turbine building switchgear room is separately ventilateq by two half-capacity air handling units that cool the space with outside _air. Each air handling unit contains a medium efficiency filter arid centrifugal fan. Outside air is mixed with return air at the suction of the air handling units to maintain the temperature in the switchgear room. Heating units are mounted on the wall. A nonsafety-related fan is used to provide ventilation for the turbine generator building (TGB) battery room. The TGB battery chargers are necessary for control power to the off-site power switchgear during a fire event where off-site power is not lost; in this scenario, the exhaust fan is not required. However, in a fire event where off-site power is initially lost and the TGB batteries are supplying the DC loads and discharging, then the TGB battery exhaust fan will be required once off-site power is restored to support removal of hydrogen generated from the TGB batteries during recharging. The HVT system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The HVT system has the following intended function for 10 CFR 54.4(a)(3). * . Perform a function (switchgear room and battery room ventilation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). FSAR References Section 9.4.3.5 (SVS) Section 6.2.5 (CAR) Section 6.2.5.2.3 (CAR) Section 9.4.2 (HVF) Section 9.4.3 (HVR) Section 6.5.1.2.1.2 (HVR) Section 6.2.3 (SBV) Section 6.5.1 (SBV) Section 9.4.4 (HVT) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-99 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Nonsafety-related components of the systems not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining HVAC systems components are reviewed as listed below. Table 2.3.3-12 lists the component types that require aging management review. . . . Table 3.3.2-12 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. Reactor Auxiliary Building HVAC LRA-G853 sh 11 LRA-G853 sh 15 LRA-G853 sh 16 LRA-G853 sh 17 LRA-G853 sh 18 LRA-G853 sh 19 LRA-G853 sh 21 _ Various HVAC (Chilled Water) LRA-G853 sh 4 LRA-G853 sh 5 LRA-G853 sh 9 Cable Vault and Switchgear Ventilation LRA-G853 sh 8 . Containment Atmosphere Release LRA-G853 sh 1
Fuel Handling Building HVAC LRA-G853 sh 2 Shield Building Ventilation LRA-G853 sh 1 Turbine Building HVAC LRA-G853 sh 14 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-100 Waterford Steam Electric Station, Unit 3 License Renewal Application -Technical Information Table 2.3.3-12 Miscellaneous HVAC Systems Components Subject to_Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Fan housing Pressure boundary Filter housing Pressure boundary Flex connection Pressure boundary Flex hose Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Nozzle Flow control Pressure bouhdary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-101 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.13 Auxiliary Diesel Generator System Description This review includes the auxiliary diesel generator (ADG, a component in the site security [SS] system) and a function of the diesel fuel oil system. Site Security
The purpose of the SS system is to provide site access controls, surveillance equipment and communications equipment used to maintain security. at the site. The system includes a diesel generator to assure a continuous source of power for the security equipment, independent of the plant electrical systems. The security diesel generator, also known as the auxiliary diesel generator, is credited for station lighting during a station blackout event. The ADG is a nonsafety-related skid-mounted turbocharged John Deere diesel engine poweririg a generator. The diesel has its own radiator and cooling water subsystem and therefore does not require an external cooling water supply. The diesel is electrically started from battery power. The security diesel has its own fuel tank with a 24-hour supply of fuel, which is adequate for the Waterford 3 four-hour coping analysis for station blackout. The ADG is normally in standby and operated only during testing. The SS system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The SS system ha.s the following intended function for 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). Diesel Fuel Oil See Section 2.3.3.8, Fire Protection: Water for a description of the DFO system. DFO system components supporting operation of the ADG include a fuel oil tank, piping, valves, instruments, and controls. The DFO system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The DFO system has the following intended function for 1 O CFR 54.4(a)(3) related to the ADG.
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-102 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information FSAR References None Components Subject to Aging Management Review SS and DFO system components supporting the ADG are reviewed as listed below. Table 2.3.3-13 lists the component types that require aging management review. Table provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G 164 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-103 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-13 Auxiliary Diesel Generator System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Expansion joint Pressure boundary Flame arrestor Pressure boundary Piping Pressure boundary Silencer Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-104 Waterford Steam Electric Station, Unit 3 ,,----*. License Renewal Application
Technical Information 2.3.3.14 Plant Drains System Description The review of plant drains includes components from the sump pump system (system codes SP and PME) and the sanitation system (system code SAN). The review also includes components from systems described elsewhere in the application but that support an intended function for plant drains. See "Components Subject to Aging Management Review" below. *Sump Pump The purpose of the sump pump (SP) system is to provide for the drainage of equipment, tanks, and wetted surfaces during normal plant operations as well as anticipated large volume flows associated with abnormal or accident conditions. The review of the SP system also includes components with a PME (portable and miscellaneous) system code .. components of the SP system support both radioactive and non-radioactive drainage systems. The radioactive drainage systems arid non-radioactive drainage systems are isolated from each other. Each area housing safety-related equipment is provided with an independent drainage system and attendant sump to preclude the flooding of such areas from other drainage systems. Water discharged from fire suppression systems is handled by the floor drain systems, but this function is not credited for an internal flooding event and not credited for compliance with Appendix R. Dr.ainage from radiologically controlled areas is routed to the waste management systems. Except as noted below, the equipment and floor drainage systems do not serve any safety function and are classified as nonsafety-related. The sump pump system Jncludes safety-related components in the discharge flow path from the containment sump pumps that form part of the containment pressure boundary. The sump pump system includes components associated with the dry cooling tower (OCT) Each OCT sump is provided with a set of motor-driven sump pumps, normally aligned to discharge to the circulating water system, to protect safety-related equipment in the area. Each cooling tower area is also provided with a portable diesel-driven sump pump and hoses that can be connected during extreme rainfall events to discharge water directly over the NPIS exterior floodwall.
One portable DCT diesel-driven pump and one motor-driven sump pump per DCT sump are credited in the analyses for the probable maximum precipitation (PMP) event to prevent flooding of safety-related equipment in the area. In the analysis for the standard project storm (SPS) with the simultaneous occurrence of the operating basis earthquake (OBE), a single diesel-powered sump pump per OCT sump is adequate to prevent flooding of safety-related equipment. Although piping segments through the NPIS wall are classified as safety-related (non-AS ME, non-seismic), they do not perform a safety function in accordance with 1 O CFR 54.4(a)(1 ). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-105 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Roof drains inside the NPIS are credited with removing water from the roofs of structures containing safety-related components during the PMP event. These nonsafety-related drains perform an intended function that meets the criteria of 10 CFR 54.4(a)(2) of protecting related components during design basis rainfall events. These drains are evaluated as part of the SP system. No credit is taken for floor drains or sump pumps for internal flooding everits such as pipe breaks or fire system discharge; however, as discussed above, the OCT sump pumps are credited in the PMP analysis. For the ECCS equipment sumps, the .section of the sump drainage line from the pump discharge check valve back to the pump protects the compartment from backflow through the drainage system. The SP system has the following intended function fot 10 CFR 54.4(a)(1).
Support containment pressure boundary. The SP system .has the following intended functions for 10 CFR 54.4(a)(2).
Protect safety-related components during design basis rainfall and/or flooding events.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SP system has no intended functions for 1 O CFR 54A(a)(3). Sanitation The purpose of the sanitation (SAN) system is to collect all sewage originating within the protected area and to transfer it to the municipal sanitary waste system. The system consists of lift stations and associated instrumentation, piping and valves. Sanitary collection facilities are located at several locations within the nuclear plant island structure (NPIS) boundaries to accept sanitary waste. The sanitary. drain piping is vented to atmosphere via roof vents to allow gravity flow drainage through an NPIS wall penetration at elevation +12. 7 ft. MSL. This piping functions as a flood barrier for the design basis floqd.
The SAN system has no intended functions for 10 CFR 54.4(a)(1). The SAN system has the following intended function for 1 O CFR 54.4(a)(2).
Support NPIS flood barrier. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-106 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SAN system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References . Sump Pump System Section 2.4.2.3.3 (roof drains) Section 2.4.2.3.4 (cooling tower area) Section 3.6A.6.4.2.1 (compartment flooding) Section 9.3.3 Components Subject to Aging Management Review Sanitation System Section 9.2.4 Two condensate makeup and storage system valves (CMU-908, and CMU-909) in the fuel handling building are credited flood barrier valves between the Fuel Cask Decontamination Area, open to the train bay which is not flood protected, and the FHB sump. These valves, which are not depicted on an LRA drawing, are included in this review. The 6-inch refueling cavity drains in the refueling cavity (LRA Drawing LRA-G163) provide for containment spray fluid drainage from the refueling cavity post-LOCA. The drains, components in the fuel pool cooling and purification system, are included in this review. Components in sprinkler drains and in the resin waste management (RWM) system and the solid waste management (SWM) system support the NPIS flood barrier and are included in this review. The RWM and SWM systems are described in Section 2.3.3.15, Auxiliary Systems in *Scope for 1 O CFR 54.4(a)(2). Nonsafety-related components of the SP system not included in other reviews whose failure could prevent satisfactory accomplishment*of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining plant drains components are reviewed as listed below. Table 2.3.3-14 lists the component types that require aging management review. Table 3.3.2-14 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-107 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details fbr components subject to aging management review are provided in the following license renewal drawings. LRA-G 173 sh 1 LRA-G 173 sh 2 LRA-G 173 sh 3 LRA-G 170 sh 5 LRA-G 158 sh 2 LRA-G163 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-108 Waterford Steam Electric station, Unit 3 Table 2.3.3-14 Plant Drains License Renewal Application "' Technical Information Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-109 2.3.3.15 Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.1 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two
ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an ss.c. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Phvsical Failures This section summarizes the scoping and screening results for auxiliary systems based on 1 O CFR 54.4(a)(2) because_ of the potential for physical interactipns with safety-related equipment. Physical failures may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At WF3, certain components-and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.1 and 2.1.2.1.2. Physical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the' criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-110 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information criterion affected auxiliary systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Sprav Nonsafety-related system components or nonsafety-related portions of safety-related systems containing water, oil, or steam are considered within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. Auxiliary systems meeting this criterion are within the scope of license renewal per 10 CFR 54.4(a)(2). The following auxiliary systems, described in referenced sections, are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) for physical interactions. System Code System Name Section Describing System AE Air Evacuation Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) ARR Airborne Radioactivity Removal Section 2.3.3.15, Auxiliary Systems in Scope for . 10 CFR 54.4(a)(2) ANP Annulus Negative Pressure Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) AS Auxiliary Steam Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2)* BAM Boric Acid Makeup Section 2.3.3.1, Chemical and Volume Control BM Boron Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) eve Chemical and Volume Control Section 2.3.3.1, Chemical and Volume Control CF Chemical Feed Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) CHW, Chilled Water Section 2.3.3.2, Chilled Water RFR,SCH, sec cw Circulating Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water
cc Component Cooling Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-111 System Gode IA, SA CAP CAR CB DF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT LWM NG PAS PW PMU PSL System Name -Compressed Air Containment Atmosphere Purge -Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation. Leak Rate Testing Liquid Waste Management Nitrogen .. Post Accident Sampling Potable Water Primary Makeup Primary Sampling 0 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section Describing System Section 2.3.3.4, Compressed Air Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2)
Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.4, Compressed Air Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.7, Emergency Diesel Generator Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.10, Fuel Pool Cooling and Purification Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) -Section 2.3.3.15, Auxiliary Systems in Scope for -10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.11, Nitrogen Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology tor Identifying Structures and Components Page 2.3-112 Subject to Aging_ Management Review and Implementation Results -

System Code System Name ARM, PRM Radiation Monitoring HVR Reactor Auxiliary Building HVAC RCC Reactor Cavity Cooling RWM Resin Waste Management SSL, CTB Secondary Sampling SWM Solid Waste Management SP, PME Sump Pump TC Turbine Building Cooling Water System Descriptions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section Describing System Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.14, Plant Drains Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) The following systems within the scope of license renewal based.on the criterion of 10 CFR 54.4(a)(2) are not described elsewhere in the application. Each system has the following intended function.

Maintain integrity of nonsafety-related components such that no physical interaction with safety-related componer:its could prevent satisfactory accomplishment of a .safety function. The systems described below have components that support this intended function. For systems with intended functions that meet additional scoping criteria, the additional intended functions are noted in the descriptions below with a reference to the section where the affected components are evaluated (e.g., Section 2.3.2.3, Containment Penetrations). Air Evacuation The purpose of the air evacuation system (AE) is to remove air from the three condenser shells to create a vacuum in the condenser during plant startup and to maintain the 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-113 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information vacuum by removing non-condensible gases and in-leaking air from the steam space of. the three condenser shells during normal operation. The system has no safety function. The system consists of three full-capacity condenser vacuum pump assemblies. Each assembly consists of one motor driven, rotary, water-seal type, two-stage vacuum pump and seal water system. Ea.ch seal water system includes one centrifugal circulating pump, one heat exchanger, one separator and all necessary piping, valves, instruments and electric devices. , The non-condensible gases and water vapor mixture is drawn directly from each shell of the condenser. The mixture flows through the condenser vacuum pump(s) and then to -the separator, where most of the water vapor is condel}sed, and the non-condensible gases are released to the atmosphere via a discharge silencer. The exhaust is monitored for radioactivity prior to discharge to the atmosphere to provide early detection of a steam generator tube leak; in this event, the discharge can be routed to the reactor auxiliary building HVAC system exhaust. The condensed water normally is returned to the condenser; a backup overflow drain line is routed to the industrial waste sump.
Airborne Radioactivity Removal The purpose of the airborne radioactivity removal (ARR) system is_ to limit the buildup of airborne radioactivity leaKing from the reactor coolant system during normal operation, _ and* reduce airborne radioactivity of containment atmosphere to *permit personnel access inside containment during normal operation, shutdown or refueling. The system is used . for radioactivity removal during normal operation only and serves no function for accident dose reduction. The system consists of two airborne radioactivity removal uriits, each consisting of a medium efficiency filter, HEPA prefilter,* charcoal adsorber, and centrifugal fan. Annulus Negative Pressure The annulus negative pressure (ANP) system is provided to maintain the shield building annulus at a negative pressure during normal operation. This minimizes the leakage of unfiltered air to the outside atmosphere. The system draws from the annulus through a single duct which penetrates the shield building through two isolation valves in series to two full-capacity exhaust fans arranged in parallel. The fans discharge to a single duct to the stack. The fans are stopped and . " the isolation valves are closed on a safety injection actuation signal (SIAS) or a containment isolation actuation signal (CIAS). Apart from support of the secondary containment pressure boundary by the isolation valves, the system has no safety functi_on.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-114 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information In addition to the 10 CFR 54.4(a)(2) function described above, the ANP system has the following intended function for 10 CFR 54.4(a)(1).
_ Support containment pressure boundary. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Gontainment Penetrations. Auxiliary Steam The of the auxiliary steam system (AS) is to distribute low pressure steam to plant auxiliary equipment. The AS system is supplied by either the main steam system or the auxiliary boiler system. The AS system supplies steam to the boric acid concentrator, the boric acid/waste concentrator, and the decontamination facility steamerette. The system includes piping and valves located in the reactor auxiliary building. Boron Management The purpose of the boron management (BM) system is to accept, collect, and process_ radioactive waste from various plant systems for recycle or disposal. The BM system proyides a mechanism for concentrating and recovering dissolved boron from the liquid effluent for reuse in the plant or removal from the site. The BM system includes two concentrators, several tanks and. pumps, filters and ion exchangers, and the associated piping and valves_ required to collect and process radioactive waste fluids from various plant systems for recycle or disposal. -The major influent to the f?M system is from the letdown line in the CVC system and is the result of feed and bleed operations during plant shutdowns, startups, and dilution due to fuel burnup over core life. Other sources into the BM system consist of valve and equipment leak-offs, miscellaneous drains, and relief valve discharges. The reactor drain tank collects these discharges within the containment, while the equipment drain tank and equipment drain s_ump accumulate those from outside the containment. From the of the collection tanks and CVC system, water .is sent to the holdup tanks, where the radioactivity of the liquid is significantly reduced during storage. From the holdup tanks, water is processed through filters and ion exchangers and stored in the boric acid condensate tanks. From there the fluid is either released or reprocessed. The section of the system including the flash tank and flash tank pumps is inactive and isolated from the rest of the system by closed valves. Use of the tank required a continuous feed of nitrogen, which created an excessive amount of gaseous waste to be stored and processed. The three-way valve at the inlet to the flash tank is positioned to bypass the tank and has no supply air or power. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review am;! Implementation Results. -Page 2.3-115 '1 )

Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Portions of the BM system that receive *and store reactor coolant water discharge for decay are classified as safety-related (Safety Class 3). This includes the holdup tanks, reactor drain tank pump, equipment drain tank pump, and associated piping and isolation valves. However, as part of the licensing basis change to use the alternate source term (10 CFR 50.67), the FSAR analyses of the liquid waste system (BM system and waste management system) leak or failure (release to atmosphere) was deleted from FSAR Section 15.7.3.2. This event is no longer required by the Standard Review Plan (NUREG-0800). Therefore, the Safety Class 3 components of the BM system no longer perform a safety function in accordance with 10 CFR 54.4(a)(1).

BM system components that support the containment pressure boundary are related (Safety Class 2). A BM system valve also supports the pressure boundary of tlie refueling water storage pool (RWSP). Other components of the system have no safety function. In addition to the 10 CFR 54.4(a)(2) function described above, the BM system has the following intended function for .10 CFR 54.4(a)(1). : *
Support containment pressure boundary. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations .. A valve supporting the RWSP pressure boundary is reviewed in Section 2.3.2.2, Safety Injection. Chemical Feed The purpose of the chemical feed (CF) system is to feed various chemicals into the secondary system to maintain and control the pH and to control the oxygen level for the protection of the steam generator tube integrity. The CF system includes a hydrazine feed system-and an *ammonia feed system, designed to feed a hydrazine solution and an aqueous ammonia solution, respectively, into the secondary system. The system also includes two independent chemical feed skids generically designed to feed alternate chemicals as water chemistry technology evolves. The system consists of tanks, pumps, valves, piping, controls and indicators. Containment Atmosphere Purge The purpose of the containment atmosphere purge (CAP) system is to reduce the level of radioactive contamination in the containment atmosphere to permit personnel access. The CAP system consists of a containment purge air makeup unit and a separate containment purge exhaust which is connected to the exha.ust portion of the reactor auxiliary building HVAC (HVR) system. The CAP system includes no*faris; motive force. for the purge and makeup is provided by the HVR system exhaust fans. Apart from 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-116 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information containment isolat[on valves and ducting on the makeup and exhaust lines, the CAP system has no safety function. These valves also isolate the system on a high radiation signal to support the fuel handling accident analysis. The makeup portion of the system provides air to the containment while purge operations are being conducted. Makeup air enters through a louvered damper and passes through a medium efficiency filter and an electric heating coil. The makeup air flows in series through containment isolation valves to enter the containment. The exhaust portion of the system draws air from inlet dampers, arranged in parallel, serving the general containment area and the refueling pool area inside containment. Exhaust air passes through the inlet dampers and a series of containment purge isolation valves to the HVR system where it is filtered for removal of any radioactive particulates and radioiodines before being exhausted by HVR system exhaust fans to the plant stack. In addition to the 1 O CFR 54.4(a)(2) function described above, the CAP system has the following intended functions for 1 O CFR 54.4(a)(1 ).
Isolate the system on high radiation signal to support the fuel handling accident analysis.
Support containment pressure boundary. Components that isolate the system and also support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Decontamination Facility The purpose of the decontamination facility (OF) is to provide locations and facilities to decontaminate equipment. Equipment decontamination areas are provided at selected locations in the plant. The OF system code includes components of the decontamination equipment. These components include rinse tanks, pumps, filters, strainers, valves, and piping. Gaseous Waste Management The purpose of the gaseous waste management (GWM) system is to provide for collection, storage, sampling, and discharge of potentially radioactive gaseous waste. The GWM system consists of a gas surge tank, two waste gas compressors, three gas decay tanks, and the associated piping and valves required to collect gaseous waste and allow for release through the plant stack. Waste gases enter the GWM system by way of three headers: the vent gas collection header, the containment vent header, and the gas surge header. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-117 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The vent gas collection header collects gas primarily from aerated vents of process equipment in the boric. acid makeup and boron management systems, the liquid waste management system, the chemical and volume control system, and the fuel pool cooling and purification system. Because of the large volume of gas and the low activity level from the sources, the gases are routed directly to the plant stack. Waste gases which are routed to the gas surge header and containment vent header are mainly hydrogenated, radioactive, or potentially radioactive gases from various sources throughout the plant. Gaseous wastes are generated from reactor coolant degassing operations, processing of radioactive liquid wastes, and tank purging. These gases are collected and stored for decay in the gas surge tank prior to release to the environment. The gas surge tank acts as an accumulator for the system, allowing batch processing of the waste gases. The waste gas compressors process the gas, taking suction on the gas surge tank and discharging to a gas decay tank. The gas decay tanks collect the waste gas by the waste gas compressors and store it for approximately 60 days. This allows for the decay of the shorter lived nuclides and reduces the overall activity before the gas is discharged through the plant stack. _ Components of the containment vent header support the containment pressure boundary. Other GWM system components support the pressure boundary of the safety-related chemical and volume control (CVC) and the boron management (BM) system, which has no safety functions. In addition to the 10 CFR 54.4(a)(2).function described above, the GWM system has the following intended functions for 10 CFR 54.4(a)(1 ).
Support the pressure boundary of the chemical and volume control system.
Support containme_nt pressure boundary. Components that support the eve system are reviewed in Section 2.3.3.1, Chemical and Volume Control Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Hot Machine Shop and Decontamination Facilitv Ventilation The purpose of the hot machine shop and decontamination facility ventilation (HVD) system is to maintain a suitable operating environment for personnel and to limit concentrations of airborne radioactivity within the areas and in the exhausted air. The ventilation supply system includes two supply air handling units, one supplying the hot machine shop and the other the decontamination facility. Each air handling unit has a 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-118 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information medium efficiency filter, electric heating coil, chilled water cooling coil, a*nd centrifugal fan. Two exhaust air handling units, one each for the decontamination' room and hot machine shop, exhaust air using a medium efficiency filter, HEPA filter, and centrifugal Jan which discharges through a pneumatically operated damper and louver. The HVD system contains drain valves and piping located in the reactor building. Leak Rate Testing The purpose of the leak rate testing (LRT) system is to support integrated leak rate testing of the containment. The system includes pressure, temperature and humidity instrumentation and test connection valves on station air system containment penetrations (penetrations 63 and 65) and the H&V instrumentation penetration (penetration 53). These LRT valves form part of the containment pressure boundary. LRT system components containing indoor air and waste water are attached to safety-related equipment and located* in areas with safety-related equipment. In addition-to the 10 CFR 54.4(a)(2) function described above, the LRT system has the following intended function for 1 O CFR 54.4(a)(1 ).
Support containment pre_ssure boundary. Components that support containment pressure boundary are reviewec;l in Section 2.3.2.3, Containment Penetrations.
Liquid Waste Management The purpose of the liquid waste mc;inagement (LWM) system is to collect, store, process, monitor, and release liquid wastes while ensuring that all releases of radioactive materials, both in plant and to the environment, are within applicable requirements. The
system manages both radioactive and non-radioactive liquid wastes from process systems, equipment drains, and sumps. The system includes a variety of storage and collection tanks, pumps, piping, valves, filters, and instruments and controls. Post Accident Sampling
The purpose of the post accident sampling (PAS) system is to permit sampling of the primary coolant and safety injection sump following an accident. (Post-accident sampling of the containment atmosphere is supported by the hydrogen re.combiners and analyzers (HRA) system.) Components of the PAS system code are used to collect, cool and 2.0 -Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation.Results Page 2.3-119 \_ __ -*

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information analyze reactor ,coolant and safety injection sump samples. The system supports collection of diluted, undiluted, and full pressure liquid samples and gas grab samples. The PAS system consists of accumulators, a chiller, dryers, filters, heat exchangers, pumps, piping, valves, and instrumentation and controls. Post-accident sampling is not a safety function, and the system contains no safety-related components.

Nonsafety-related PAS components containing treated water or waste water are located in areas.with safety-related equipment. Potable Water The purpose of the potable water (PW) system is to distribute water from. the St. Charles* Parish Water System throughout the plant site. The system provides potable Wqter, both hot and cold, for drinking water, sanitary services, and emergency showers and eyewash stations. The distribution system also supplies makeup water to the fire water storage tanks and to the primary water treatment plant clearwell tank. The potable water distribution system may be used as necessary (if available) to replenish water to the wet cooling tower basins following a tornado. A hose connection in the makeup water supply to the fire water storage tanks and a p9rtable diesel-driven pump are provided to allow makeup from the potable water system to the wet cooling tower basins. However, because the availability of the potable water supply to the site is not assured following a tornado, this Is not an intended function for the potable water supply. The credited source is the Mississippi River through the circulating water system using the portable pump.
Potable water to the reactor auxiliary building is supplied via a solenoid-operated isolation valve. This valve isolates potable water to the reactor auxiliary building during a seismic event or piping rupture to prevent control room flooding. The system has no related components. Nonsafety-related components are located in areas with safety-related equipment. This includes piping and valves as well as a hot water storage tank and associated pump. In addition to the 10 CFR 54.4(a)(2) function described above, the PW system has the following intended function for 1 O CFR 50(a)(2), which is included in this review.
Isolate potable water from the reactor auxiliary building during a seismic event or piping rupture.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-120 I Primarv Makeup Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The prim.ary makeup (PMU) system provides storage and transfer capability necessary to supply demineralized water to primary plant systems including the chemical and volume control system, boron management system, reactor coolant system (reactor drain tank and quench tank), and waste management systems. The PMU system consists of a 260,000 gallon primary water storage tank (PWST) located in the yard, two full-capacity primary water pumps, and associated system valves, distribution piping, and instrumentation. PWST makeup comes from the demineralized water system. Th_e PMU pumps take suction from the PWST to supply primary grade water to plant loads. The system distribution piping includes safety-related components for a containment penetration. The system has no other safety functions except to support the pressure boundary of the eve system. . If.available. following a tornado, inventory from the PWST be used to replenish the wet cooling tower basin; however, because this tank is not protected from tornado missiles, this is not an intended function for the tank. The credited source is the Mississippi River through the circulating water system. In addition to 10 CFR 54.4(a)(2) function described above, the PMU system has the following intended functions for 10 CFR 54.4(a)(1). * . Support the CVC system pressure boundary.
Support containment pressure boundary. PMU system components that support the pressure boundary of the CVC system are reviewed in Section 2.3.3.1, Chemicaland Volume Control. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. PrimafY Sampling The purpose of the primary sampling (PSL) system is to collect and analyze fluid and gaseous grab samples from the reactor coolant system, chemical and volume control system, safety injection system, and the primary water storage tank during all modes of operation without requiring access to the containment. The PSL takes samples and brings them to a common location in the primary sampling room PSL panel in the reactor auxiliary building for analysis. The analyses performed on the samples determine fission and corrosion product activity levels, boron concentration, residual hydrazine, silica, lithium, pH and conductivity levels, crud concentration, dissolved gas concentration, and chloride. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-121 Waterford Steam Electric Station, Unit 3 License Renewal Application Techl']ical Information The PSL system includes safety-related components that form parts of the pressure boundary of the chemical and volume control system. The PSL system also includes components that are part of the containment pressure boundary. Other than the support of the safety-related system and containment pressure boundaries, the PSL system has no safety function. Safety-related components associated with safety injection (SI) system sampling are components in the SI system. In addition to the 10 CFR 54.4(a)(2) function described above, the PSL system has the following intended functions for 10 CFR 54.4(a)(1).
Support the *safety-related pressure boundaries of sampled systems.
Support containment pressure boundary. The PSL system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function (safety-related systems pressure boundaries) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). PSL system components that support the pressure boundary of the CVC system are reviewed in Section 2.3.3.1, Chemical and Volume Control. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Radiation Monitoring The radiation monitoring system consists of components in the ARM and PRM system codes:
The purpose of area radiation monitoring (ARM) components is to inform operations personnel, both locally and in the main control room, of radiation levels in areas where area radiation monitoring system detectors are located, provide warning when abnormal radiation levels occur in specific plant areas, and warn of possible equipment
malfunctions. Some channels of the area radiation monitoring system provide a containment purge isolation signal and enable main control room operators to monitor radioactivity levels inside the containment. In the event of a fuel handling accident, the area radiation monitoring system provides a signal to isolate the fuel handling building and start the emergency ventilation system. The purpose of process radiation monitoring (PRM) components is to sample, detect, measure, and record trends of radioactive concentrations in liquid process systems, ventilation systems, and airborne or liquid effluents. These components also provide 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-122 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information alc;1rms and automatic termination o-r redirection of liquid and airborne radioactive discharges. PRM components support the pressure boundary of monitored systems. The radiation monitors are comprised mainly of EiC components, which are within the scope of license renewal by default (see Section 2.1.1). Intended functions performed by EiC components are not reviewed here. However, there are safety-related mechanical components with the ARM system code associated with containment atmosphere radiation sampling. Also, the PRM system code includes mechanical components (pumps, valves, piping, heat exchangers, dryers, and filters) to support the operation of some process monitors. These mechanical components for most of the radiation monitors are not classified as safety-related and have no safety function. However, the mechanical components that support monitoring of the containment atmosphere, plant stack effluent, and component cooling water are classified as safety-related .. The containment atmosphere radiation monitor (PRM-IR-0100Y) takes particulate, iodine and gas readings of the containment atmosphere to help detect identified or unidentified leaks in the RCS pressure boundary. While the rad _monitor itself and certain components associated with the monitor are classified as safety-related, they* do not perform a function in accordance with the criteria of 10 CFR 54.4(a)(1) and are therefore not within the scope of license renewal for 1OCFR54.4(a)(1). This rad monitor is associated with a containment penetration, and the piping and valves associated with the penetration perform a safety function in accordance with the-_criteria of 10 CFR 54.4(a)(1). The plant stack monitors (PRM-IRE-0100.1, -0100.2) provide indication of the activity levels of radioactive materials released to the environs, so that determination of the total release is possible. They are credited in FSAR Section 15.7.3.4 (referred to as airborne radiation monitors) for a containment purge isolation signal. Although the containment purge isolation has no protective function in accordance with IEEE Standard 279-1971, isolation of containment purge (system code GAP) is conservatively credited to support the fuel handling accident analysis. Therefore, the PRM system performs a safety function associated with the plant stack rad monitors. The component cooling water radiation monitors provide for early detection of radioactivity leakage into normally nonradioactive systems. This is not a safety function in accordance with 1 O CFR 54.4(a)(1) nor does it support a safety function (not credited in an analysis of off-site dose release). However, these components have an intended function of supporting the pressure boundary of the component cooling water _system. In addition to the 1 O CFR 54.4(a)(2) function describe(j above, the radiation monitoring system has the following intended functions for 10 CFR 54,4(a)(1).
Support isolation of containment purge in the event of c;i fuel handl.ing accident. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results -Page 2.3-123 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Support component cooling water system pressure boundary.
Support containment pressure boundary. Nonsafety-related components that support dry cooling tower sumps discharge flow paths to the circulating cooling water system are reviewed in Section 2.3.3.14, Plant Drains. Components supporting the component cooling water system pressure boundary are reviewed in Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water. The plant stack monitors are included in Section 2.3.3.12, Miscellaneous HVAC. The safety-related mechanical components of the containment atmosphere radiation monitors are reviewed in Section 2.3.2.3, Containment Penetrations. Reactor Cavitv Cooling The purpose of the reactor cavity cooling (RCC} system is to maintain the ambient steady state air temperature in the annular space between the reactorvessel and the concrete primary shield wall below the maximum design basis air temperature of the reactor cavity during normal operations. The system has no safety function. The RCC system consists of two full-capacity axial supply fans arranged in parallel and connected to a common supply duct. Each fan is provided with a supply discharge gravity damper to prevent recirculation through the standby fan. Each axial supply fan . . draws cooled air from the containment cooling system ring header. The fans supply air to ventilate the annular space between the reactor vessel and primary shield wall. Resin Waste Management The purpose of the resin waste management (RWM) system is to collect and store spent radioactive ion exchanger resin from the various process demineralizers*and to transfer resins to the portable solidification and/or dewatering system. The RWM system includes a spent resin spent resin transfer pump, spent resin dewatering pump, spent resin strainers, and associated valves, piping and controls.
For NPIS penetrations 75 and 76, resin waste management system piping and valves provide flood barrier protection during a Probable Maximum Flood (PMF) event. In addition to the 10 CFR 54.4(a)(2) function described*above, the RWM system has the . following intended function for 10 CFR 54.4(a)(2).
Support NPIS flood barrier. Components that support the NPIS flood barrier are reviewed in Section 2.3.3.14, Plant Drains. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management'Review and Implementation Results Page 2.3-124 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Secondary Sampling The purpose of the secondary sampling system is to collect steam and water samples from the secondary cycle, the makeup demineralizer, the blowdown demineralizer, condensate transfer pump discharge, and the steam generators and to bring them to a common location in the secondary lab and sampling room for analysis. Water quality analyses are performed to provide a basis for the control of the secondary cycle water chemistry and steam generator integrity. The analyses performed on the samples are . appropriate to determine pH, specific and cation conductivity levels, silica, sodium, dissolved oxygen, and residual hydrazine concentrations. The secondary sampling system includes components of the secondary sampling (SSL) system code and the constant temperature bath (CTB) system code. The CTB system components provide constant temperature cooling water used to cool secondary plant samples. The system includes coolers, pumps, a sample recovery tank, piping, valves, and instrumentation and controls. The SSL system code includes safety-related components that support the pressure boundary of the main steam system. The SSL system code also includes components that are part of the containment pressure boundary. Other than the support of the main steam system and containment pressure boundaries, the secondary sampling system has no safety function. In addition to the 1 O CFR 54.4(a)(2) function described above, the secondary sampling system has the following intended functions for 10 CFR 54.4(a)(1).
Support the safety-related pressure boundary of main steam system.
Support containment pressure boundary. The secondary sampling system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function (main steam pressure boundary) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). Components that support the main steam pressure boundary are reviewed in Section 2.3.4.4, Main Steam. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-125 Solid Waste Management Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the solid waste management (SWM) system is to process, package and store low-level solid radioactive wastes for subsequent shipment and offsite burial. The SWM system code includes the waste concentrate storage tank, a dewatering tank, a *sodium silicate storage tank, a cement silo, pumps, and associated valves and piping. 'This equipment is not used. Isolation valves remain active in this system code. For NPIS penetration 114, solid waste management piping and a valve provide flood barrier protection during a Probable Maximum Flood (PMF) event. . . In addition to the 10 CFR 54.4(a)(2) function described above, the SWM system has the following intended function for 10 CFR 54.4(a)(2).
Support NPIS flood barrier. Components that support the NPIS flood barrier are reviewed in Section 2.3.3.14, Plant Drains.
Turbine Building Cooling Water The purpose of the turbine building cooling water (TC) system is to provide a heat sink for power cycle equipment during normal operation and shutdown conditions. The TC . system is a closed loop system which uses treated demineralized water to remove heat from the turbine auxiliaries and other components located within the turbine building. The water is circulated by two turbine cooling water pumps, and the heat removed via two turbine cooling water heat exchangers is transferred to the circulating water system. Components associated with the turbine building cooling water surge tank are located in the reactor auxiliary building. FSAR References The. following table lists the FSAR references for systems described in this section. System Code System FSAR Reference AE Air Evacuation Section 10.4.2 (main condenser evacuation system) ARR Airborne Radioactivity Removal Section 9.4.5.2 ANP Annulus Negative Pressure Section 9.4.5.8 AS Auxiliary Steam None 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-126 System Code BM CF CAP OF GWM HVD LRT LWM PAS PW PMU PSL ARM PRM RCC RWM SSL CTB SP, PME TC System Boron Management Chemical Feed Containment Atmosphere Purge Decontamination Facility Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Liquid Waste Management Post Accident Sampling Potable Water Primary Makeup Primary Sampling Radiation Monitoring Reactor Cavity Cooling Resin Waste Management Secondary Sampling Solid Waste Management Turbine Building Cooling Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information FSAR Reference Section 11.2.2.1 section 10.4.10 Section 9.4.5.3 None Section 11.3 Section 9.4.3.6 Figure 3.8-3 Section 11.2 Section 9.3.8 Section 9.2.4 Section 9.2.3 Section 9.3.2 Section 7.6.1.5 Section 11.5 Section 12.3.4 Section 9.4.5.6 Section 11.4.5 (spent resin transfer system) Section 9.3.2 Section 11.4 Section 9.2. 7 (turbine closed cooling water system) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-127 Components Subject to Aging Management Review Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to..:nonsafety interface up to a flexible connection or the end *of a piping run (such as a vent or drain line) or up to and including a mounted component (4) Ail endpoint of a plant-specific* piping design analysis to ensure that forces and moments are restrained in three orthogonal directions. For spatial interaction, auxiliary system components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to' aging management review in this 1 O CFR 54.4(a)(2) review if not already included in another system review .. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in an auxiliary system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 1 O CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 1 O CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related .SSCs directly connected to safety-related SSCs. Series 2.3.3-15-x tables list the component types for auxiliary systems that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. Series 3.3.2-15-x tables provide the results of the aging management review for auxiliary systems for 10 CFR 54.4(a)(2) based on potential for physical.interactions. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-128 System Code AE ARR ANP AS BAM BM eve CF CHW, RFR, scH, sec cw cc IA,SA CAP CAR CB DF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT LWM NG PAS PW System Name Air Evacuation Airborne Radioactivity Removal Annulus Negative Pressure Auxiliary Steam Boric Acid Makeup Boron Management Chemical and Volume Control Chemical Feed Chilled Water Circulating Water Component Cooling Water Compressed Air Containment Atmosphere Purge Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Liquid Waste Management Nitrogen Post Accident Sampling Potable Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Types AMR Results Table 2.3.3-15-1 Table 3.3.2-15-1 Table 2.3.3-15-2 Table 3.3.2-15-2 Table 2.3.3-15-3 Table 3.3.2-15-3 Table 2.3.3-15-4 Table 3.3.2-15-4 Table 2.3.3-15-5 Table 3.3.2-15-5 Table 2.3.3-15-6 Table 3.3.2-15-6 Table 2.3.3-15-7 Table 3.3.2-15-7 Table 2.3.3-15-8 Table 3.3.2-15-8 Table 2.3.3-15-9 Table 3.3.2-15-9 Table 2.3.3-15-10 Table 3.3.2-15-10 Table 2.3.3-15-11 Table 3.3.2-15-11 Table 2.3.3-15-12 Table 3.3.2-15-12 Table 2.3.3-15-13 Table 3.3.2-15-13 Table 2.3.3-15-14 Table 3.3.2-15-14 Table 2.3.3-15-15 Table 3.3.2-15-15 Table 2.3.3-15-16 Table 3.3.2-15-16 Table 2.3.3-15-17 Table 3.3.2-15-17 Table 2.3.3-15-18 Table 3.3.2-15-18 Table 2.3.3-15-19 Table 3.3.2-15-19 Table 2.3.3-15-20 Table 3.3.2-15-20 Table 2.3.3-15-21 Table 3.3.2-15-21 Table 2.3.3-15-22 Table 3.3.2-15-22 Table 2.3.3-15-23 Table 3.3.2-15-23 Table 2.3.3-15-24 Table 3.3.2-15-24 Table 2.3.3-15-25 Table 3.3.2-15-25 Table 2.3.3-15-26 Table 3.3.2-15-26 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-129 System Code System Name PMU Primary Makeup ,. PSL Primary Sampling ARM, PRM Radiation Monitoring HVR Reactor Auxiliary Building HVAC RCC Reactor Cavity Cooling RWM Resin Waste Management SSL, CTB Secondary Sampling SWM Solid Waste Management SP, PME Sump Pump TC Turbine Building Cooling Water License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Types AMR Results Table 2.3.3-15-27 Table 3.3.2-15-27 Table 2.3.3-15-28 Table 3.3.2-15-28 Table 2.3.3-15-29 Table 3.3.2-15-29 Table 2.3.3-15-30 Table 3.3.2-15-30 Table 2.3.3-15-31 Table 3.3.2-15-31 Table 2.3.3-15-32 Table 3.3.2-15-32 Table 2.3.3-15-33 Table 3.3.2-15-33 Table 2.3.3-15-34 Table 3.3.2-15-34 Table 2.3.3-15-35 Table 3.3.2-15-35 Table 2.3.3-15-36 Table 3.3.2-15-36 Additional details for components subject to aging management review are provided in the following license renewal drawings.
System Code System Name LRA Drawings AE Air Evacuation LRA-G163 ARR Airborne Radioactivity Removal LRA-G853 sh 11 ANP Annulus Negative Pressure LRA-G853 sh 1 AS Auxiliary Steam LRA-G 164 sh 2 BAM Boric Acid Makeup LRA-G168 sh 3 BM Boron Management LRA-G171 sh 1 LRA-G171 sh 2 LRA-G171 sh 3 eve Chemical and Volume Control LRA-G168 sh 1 LRA-G168 sh 2 CF Chemical Feed LRA-G164 sh 1 LRA-G164 sh 6 LRA-G170 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Manageme.nt Review and Implementation Results LRA-G170 sh 3 LRA-G171 sh 2 Page 2.3-130 System Code CHW, RFR, SCH, sec cw cc IA, SA CAP CAR CB OF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT System Name Chilled Water Circulating Water Component Cooling Water Compressed Air Containment Atmosphere Purge Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel 'Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LRA Drawings LRA-G853 sh 3 LRA-G853 sh 4 LRA-G853 sh 9 LRA-G164 sh 5 LRA-G164 sh 6 LRA-G158 sh 2 LRA-G160 sh 1 LRA-G160 sh 5 LRA-G160 sh 2 LRA-G162 sh 1 LRA-G160 sh 3 LRA-G162 sh 3 LRA-G 160 sh 4 LRA-G170 sh 6 LRA-G152 sh 4 LRA-G157 LRA-G152 sh 6 LRA-G164 sh 6 LRA-G152 sh 9 LRA-G853 sh 1 LRA-G853 sh 21 LRA-G853 sh 1 None None LRA-1564-2044 LRA-5817-9519 LRA-G164 sh 1 LRA-G164 sh 2 LRA-G853 sh 2 LRA-G163 LRA-G169 LRA-G170 sh 4 LRA-G170 sh 6 None LRA-G164 sh 1 LRA-G164 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-131 System Code LWM NG PAS PW PMU PSL ARM, PRM HVR RCC RWM SSL, CTB SWM SP, PME TC System Name Liquid Waste Management Nitrogen Post Accident Sampling Potable Water Primary Makeup Primary Sampling Radiation Monitoring Reactor Auxiliary Building HVAC Reactor Cavity Cooling Resin Waste Management Secondary Sampling Solid Waste Management Sump Pump Turbine Building Cooling Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LRA Drawings LRA-G170 sh 1 LRA-G170 sh 2 LRA-G170 sh 3 LRA-G166 sh 1 sh 2 LRA-G168 sh 2 LRA-G162 sh 3 None LRA-G161 sh 2 LRA-G170 sh 3 LRA-G168 sh 2 LRA-G170 sh 5 LRA-G162 sh 1 LRA-G162 sh 5 LRA-G164 sh 2 LRA-G853 sh 11 LRA-G853 sh 16 LRA-G853 sh 15 LRA-G853 sh 21 LRA-G853 sh 1 LRA-G168 sh 1 LRA-G170 sh 5 LRA-G170 sh 1 LRA-G171 sh 1 LRA-G170 sh 2 LRA-G162 sh 1 LRA-G162 sh 4 LRA-G162 sh 2 LRA-G 162 sh 6 LRA-G170 sh 5 LRA-G173 sh 2 LRA-G173 sh 3 l-RA-G159 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-132 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3;3-15-1 Air Evacuation System Components Affecting Safety-Related Systems Components Subject to Aging Management Review Co111ponent Type Intended Function Bolting Pressure bound.ary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components . Subject to Aging Management Review and Implementation Results Page 2.3-133 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body
Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Strw;:tures and Components Subject to Aging Management Review and Implementation Results Page 2.3-134 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-3 Annulus Negative Pressure System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-135 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Table 2.3.3-15-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-136 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-137 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Condenser (shell) Pressure boundary Cooler housing Pressure boundary Demineralizer Pressure boundary Evaporator Pressure boundary Filter housing Pressure boundary Flow element Pressure bOLmdary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-138 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-7 Chemical and Volume Control System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary .Demineralizer Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-139 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Cylinder Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-140 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-9 Chilled Water System Nonsafety-Related Components Affecting Safety-Related Systems . Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Sc:oping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-141 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-1 O Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review. Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Valve body Pre.ssure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplementatipn Results Page 2.3-142 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary . Filter housing Pressure boundary Flow element Pressure bo_undary Piping Pressure boundary .. Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-143 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-12 Compressed Air System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-144 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-13 Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boun*dary -Heater housing Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-145 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-146 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-147 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-148 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-17 Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-149 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-18 Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-150 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Orifice Pressure boundary . Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-151 Waterford Steam Electric Station, Unit 3 Licel')se Renewal Application Technical Information Table 2.3.3-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Cooler housing Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Separator Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-152 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-21 Hot Machine Shop and Decon Facility Ventilation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-153 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-154 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-23 Liquid Waste Management System Nonsafety-Related Components Affecting_ Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Condenser (shell) Pressure boundary Cooler housing Pressure boundary Demineralizer Pressure boundary Evaporator Pressure boundary Filter housing Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary body Pressu're boundary 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and_ Implementation Results Page 2.3-155 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary

Strainer housing Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping' and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-156 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Chiller housing Pressure boundary Heat exchanger (shell) Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-157 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-158 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-27 Primary Makeup System Nonsafefy-Related'Components Affecting Safety-Related Systems Components Subject to Aging Management.Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-159 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flex hose Pressure boundary Heat exchanger (shell) Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Trap Pressure boundary Valve body Pressure boundary Vessel Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-160 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing '" Pressure boundary Heat exchanger (shell) Pressure boundary Piping Pressure boundary Pump casing Press1,1re boundary Trap Pressure boundary *-. Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-161 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-162 Waterford S!eam Electric station, Unit 3 License Renewal Application TechniQal Information Table 2.3.3-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type . Intended Function Blower housing Pressure boundary Bolting Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-163 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-164 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-33
Secondary Sampling System Nonsafety-Related. Components Affecting Safety-Related Systems Components Subject to Aging Management Review-Component Type Intended Function Bolting Pressure boundary Cooler housing Pressure boundary Orifice .. Pressure boundary .-Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results I Page 2.3-165 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-34 Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting* Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-166 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Strainer housing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-167 Wate.rford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-168
2.3.4 Steam and Power Conversion Systems The following systems are included in this section.
Section 2.3.4.1, Condensate Makeup and Storage
Section 2.3.4.2, Emergency Feedwater
Section 2.3.4.3, Main Feedwater
Section 2.3.4.4, Main Steam Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-169 2.3.4.1
Condensate Makeup and Storage System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the condensate makeup and storage system is to make up water to, and discharge water from, the condensate system and to store and transfer demineralized water for initial fill and makeup to various normally nonradioactive systems throughout the plant. The condensate makeup and storage system includes components in system codes CML.i (condensate makeup and storage system) and DW (demineralized water system). The CMU system includes two sources of condensate makeup: the safety-related condensate storage pool in the reactor/auxiliary building and the nonsafety-related condensate storage tank in the yard. The CMU system also indudes component cooling water makeup pumps and a distribution subsystem for the condensate storage pool. The DW system includes the nonsafety-related demineralized water storage tank located in the yard. The condensate storage tank and demineralized water tank are provided with a nitrogen blanket to maintain the dissolved oxygen content. These tanks share a distribution subsystem comprised of pumps, piping and valves with component identification numbers that use the CC (component cooling water), CD (condensate), CMU, and DW system codes; for license renewal, these components are included with the condensate makeup and storage system review.
The condensate storage pool is the water supply for the EFW pumps. The flow path from the condensate storage pool to the EFW pumps is considered part of the condensate makeup and storage system. The condensate storage pool, component cooling water makeup pumps, and the associated distribution subsystem provide makeup to the component cooling water system. They can also distribute makeup to the emergency diesel generator jacket water standpipes, the essential chiller expansion tanks, and the fuel pool makeup fill and purification loop. The makeup supply to the spent fuel pool provides a seismic Category I makeup supply from the condensate storage pool. The nonsafety-related condensate storage tank, demineralized water tank, condensate storage tank pumps, condensate transfer pump, hotwell transfer pump, and the associated distribution subsystem provide demineralized water to various systems and components, including the condenser hotwell, the auxiliary boiler, the chemical feed system, auxiliary feedwater pump, condensate storage pool, refueling water storage pool, and auxiliary component cooling water wet cooling towers. This subsystem also provides water to hose stations inside the reactor building. Apart from the containment pressure boundary components, the distribution subsystem from the condensate storage tank and demineralized water tank has no safety function. If available following a tornado, inventory from the condensate storage tank and demineralized water tank may be used to replenish the wet cooling tower basin; however, becpuse these tanks are not protected from tornado missiles, this is not an intended function for the tanks. The credited source is the Mississippi River through the circulating water system. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-170 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Two nonsafety-related valves (CMU-908 and -909, fuel casket spray valve isolation and bypass) are credited as part of the flood barrier for the fuel handling building for the design basis flood. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(1 ).
Provide a source of makeup to the component cooling water system, the emergency diesel generators and the essential chilled water system.
Provide water for the EFW pumps.
Support containment pressure boundary. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(2).
Provide a makeup water supply to the spent fuel pool.
Provide flood barrier for design basis flood.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (EFW water supply and makeup to other safe shutdown equipment) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (EFW water supply) that demonstrates compliance with the *Commission's regulations for station blackout (10 CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-171

'; Waterford Steam EleCtric Station, Unit 3 License Renewal Application Technical Information FSAR References Section 9.1.3.1.e (spent fuel pool makeup) Section 9.2.3.2 (demineralized water) Section 9.2.6 (condensate storage) Section 10.4.9.2 (condensate storage pool) Components Subject to Aging Management Review Safety-related basket strainers in the condensate storage pool are reviewed in Section 2.4.2, Nuclear Plant Island Structure. Valves credited as flood barriers are reviewed in Section 2.3.3.14, Plant Drains. Components supporting the component cooling water system pressure boundary are reviewed in Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, . Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table 2.3.4-1 lists the component types that require aging management review. Table 3.4.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 153 sh 4 LRA-G 160 sh 6 LRA-G161-sh 2 LRA-G163 LRA-G 164 sh 2 LRA-G169 LRA-G853 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and-Components Subject to Aging Management Review and Implementation Results Page 2.3-172 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-1 Condensate Makeup and Storage System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Flow control Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Thermowell Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging.Management Review and Implementation Results Page 2.3-173 ! Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.2 Emergency Feedwater System Description The purpose of the emergency feedwater (EFW) system is to provide cooling water to the steam generators for the removal of decay heat from the reactor during emergency situations when the main feedwater system is not available. The system can also be used during emergency situations to cooldown the reactor coolant system to the temperature and pressure required for shutdown cooling system operation. The EFW system consists of two half-capacity motor-driven pumps, a full-capacity steam turbine-driven pump, and the associated piping and valves. For license renewal, the EFW system is considered to begin at the EFW pumps. Supply to the pumps from the condensate storage pool is provided by the condensate makeup and storage system. The three pumps take suction from a common suction header supplied by two lines from the condensate storage pool. The pumps discharge to a common supply header. Each EFW pump can be isolated by suction and discharge valves which are normally locked open. The suction and discharge lines of the pumps are normally cross-connected by locked-open manual valves. Water from the discharge header is then delivered to each main feedwater header through an arrangement of control and isolation valves. The discharge of the EFW pumps can supply either or both steam generators. Steam for the emergency feedwater pump turbine is supplied from either or both steam generators, taken upstream of the main steam isolation valves. The wet cooling tower basins of the auxiliary component cooling water system are available to the EFW pumps as an alternate source of water if the condensate storage pool becomes depleted. The EFW system has the following intended functions for 10 CFR 54.4(a)(1 ).

Provide cooling water to one or both steam generators for the removal of decay heat from the reactor during emergency situations when the main feedwater system is not available.
Support containment pressure boundary. The EFW system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-174 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The EFW system has the following intended functions_for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 10.4.9 Components Subject to Aging Management Review The emergency feedwater pump turbine and EFW components that support the lube oil cooler for the emergency feedwater pump turbine governor and governor valve servo are reviewed in Section 2.3.4.4, Main Steam.' Components with an EFW component identification in the flow path from the condensate storage pool to the EFW pumps are reviewed in Section 2.3.4.1, Condensate Makeup and Storage. Nonsafety-related components of the system not included in other reviews whose failu-re could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 1 O CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table-2.3.,4-2 lists the _component types that require aging management review. Table 3.4.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject fo aging management review are provided in the following license renewal drawings. LRA-G 153 sh 4 LRA-G 160 sh 6 2,0 _ Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-175 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-2 Emergency Feedwater System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Coil Heat transfer Pressure boundary Heat exchanger (housing) Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-176 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.3 Main Feedwater. System Description The purpose of the main feedwater (FW) system is to supply water from the condensate system to the steam generators at the proper pressure, temperature and flow rate to maintain steam generator water level under all plant operating conditions. The FW system components are arranged in two parallel paths that provide feedwater to each steam generator. The FW system consists of two turbine-driven pumps, three high-pressure heaters, regulating valves, isolation valves, and other miscellaneous valves and piping. A control system*operates the regulating valves and controls feed pump speed to maintain steam generator water level: The condensate system supplies water to the suction of the .feedwater pumps. Each feedwater pump discharges to the combined discharge header, which feeds three parallel high-pressure feedwater heaters. The heaters discharge to a single header.that splits to supply each steam generator. Following the split in the header, a flow venturi measures feedwater flow to each steam generator. Each steam generator feedwater supply line has one main feedwater regulating valve, one start-up feedwater regulating valve, and one motor-operated feedwater regulating bypass valve. Downstream of the regulating valves, the feedwater flows through a check valve, main feedwater isolation valve, and another check valve before going to the steam generator. The emergency feedwater (EFW) system ties into the feedwater lines downstream of the main feedwater isolation valves. When required, automatic isolation of the steam generators is provided by the main feedwater isolation valves with backup from the main feedwater regulating.valves and start-up feedwater regulating valves. The portion of the FW system from the check valves located outside containment to the steam generator feed nozzles is part of the containment pressure boundary. The FW system has the following intended functions for 10 CFR 54.4(a)(1).
Provide automatic isolation of the feedwater flow to the steam generators. I
Support the delivery of emergency feedwater to the steam generators.
Support containment pressure boundary. The FW system has the following intended functions for 1 O CFR 54.4(a)(2).
Provide backup automatic isolation of the feedwater flow to the. steam generators. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-177
' .. , i \ i I "'-. ... ./ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The FW system has the following intended functions for 1 O CFR 54.4(a)(3).
Perform a function (EFW system support, FW isolation) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (EFW system support) that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). FSAR References Section 10.4.7 Components Subject to Aging Management Review Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table 2.3.4-3 lists the-component types that require aging management review. Table 3.4.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G151 sh 1 LRA-G 153 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-178 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-3 Main Feedwater System Components Subject to Aging Management Review Component Type In.tended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary *' Tubing Pressure boundary \(alve body Pressure boundary -2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-179 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.4 Main Steam System Description This review includes the main steam system and supporting functions performed by the steam generator blowdown system and the reheat steam system. Main Steam The purpose of the main steam (MS) system is to convey steam from the steam generators to the high pressure turbine and to other auxiliary equipment for power generation. During power operating conditions, main steam normally supplies the high pressure main turbine, the moisture separator reheaters, and the auxiliary steam system. During reduced power conditions, main steam replaces or supplements steam to the feedwater pump turbines and the gland seal steam system. The main steam system is the source of steam for the turbine-driven emergency feedwater pump. The MS system provides for overpressure protection for the steam generators and main steam lines, discharges steam to the condenser or atmosphere when the main turbine* is unavailable, and provides for isolation of the main steam lines when required.
The main steam system conveys steam from the steam generators to the high pressure turbine through the containment vessel in two main steam lines. Downstream of the steam generators, / each main steam line has a flow element, six safety relief valves, a power-operated atmospheric relief valve, and a main steam isolation valve (MSIV). A steam supply line to the emergency feedwater pump turbine branches from each main steam line, upstream of the MS IVs. Downstream of the MSIVs, the main steam lines supply the high pressure turbine, the gland seal system, the auxiliary steam system, and a common main steam header. Lines from the main steam header supply the moisture separator reheaters, the steam generator feedwater pump turbines, and the steam bypass system. The steam bypass system, comprised of in the MS system code, includes six valves connected to the main steam header that discharge steam directly to the main condenser. In the event of a steam line break upstream of an MSIV and a failure of the MSIV to close on the unaffected steam generator, blowdown of the unaffected steam generator is prevented by the closure of the nonsafety-related*turbine stop valves and turbine bypass valves that serve as an acceptable backup for this accident. The MS system has the following intended functions for 10 CFR 54.4(a)(1).
Isolate the SGs from the non-safety portions of the MS system during emergency con.ditions by automatic closure of the MS IVs. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-180 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Dissipate heat generated and accumulated in the nuclear steam supply system (N$SS) to atmosphere during emergency conditions by operation of the main steam safety valves and/or the atmospheric dump valves until shutdown cooling can be initiated.
Provid.e main steam line and steam generator overpressure protection.
Provide redundant flow paths for the steam supply to emergency feedwater pump turbine.
Support containment pressure boundary. The MS system has the following intended functions for 10 CFR 54.4(a)(2).
Prevent blowdown of the µnaffected steam generator during a main steam line break ever:it when the fault is upstream of one MSIV and .the single failure is the failure of the other steam generator MSIV to close.
Maintain integrity of nonsafety-related components such that no physical interaction with safefy-related components could prevent satisfactorY accomplishment of a safety function. The Ms system has the following intended functions for 10 CFR 54.4(8)(3).
Perform a function (relief valves, MS IVs, EFW) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function (support EFW) that demonstrates compliance with the Commission's . regulations for station blackout (10 CFR 50.63). Blowdown The purpose of the steam generator blowdown (BO) system is to control the chemical composition of water in the steam generator shells. The BO system removes water from the steam generators to maintain water chemistry. Two blowdown lines, one from each steam generator, exit the containment through their own penetrations. Two air-operate.d containment isolation valves, one inside and one outside, are located in each of the lines exiting containment. Downstream of the containment isolation valves, blowdown water pressure and temperature are reduced, and the water is processed through mixed bed demineralizers or processed as waste. Clean water is returned to .the secondary system. The system includes tanks, heat exchangers, pumps, demineralizers, piping, valves, flow elements, and instrumentation. The portion of the BO system from the steam generators to and including the outside containment isolati6n valves comprises an extension of the steam generator boundary. The remainder of the BO system has no safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-181 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The BD system has the following intended functions for 10 CFR 54.4(a)(1).
Support*the steam generator pressure boundary.
Support containment pressure boundary. The BD system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The BD system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (blowdown isolation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Reheat Steam The purpose of the reheat steam (RS) system is to reheat and dry the high pressure turbine exhaust by means of the moisture separator reheaters and to provide the reheated steam to the low pressure turbines. Two horizontal axis, cylindrical shell combined moisture*separa.tor and. ' . ' reheater assemblies are installed in the steam lines connecting the high pressure and low pressure turbines.
Steam from the high pressure turbine passes up through the moisture separators. The water . separated from the steam is drained from the moisture separator-reheaters to the moisture separator reheater shell drain tanks, which drain into the intermediate pressure feedwater heaters. The steam then flows through the rehe.ater section of the moisture separator-reheater, where it is heated by a steam tube bundle. Main steam is supplied to this tube bundle froi:n the main steam line. The condensate from this tube bundle is drained to the moisture *separator reheater drain collector tank, which drains into the high feedwater heaters. Steam flow from the moisture separator reheaters is then directed to the low pressure turbines. A sepa_rate outlet located on Moisture Separator Reheater 8 supplies steam flow for normal operation of the feedwater pump turbines. In the event of a steam line break upstream of an MSIV and a failure of the MSIV to close. on the unaffected steam generator, blowdown of the unaffected steam generator is prevented by the closure of the nonsafety-related turbine stop valves and turbine bypass valves that serve as an acceptable backup for this accident. Part of this flow path is isolated by two RS valves to the steam generator feedwater pump turbines. The RS system has no intended functions for 10 CFR 54.4(a)(1). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-182 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The RS system has the following intended for 1 O CFR 54.4(a)(2).
Support preventing blowdown of the unaffected steam generator during a main steam line break event when the fault is upstream of one MSIV and the single failure is the failure of the other steam generator MSIV to close. The RS system has no intended functions for 1 O CFR 54A(a)(3): FSAR References Section 10.3 (main steam supply system) Section 10.4.4 (steam bypass system, also referred to as turbine bypass system) Section 10.4.8 (steam generator blowdown) Section 10.2.2.2.4 (reheat steam) Components Subject to Aging.Management Review The nitrogen chambers in the MSIV aCtuators are reviewed in Section 2.3}.11, Nitrogen. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfacfory accomplishment of safety functions are reviewed in* Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR S4.4(a)(2r Remaining compo-nents a're. reviewed as listed below .. Table 2.3.4-4 lists the component types that require aging manage*ment-review. _ Table 3.4.2-4 the results of the aging mariagemertt review. . License Renewal. Drawings Additional details for components subject to aging management review are provided in the followi_ng license renewal drawings. LRA-G151 sh 1 LRA-G151 sh 2 LRA-G151 sh 4 LRA-G 162 sh 2
LRA-G164 sh 5 LRA-G 165 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-183 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-4 Main Steam System Components Subject to Aging Management Review Component Type Intended Function Bearing housing Pressure boundary Bolting Pressure boundary Filter housing Pressure boundary Flow element Flow control Pressure boundary Heat exchanger (channel Pressure boundary head) Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Nozzle Flow control Pressure boundary Orifice Flow control Pressure boundary Piping . ,. Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer Filtration Strainer housing Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary ,* Turbine casing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Subject to Aging Management Review and Implementation Results Page 2.3-184 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a}(2) As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are* not discussed in this section. Phvsical Failure This section summarizes the scoping and screening results for steam and power conversion (S&PC) systems based on 10 CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures* may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.1 and 2.1.2.1.2. Physical Impact or Flooding _ .
The evaluation of interactions due to physical impa9t or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-185 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this criterion affected S&PC systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Spray Nonsafety-related system components or nonsafety-related portions of safety-related systems containing water; oil, or steam are considered within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. S&PC systems meeting this criterion are within the scope of license renewal per 1 O CFR 54.4(a)(2). The following S&PC systems, described in the referenced sections, are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) for physical interactions. System Number System Name Section Describing System BO Slowdown Section 2.3.4.4, Main Steam CD Condensate Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) CMU Condensate Makeup and Storage Section 2.3.4.1, Condensate Makeup and ow Storage EFW Emergency Feedwater Section 2.3.4.2, Emergency Feedwater FW Main Feedwater Section 2.3.4.3, Main Feedwater MS Main Steam Section 2.3.4.4, Main Steam System Description The following system within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) is not described elsewhere in the application. Condensate The purpose of the condensate (CD) system is to supply purified and preheated water to the feedwater pumps via the condensate polishers and low-pressure and 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-186 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information intermediate-pressure feedwater heaters. The system also supplies water to the steam generator blowdown system, feedwater pump glands, and condenser exhaust hood spray. The major components of the condensate system are the main condenser, condensate pumps, gland steam condenser; low-pressure feedwater heaters, and pressure feedwater heaters. Apart from the condensate polisher system components, the condensate system includes the components in the feedwater flow path from the main condenser hotwell up to the feedwater pump suction. Condensate flow begins at the main condenser hotwell. The main condenser functions as the heat sink for the low-pressure turbines and pump turbines exhaust, main steam system bypass steam, and miscellaneous flows, drains and vents during normal operation. The condenser also provides de-aeration of the condensate. The pumps discharge water through the polishing demineralizers. A portion of the flow then passes through the tubes of the gl_and.steam condenser, which receives the exhaust steam from the glands of the main turbine and the feedwater pump turbines and condenses it back into water. After the gland steam condenser, the condensate flows through three parallel strings of low-pressure feedwater beaters and then through the
three pcirallel strings of intermediate-pressure feedwater heaters. Water exits the intermediate-pressure heaters and is combined with the discharge of the heater drain pumps (system FHD). The total water flow is sent to the combined suction of the steam generator feed pumps. The CD system code is used for safety-related piping that supports the flow path from ,the condensate storage pool to the emergency feedwater pumps. Safety-related piping using the CD system code also supports the condensate makeup and storage fill line to the condensate storage pool and the refueling water storage pool; the fill lines are pressure boundaries for the pools. This safety-related piping is reviewed for license renewal *as part of the condensate makeup and storage system (Section 2.3.4.1 ). The CD system code has no other mechanical components that are safety-related. The CD system has no .intended functions for 1 O CFR 54.4(a)(1 ). *. The CD system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory
accomplishment of a safety function. The CD system has no intended functions for 1 O CFR 54.4(a)(3). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-187 FSAR References Section 10.4.7 Components Subject to Aging Management Review Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is .defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A. boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. . (4) An endpoint of a plant-specific piping design anaiysis to ensure that. forces and moments are restrained in three orthogonal directions. For spatial interaction, S&PC system containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety.:related piping in an S&PC system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 10 CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related SSCs directly connected to safety-related SSCs. Series 2.3.4-5-x tables list the component types for S&PC systems that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-188 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Series tables provide the results of the aging management review.for S&PC systems for 1 O CFR 54.4(a)(2) based on potential for physical interactions. System Number System Component Types AMR Results SD Slowdown Table 2.3.4-5-1 Table CD Condensate Table 2.3.4-5-2 Table 3.4.2-5-2 CMU Condensate Makeup and Storage Table 2.3.4-5-3 .Table 3.4.2-5-3 DW EFW Emergency Feedwater . Table 2.3.4-5-4 Table 3.4.2-5-4 FW Main Feedwater Table 2.3.4-5-5 Table 3.4.2-5-5 MS Main Steam Table 2.3.4-5-6 Table 3.4.2-5-6 License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. System Code System LRA Drawings SD Slowdown LRA-G164 sh 5 LRA-G164 sh 6 LRA-G173 sh 1 CD Condensate LRA-G164 sh 2 LRA-G164 sh 6 CMU Condensate Makeup and Storage LRA-G160 sh 1 DW LRA-G161 sh 2 LRA-G162 sh 3 EFW Emergency Feedwater LRA-G153 sh 4 FW Main Feedwater LRA-G153 sh 4 MS Main Steam LRA-G151 sh 1 LRA-G151 sh 4 LRA-G165 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results .. LRA-G163 LRA-G853 sh 9 Page 2.3-189.

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Demineralizer Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Heat exchanger (shell) Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to ,A.ging Management Review and Implementation Results Page 2.3-190 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4.;5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-191 ,. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-3 Condensate Makeup and Storage System Nonsafefy-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-192 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-193 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-5 Main Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-194 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-6 Main Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Module8 Support for criterion (a)(1) equipment Piping Pressure boundary Strainer housing Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary a. The MSIV hydraulic pump module provides lube oil that is used to maintain the MSIVs open. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-195 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES The following structures and structural components are within the scope of license renewal.

Section 2.4.1, Reactor Building
Section*2.4.2, Nuclear Plant Island Structure
Section 2.4.3, Turbine Building and Other Structures
Section 2.4.4," Bulk Commodities 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4.1 Reactor Building Description The reactor building is a Category I structure comprised of a free-standing steel containment vessel and a containment internal structure. The steel containment vessel is enclosed inside the shield building, which is a reinforced concrete structure. The reactor building, and all other seismic Category I structures are housed in a common reinforced concrete structure called the nuclear plant island structure (NPIS). The purpose of the reactor building is to support and protect the enclosed vital mechanical and electrical equipment, including the reactor vessel, the reactor coolant system, the steam generators, pressurizer, auxiliary and engineered safety features systems required for safe operation and shutdown of the reactor. The safety function of the reactor building is to limit the release of radioactive fission products following an accident thereby limiting the dose to the public and control room operators. The reactor building structure also provides physical support for itself, the reactor coolant system, engineered safety features, and other systems and equipment located within the structure. In addition, the reactor building supports the plant stack and also serves as a reliable final .barrier against the escape of fission products to ensure the leakage limits are not exceeded and fission product releases are within 1 O CFR 20 during normal plant operation and 10 CFR 50.67 during the postulated design basis accidents. The exterior walls and dome of the concrete shield building provide protection for the reactor vessel and all other safety-related system, structures and components inside the steel containment from missiles and natural phenomena. The carbon steel components and the concrete inside the steel containment vessel are credited as structural heat sinks in the energy absorption analysis during a loss of coolant accident. The reactor building and its associated structures contains jib cranes and monorails used for maintenance related activitie_s. During normal operations this equipment is stored and restrained in a designated storage position. An annular space is provided between the walls and domes of the steel containment vessel and concrete shield building to permit in-service inspections. A more detailed description of the reactor building is provided below. Steel Containment Vessel The steel containment vessel is a vertical upright cylinder, all welded steel pressure vessel with hemispherical dome and ellipsoidal bottom which houses the reactor pressure vessel, the reactor coolant piping, the pressurizer, the quench tank, the reactor coolant pumps, the *steam generators, and the safety injection tanks. It is completely enclosed by the reinforced concrete shield building. The steel containment vessel ellipsoidal bottom is totally encased in concrete and founded on the concrete base and common foundation mat with the shield building. A circular bridge crane or polar crane is used inside containment _to facilitate maintenance activities 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-2 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information during refueling. The polar crane girder support plates are welded to the shell liner. Except for some miscellaneous platform framing and some minor seismic restraints, no major floor framing or seismic restraint supports are attached to the shell liner. An equipment hatch constructed of carbon steel has been provided to enable passage of large equipment and components from the outside into the steel containment vessel during plant shutdown. The equipment hatch is a welded steel assembly, with a double gasket flanged and bolted cover. Additionally, two carbon steel personnel airlocks provide personnel access from the reactor auxiliary building into the steel containment vessel. The airlocks are equipped with double doors that are interlocked to prevent simultaneous opening of the two doors. Each door is designed with a double gasket to ensure a high degree of leak tightness. In addition to the equipment hatch and personnel airlocks, containment penetrations include piping penetrations (including the fuel transfer tube penetration) and electrical penetrations. Containment penetration assemblies form openings through the shield building and steel containment vessel for passage of electrical conductors, HVAC ducts, and process system piping, including the fuel transfer tube penetration. The function of the containment piping penetration assemblies is to provide for passage of process, service, sampling and/or instrumentation pipe lines (or in the case of the fuel transfer assembly, new or speriffuel) into the steel containment vessel, while maintaining the desired containment integrity and providing a leak-tight seal with adequate provisions for movement between the piping components and the

containment structure during operation. The safety-related containment integrity function is shared by the steel containment vessel, shield building, containment isolation system and penetration assemblies. Some assemblies, .such as guard pipes, also function as barriers between high energy process systems and the containment annulus, preventing pressurization of the annulus in the event of a high energy line preak. Bellows expansion joints serve to provide for the passage of process pipes into the containment while maintaining a leak tight seal between them and to absorb relative movements (thermal and/or seismic) between the containment vessel, shield building and/or the process piping. Bellows assemblies located between the containment vessel and the flued head are designated as primary bellows. Those bellows assemblies located between the shield wall and the flued head are designated as secondary bellows. The steel containment vessel contains one seismic Category I safety injection system (SIS) sump*and one containment sump. The SIS sump is a large collecting reservoir designed to provide an adequate supply of water to the containment spray system and SIS during the recirculation mode. The SIS sump is located at the lowest floor elevation inside containment exclusive of the reactor vessel cavity and containment sump. The containment sump, which is located at the lowest point within the reactor cavity, collects liquid discharges of low purity reactor grade) wastes from equipment, tanks, miscellaneous leak-off points, and floor drainage. Two sump pumps discharge the sump contents to the waste tanks through a radiation monitor located outside* the containment. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-3 Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Trisodium phosphate dodecahydrate (TSP) is stored in the containment in multiple containers located on the -11' MSL elevation. The containers are constructed of stainless steel angles, stainless steel plates at and bottom, and stainless steel wire mesh on the four vertical sides. The containers are all welded construction with a hinged top plate to allow for TSP surveillance inspection. The function of the TSP is to raise the SIS sump pH following a design basis loss of coolant accident. . Containment Internal structure The containment internal structures components and framing are seismic Category I and are enclosed completely by the steel containment vessel. The concrete components are the primary and secondary shield walls, a refueling canal, enclosures around the pressurizer and the regenerative heat exchanger. The internal steel structures are the reactor vessel, steam . generators and the reactor coolant pump support framing along with pipe, duct and tray . restraints, operating floor framing, and miscellaneous platform framing. Concrete floor fill, placed in the bottom. of the steel containment vessel support the internal structures. The concrete floor fill, concrete primary and secondary shield walls and the concrete enclosures form compartments within which the entire reactor coolant system is located. The primary and secondary shield walls and other containm_ent internc;il structures provide protection from internal missiles. The purpose of the internal structures is to provide structural support and radiation shielding for the reactor coolant system, auxiliary systems, and engineered features.
Around the reactor pressure vessel is a* primary shield wall. This wall is a rectangular reinforced concrete structure and provides support for the reactor vessel through a ring girder. A secondary shield wall consisting of two half-cylindrical reinforced concrete walls, enclose the steam generators, reactor coolant pumps and reactor coolant piping, located on each side ofthe reactor
vessel. A concrete pedestal resting upon the concrete floor fill provide support for the steam generators. The pressurizer and regenerative heat enclosures consist of reinforced concrete walls, supporting floor, and a roof forming compartments abutting the secondary shield wall. Vent openings in the pressurizer enclosure walls and supporting floor slab.provides for pressure relief. The secondary i;;hield wall and adjacent columns located on the concrete fill support both walls. The enclosures provide biological shielding during normal operation. For the'f>ressurizer enclosure the walls also serve to contain potential missiles. A watertight permanent cavity seal ring (PCSR) is installed between the reactor vessel flange .. and floor of the refueling pool specifically for the refueling operation. The PCSR has multiple hatches, which can be opened to provide access for activities within the reactor cavity. These hatches also allow for ventilation between the reactor cavity and the refueling cavity. During plant outages removable hatch covers are installed to provide a watertight seal. Double 0-ring_ 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.4-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information seals act against the PCSR and the removable hatches. A welded flexure ring is provided on the reactor vessel seal ledge and the refuel pool embedment ring. The flexure ring design permits relative displacement (due to a safe shutdown earthquake) between the vessel flange and the pool floor while still maintaining a watertight seal. To ensure a leak tight seal, the seals for the removable hatches are tested after installation and before flooding the pool. The refueling canal connects the reactor cavity and the spent fuel storage pool of the fuel handling building through the fuel transfer tube. The refueling cavity concrete provides a support structure for the operating floor, intermediate platform and* the missile shield above the reactor pressure vessel. The refueling cavity will be flooded with borated water during refueling.
Therefore, the refueling canal reinforced concrete walls are provided with a stainless steel liner completely covering the interior face of the cavity for the purpose of rendering the refueling cavity completeiy watertight. A refueling machine is the principal means of transporting fuel assemblies between the reactor cavity and the fuel transfer tube. The steel platform travels on steel tracks along each side of the reactor cavity above the refuel canal pool. Shield Building The shield building is a free standing structure without any structural ties between it and the steel containment yessel above the foundation level. Concrete fill placed in the bottom of the structure provides support of the steel containment. The shield building, supported on the common foundation of the NPIS, is a reinforced concrete structure constructed as a right cylinder with a shallow dome roof. Conventional reinforcing steel bars were used throughout the structure. Clearance between the bottom face of the concrete shield building dome and the top of the steel containment dome allows for access for inspection and to assure freedom of movemenf ofthe steel containment. An annulus airlock is provided for access from the outside environment to the shield building annular space. A shield building maintenance hatch is provided for equipment access to the steel containment vessel. A seismic Category I concrete filled door is provided for. this maintenance hatch at the exterior face of the shield building to protect this access opening. The door is double sealed to prevent in-leakage to the containment annulus space. The function of the shield building is to protect the steel containment vessel from external missiles and the annular space provided between the interior face of the concrete shield building walls and the outside face of the steel containment vessel provides the means for collecting and diluting any leakage. The reactor building has the following intended functions for 10 CFR 54.4(a)(1), (a)(2) and (a)(3).
Provide physical support, shelter and protection for safety-related equipment within the scope of license renewal. (10 CFR 54.4(a)(1)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Provide primary containment to limit the release of radioactive materials so that offsite doses from a postulated design basis accident are below the guideline values of 10 CFR 50.67. (10 CFR 54.4(a)(1)) .
Maintain integrity of nonsafety-related structural components such that safety functions are not affected. (1 O CFR 54.4(a)(2))
Provide shelter, support and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. The reactor building
houses equipment credited in the safe shutdown analysis for fire protection (10 CFR 50.48), for station blackout (10 CFR 50.63) and for anticipated transients without scram (10 CFR 50.62). (10 CFR 54.4(a)(3)) FSAR References Section 3.8.1 Section 3.8.2 Section 3.8.3 Section 3.8.4 Section 6.1.3 Section 6.2.2.2.2.1 Section 9.3.3.2.1.2 Figure 1.2-17 Figure 1.2-18 Figure 1.2-19 Figure 1.2-20 Figure 1.2-21 Figure 1.2-22 Components Subject to Aging Management Review Figure 3.8-31 Figure Figure 3.8-44 Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. structural commodities that are unique to the reactor building are included in this review. Those, that are common to in-scope systems and
structures (anchors, embedments, pipe and equipment supports, instrument panels and racks, cable trays, conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. Table 2.4-1 *lists the component types that require aging management review. Table 3.5.2-1 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Page 2.4-6 Subject to Aging Management Review and Implementation Results
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 Reactor Building Components Subject to Aging Management Review Component Crane: rails and str.uctural girders Crane: structural gii"ders Penetration bellows Penetration sleeves Plant stack. Steel components: annulus access lock Steel components: beams, columns and plates *steel components: impingement barriers Steel components: jib cranes Steel components: liner plate Heat sink Support for Criterion (a)(2) equipment Heat sink Support for Criterion (a)(2) equipment Enclosure protection Heat sink Pressure boundary Support for Criterion (a)(1) equipment Enclosure protection Heat sink Pressure boundary Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) .equipment Fire barrier Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Heat sink Missile barrier Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(2) equipment *Heat sink Support for Criterion (a)(1) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Intended Function Steel components: maintenance hatch shield Fire barrier door Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Steel components: monorails Heat sink Support for Criterion (a)(2) equipment Steel components: personnel airlock, escape Enclosure protection lock, construction hatch, maintenance hatch Fire barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: personnel airlock, escape Pressure boundary lock, construction hatch; maintenance hatch: Support for Criterion (a)(1) equipment locks, hinges; and closure mechanisms Steel components: pressure retaining bolting Heat sink Pressure boundary. Support for Criterion (a)(1) equipment Steel component: reactor missile shield Heat sink Missile barrier ' Support .for Criterion (a)(1) equipment Steel component: reactor cavity seal ring and Flood barrier hatches Heat sink Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Steel components: refueling maintenance Heat sink structure Support for Criterion (a)(2) equipment Steel components: refueling platform Heat sink equipment assembly and rails Support for Criterion (a)(2) equipment Steel elements (accessible areas): liner; liner Enclosure protection anchors; integral attachments (steel Heat sink *, containment vessel) Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Steel elements (inaccessible areas): liner; liner anchors; integral attachments (steel containment vessel) elements: SIS sump screens/strainers Support members: welds; bolted connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) Support members: welds; bolted c.onnections; support anchorage to building structure (supports and restraints for the reactor pressure vessel) Beams, columns, floor slabs and interior walls (primary and secondary shield walls; pressurizer compartments; reactor cavity; l!lnd missile shield and barriers) Concrete (accessible areas): shield building; all Concrete (accessible areas): refueling canal Intended Function Enclosure protection Heat sink* Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Heat sink Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(1) equipment Enclosure protection Heat sink Missile barrier . Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment . Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Concrete (accessible areas): shield building wall and dome;. interior and above-grade *exterior Concrete (inaccessible areas): refueling canal Concrete (inaccessible areas): shield building; all Compressible seals for annulus lock; escape lock; personnel lock; maintenance hatch Containment penetration seals and sealant Inflatable seal for maintenance hate.ti shielding door Moisture barrier Service Level I coatings Intended Function Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2).equipment Support for Criterion (a)(3) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(t) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Pressure boundary Support for Criterion (a)(1) equipment Pressure boundary Support for Criterion (a)(1) equipment Pressure boundary Support for Criterion (a)(1) equipment _ Enclosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying St.ructures and Components Subject to Aging Management Review and Implementation Results page 2.4-1 O (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4.2 Nuclear Plant Island Structure Description The nuclear plant island structure contains the component cooling water system structure, fuel handling building, reactor auxiliary building, and reactor building. The reactor building is addressed separately in Section 2.4.1. Nuclear Plant Island Structure lNPISJ The purpose of the NPIS is to provide a common structure for the building, reactor auxiliary building, fuel handling building, and component cooling water system*sfructure as well as providing a common foundation mat for these structures. The nuclear plant island structure is a seismic Category I structure supported on a continuous reinforced concrete foundation mat. The NPIS is a reinforced concrete box structure with solid exterior walls. All exterior doors and penetrations below elevation +30 feet which lead to areas containing safety-related equipment are watertight. The structure is founded on a continuous reinforced concrete foundation resting on a compacted shell filter blanket, which is supported by the Pleistocene sediments. Double water stops are provided at the construction joints in the foundation mat, while single water stops for vertical construction joints in the exterior walls are provided up to elevation +30 feet. In addition, stainless steel plates are provided at the bottom of the mat, where sumps and mal'}holes are located. The cylindrical wall of the shield building is direcUy founded on the common mat as well as the steel containment vessel, which is supported on the concrete fill. To assure proper contact between the containment and the concrete fill, the !nterface is grouted with epoxy between the concrete fill and the bottom of the vessel through channels left by pulled tubing. The primary shield wall, secondary shield wall and refueling canal of the internal structure are also founded on concrete fill supported by the NPIS.

The nuclear plant island structure has the following intended function for 10 CFR 54.4(a)(1), (a)(2) and (a)(3). *
Provides physical support, shelter, and protection for safety-related systems*, structures, and components within the scope of license renewal. (10 CFR 54.4(a)(1))
Provides physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure* could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (1 O CFR 50.48) and station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-11 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling Water Svstem Structure The purpose of the component cooling water system (CCWS) structure is to provide a source of cooling water for safe shutdown of the plant. The CCWS structure is located on the east and west side of the reactor building. The structure comprises two independent sets of dry and wet cooling towers in conjunction with water stored in the wet cooling tower basins. Each set of dry and wet cooling towers consists of reinforced concrete box structures supported on the common mat foundation of the nuclear plant island structure. An access to the equipment hatch of the reactor building is provided in the west CCWS structure. The motor control centers and the transformers for the dry and wet cooling towers are protected from tornado missiles by grating capable of withstanding tornado missile impact. The purpose of the component cooling water system structure is to house the CCWS, which services all reactor auxiliaries and serves as the ultimate heat sink. The ultimate heat sink is defined as the dry cooling towers, the wet cooling towers, and the water stored in the wet cooling tower basins.
Dry Cooling Tower The dry cooling towers consist of two separate and independent forced draft cooling towers. Each dry cooling tower is subdivi.ded into five reinforced concrete and each chamber is equipped with three fans supported on the walls at different levels in each of these chambers. The cooling coils of three of the dry cooling tower chambers of each tower are protected from tornado missiles by grating located above the coils. Dry cooling tower fans and motors are located below grade, and protected from tornado missiles by building walls and/or access platforms. Wet Cooling Towers The wet cooling towers consist of two separate independent multi-fan cooling units. Each wet cooling tower has two reinforced concrete chambers. The wet cooling towers utilize fill section consisting of a large number of cross fluted, vertically oriented stainless steel sheets. These sheets are attached at their sides to stainless steel frames which in turn are supported by structural steel beams. The drift eliminator for the cooling tower is located above the water distribution pipes. Drift eliminators are constructed of vertical corrugated slats of stainless steel sheets. The fan deck of the wet cooling towers is constructed of a series of stainless steel panels and is supported by structural steel beams. These beams also support the fan-motor drive assembly and the fan stacks. Galvanized steel access hatches, located in the fan deck, provide means of access to the interior of the tower.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The component cooling water system structure has the following intended functions for 10 CFR 54.4(a)(1) (a)(2) and (a)(3). *
Provide physical support, shelter and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. (1 O CFR 54.4(a)(1))
Provide a source of cooling water for safe shutdown of the plant. The structure is designed to provide a reliable source of cooling water and is the ultimate heat sink. (10 CFR 54.4(a)(1 )) -* Provide physical support, shelter, and protection for nonsafety-related systems,
structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provide physical support, shelter, and protection for safety-related systems, structures, and components and nonsafety-related systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (1 O CFR 50.48) and for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) Fuel Handling Building The purpose of the fuel handling building is to provide housing for a spent fuel storage pool, spent fuel pool pumps, spent fuel pool heat exchanger, backup fuel pool heat exchanger, spent fuel pool purification pump and heating and ventilating equipment. The handling* building is located immediately north of the reactor building. The building is a reinforced concrete structure supported on the common NPIS mat foundation. Above the common foundation mat the building is structurally separated from the reactor building at all levels. The building's exterior walls, floors, and interior partitions provide plant personnel with biological radiation shielding and protection for the surrounding equipment. The spent fuel pool, within the structure, is a stainless steel-lined reinforced concrete tank structure provides space for storage of spent fuel, spent fuel cask an*d miscellaneous items. The spent fuel cask storage area is located adjacent to (on the west side of) the spent fuel pool. Stainless steel liners are placed directly against the concrete to form the sides of the three regions (spent fuel pool, spent fuel cask storage area and refueling canal). The steel floor liner plate is supported on a steel beam grillage, which in turn is supported by* the concrete base. The entire steel grill age is grouted to the underside of the floor liner plate. *A leak detection system is provided to monitor the pool liner welds. The system consists of a network of stainless steel angles attached to the outside of the pool liner walls and floor by means of seal welds. A bridge crane for the handling of spent fuel casks and for maintenance activities runs on rails supported on a reinforced concrete frame above the operating floor. Multiple bulkhead gates accommodate fuel handling, spent fuel cask handling and provide flood protection. Additionally, the removable 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
watertight gates provide separation of the pool storage areas. The removable gates.contain inflatable elastomer seals that provide a watertight seal between the gate and the pool wall liner face. lri the fuel handling building area there is one removable flood-protected gate (Gate 3A) welded shut. This gate is located by the spent fuel cask decontamination area and is provided as a flood barrier. The refueling canal is located adjacent to (on the west side of) the spent fuel cask storage area. The refueling canal connects the reactor cavity and the spent fuel storage pool of the fuel handling building through the fuel transfer tube. The transfer tube consists of a stainless steel pipe installed inside the carbon steel penetration connecting the refuel cavity and the spent fuel pool. The inner pipe acts as the transfer tube and is fitted with a double-gasketed blind flange in the refueling cavity. Expansion bellows are provided to compensate for differential movement between the two pipes and between the outer pipe and other structures. The handling of the spent fuel in the spent fuel pool is accomplished with the spent fuel machine which runs on rails along the top of the spent fuel pool structure.' Monorail hoists and a smaller crane service the equipment and new fuel storage area. The fuel handling building has the following intended functions for 10 CFR 54.4(a)(1 ), (a)(2), and (a)(3).
Provides physical support, shelter, and protection for safety-related systems, structures, and components within the scope of license renewal. (10 CFR 54.4(a)(1))
Maintain integrity of safety and nonsafety-related components such that safety functions are not affected. by providing biological shielding *and a watertight compartment in which to carry out the refueling process. (1 O CFR 54.4(a)(2))
Provide shelter, support and protection for safety-related equipment and related equipment within the scope of license renewal. The fuel handling_ building houses equipment credited in the safe shutdown analysis for fire protection (1 O CFR 50.48). (10 CFR 54.4(a)(3)). Reactor Auxiliary Building The purpose of the reactor auxiliary building is to provide plant personnel with the necessary
biological radiation shielding, protect.the equipment inside from the effects of adverse conditions and provide protection to cable and piping penetration areas of the reactor building. The reactor auxiliary building is a seismic Category I structure located immediately south of the reactor building. The reactor auxiliary building houses the waste treatment facilities, engineered safeguards systems, switchgear, laboratories, diesel generators and main control room. The reactor auxiliary building is a multistory reinforced concrete structure with an interior floor construction of concrete beams and girders supported by reinforced concrete columns founded on the common NPIS mat foundation. Above the common mat foundation, the building is. structurally separated from the reactor building at all levels. Within the waste treatment facility is 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information a seismic Category I cask handling bridge crane, for handling miscellaneous radioactive waste. The reactor auxiliary building also houses two seismic Category I fuel oil storage tanks for supplying two diesel generators. The tanks are located in separated enclosed vaults located on opposite sides of the reactor auxiliary building. These enclosures are fire barriers consisting of concrete walls, floors, and ceilings, The condensate storage pool (CSP) and refueling water storage pool (RWSP) are also contained as an integral part of the reactor auxiliary building. The CSP and RWSP are located in the north side of the reactor auxiliary building in separate concrete vaults lined with stainless steel. The pools are vented to the atmosphere and contain vacuum and vortex breakers. The reactor auxiliary building has the following intended functions for 1 O CFR 54.4(a)(1 ), (a)(2) and (a)(3).
Provide physical support, shelter, and protection for safety-related systems, structures, and components. (1 O CFR 54.4(a)(1 ))
Provide. physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of. function(s) identified for 10 CFR 54.4(a)(1). (10 CFR 54.4(a)(2))
Provi_de shelter, support and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. The reactor auxiliary building houses equipment credited in the safe shutdown analysis, fire protection (1 O CFR 50.48), and for station blackout (1 O CFR 50.63) and environmental qualification (10 CFR 50.49). (10 CFR 54.4(a)(3)) . FSAR References Nuclear Plant Island Structure Section 2.4.1.1 Figure 3.8-1 Section 3.8.5.1 Figure 3.8-31 Figure 3.8-45 Component Cooling Water Structure Section 3.8.4.1.4 Figure 1.2-24 Section 9.2.2.2.1 Section 9.2.5.2 Fuel Handling Building Figure 1.2-25 Section 3.4.1 Figure 1.2-15 Section 3.8.3.1.3 Figure 1.2-16 Table 3.2-1 Table 3.2-1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplerrientation Results Page 2.4-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section 3.8.4.1.3 Section 9.1.2.2 Section 9.1.4.2.2.4 Reactor Auxiliary Building Section 3.8.4.1.2 Figure 3.8-42 Section 9.5.1.1.3 Section 9.5.1 Section 10.4.9 Components Subject to Aging Management Review Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. Structural commodities that are unique to the NPIS structure are included in this review. Those that are common to in-scope systems and structures (anchors, embedments, equipment supports, instrument panels, racks, cable trays, and conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. Table 2.4-2 lists the component types that require aging management review. Table 3.5.2-2 provides the results of the aging management review. -2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-16 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-2 Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function a11c! ,Other Metif!IS '. ' ' ' , .. ' *' " .<. *; '" '1'* * '" .** Control room ceiling support system Support for Criterion (a)(2) equipment Cooling tower fill/mist eliminators Heat sink Support for Criterion (a)(1) equipment Cranes: rails Support for Criterion (a)(2) equipment Cranes: structural girders Support for Criterion (a)(2) equipment Steel components: all structural steel Enclosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: fuel pool gate Flood barrier Heat sink Support for Criterion (a)(1) equipment Steel components: fuel pool liner plate Heat sink Support for Criterion (a)(1) equipment Steel components: CSP liner plate Enclosure protection Heat sink Support for Criterion (a)(1) equipment Steel components: RWSP liner plate Enclosure protection Heat sink Support for Criterion (a)(1) equipment Steel components: monorails Support for Criterion (a)(2) equipment Steel components: vortex breakers/ screens/ Enclosure protection strainers Support for Criterion (a)(1) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results *<' Page 2.4-17 Waterford Steam Electric Station, Unit 3 Renewal Application Technical Information Table 2.4-2 (Continued) Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function . ,,. * .. ' *,. Concrete ':'" J ,*' ,, " Beams, columns, floor slabs and pipe chase Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): all Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): below-grade Enclosure protection exterior; foundation Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): interior and Enclosure protection above-grade exterior Flood barrier Heat sink Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results ' *, Page 2.4-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-2 (Continued) Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function Concrete (accessible areas): NPIS exterior Enclosure protection above-and below-grade; foundation Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): all Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): exterior above-Enclosure protection and below-grade; foundation. Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Masonry walls Enclosure protection Fire barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Roof slabs Enclosure protection Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-19 2.4.3 Turbine Building and Other Structures Description The following structures are included in. this review.
Turbine Building
Other Structures Battery House, 230kV Switchyard Control House, 230kV Switchyard Fire Pump House Fire Water Storage Tank Foundations Manholes, Handholes and Duct Banks Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Transformer and Switchyard Support Structures and Foundations Turbine Building The purpose of the turbine building is to provide support and housing for the turbine-g'enerator and associated auxiliaries. The turbine building is adjacent to and south of the auxiliary building. The main generator is located on the turbine generator pedestal located at the operating floor level. The lower levels of the turbine building contain the turbine generator auxiliary equipment and the nonsafety-related medium voltage switchgear. The turbine building also houses the auxiliary medium voltage switchgear through which offsite or preferred power from the unit auxiliary or start-up transformers is distributed to the nonsafety-related loads and to the safety-related onsite power system. The turbine building houses no components identified as performing a safety function in accordance with 10 CFR 54.4(a)(1 ). To ensure that its structural integrity is maintained and that it will not affect 10 CFR 54.4(a)(1) structures, the turbine building is included in the scope of license renewal for 10 CFR 54.4(a)(2). The turbine building consists of reinforced concrete foundations, floor slabs, masonry block walls and metal siding up to the operating floor level. Above the turbine building operating floor the area is open to the atmosphere. Portions of the exterior wal.ls on the lower level consist of structural steel framing and metal siding. The lower superstructure also supports the turbine building gantry crane. Interior walls are masonry block and reinforced concrete designed to provide fire protection as. required to protect plant personnel and equipment. The turbine 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information pedestal is a reinforced concrete structure *supported on a separate foundation from the turbine building foundation mat. The turbine building has no intended function for 10 CFR 54.4(a)(1). The turbine building has the following intended function for 1 O CFR 54.4(a)(2) and (a)(3).
Maintain structural integrity of nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 10 CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 o CFR 50.63) and for fire protection (1 o CFR 50.48). (10 CFR 54.4(a)(3)) Other Structures Battery House, 230kV Switchyard The purpose of the battery house is to provide a protected area for the switchyard batteries in support of station blackout battery house, 230kV switchyard, is a nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety function. The battery house is a prefabricated metal building supported on a reinforced concrete foundation. The battery house, 230kV switchyard, has no intended functions for 10 CFR 54.4(a)(1) and (a)(2).
The battery house, 230kV switchyard, has the following intended functions for 10 CFR 54.4(a)(3). *
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for Station Blackout (1 O CFR 50.63). (10 CFR 54.4(a)(3)) . Control House, 230kV Switchyard The purpose of the control house is to provide a protected area for the relay panels which control commodities within the switchyard. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The control house, 230kV switchyard, is a nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety function. The control house is a prefabricated metal building supported on a reinforced concrete foundation. The control house, 230k\/ switchyard, has no intended functions for 10 CFR 54.4(a)(1) and (a)(2). The control house, 230kV switchyard, has the following intended functions for 10 CFR 54.4(a)(3).
Provides physical support, shelter, and protection for systems; structures, and. components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) Fire. Pump House The purpose of the fire pump house is to provide space for three horizontal centrifugal fire pumps (one motor driven and two diesel driven) and a jockey pump for fire main pressure maintenance and shelter for the security diesel. The fire pump house, located south of the demineralized water storage tank, is a * . nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety*function. The fire pump house is a prefabricated metal building with structural steel framing and built-up roofing with exterior walls consisting of galvanized steel siding. The interior walls are of concrete block construction. The entire structure is supported on a reinforced concrete foundation supported on wooden piles driven into the subgrade. Three-hour .fire barriers consisting of concrete block walls separate fire pumps, located in cubicles within the structure from each other. The pumps take their suction from two --vertical ground level water storage tanks located south. of the structure. The fire pump house has no intended functions for 10 CFR 54.4(a)(1) and (a)(2). The fire pump house has the following intended functions for 1 O CFR 54.4(a)(3).
Provides physical support shelter, and protection for systems, structures, and components re.lied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for fire protection (1 O CFR 50.48) and station blackout (1 O CFR 50.63). (1 O CFR 54.4(a)(3)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire Water Storage Tank Foundations The purpose of the fire water storage tank foundations are to provide structural support for two fire water sto.rage tanks.* The fire water storage tank foundations are individual foundations located adjacent to and south of the fire pump house and consists of a mat foundation constructed of reinforced concrete supported on concrete piles with steel pipe casings driven into the subgrade. The fire water storage tank foundations are nonsafety-related structures separated from safety-related systems, structures, and components such that its failure would not impact a safety function. 1The fire water storage tank foundations have no intended functions for 10 CFR 54.4(a)(1) *and (a)(2). The fire water storage tank foundations have the following intended functions for 10 CFR 54.4(a)(3). .*
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (10 CFR 50.48). (10 CFR 54.4(a)(3)) . Manholes, Handholes and Duct Banks The purpose of manholes, handholes and duct bank_s are to provide structural support, shelter and protection to systems, structures, and components that are relied on in safety analysis or plant evaluations to perform a function that demonstrates compliance with the Commission's regulated events and are housed within these structures during normal plant pperation, and during and following postulated design basis accidents. Manholes and handholes consist of reinforced concrete rectangular box structures buried underground with a reinforced concrete panel on top or incorporated as part of the NPIS basemat. The manholes have an 'opening and a cover to allow access. There are no Class IE manholes located on the NPIS. The remaining manholes are located in the yard and are not identified as Class IE, but support a license renewal intended function. In some instances, adjacent to each manhole is a handhole structure, which is* physically independent of the manhole structure but it does become part of the underground duct as it ties into it on both sides of the manhole structure. These hahdholes provide access to communication cables located within the duct run. Manholes, handholes and duct banks allow underground routing of cables and some piping. Redundant trains are utilized as necessary to meet site conditions. This redundancy is provided 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Subject to Aging Management Review ar;id Implementation Results Page 2.4-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information as either entirely separate trains or designed with separating, reinforced concrete walls between the trains. --Duct banks comprise multiple raceways in an excavated trench in the yard that are encased in concrete and then backfilled with soil or engineered compacted backfill. The duct banks are used to route cables between structures and switchyard areas. Duct banks that are b1:1ried shallow in the yard may be provided with a reinforced concrete protection slab that is cast over the duct bank. * -These structures have no intended function for 10 CFR 54.4(a)(1). These structures have the following intended function for 10 CFR 54.4(a)(2) and (a)(3).
Provides physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for: systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with Commissions' regulations for fire protection (10 CFR 50.48) and station blackout (10 CFR 50.63). (10 CFR 54.4(a)_(3)) Transformer and Switchyard Support Structures and Foundations The purpose of transformer and switchyard support structures and foundations is to provide structural support to systems, structures, and components that are relied on in safety analysis or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for station plackout, specifically those necessary to recqver offsite power following a station blackout. The transformer and switchyard support structures and foundations are located in the switching station and 230kV switchyard. The switching station is located.adjacent to and south of the _ turbine building. The 230kV switchyard is located an additional distance south of the turbine building. -The structures that provide physical support to the switching station and 230kV switchyard components in the* station blackout offsite power recovery path include the transformer foundations and foundations for the associated switchyard breakers, switchyard bus, switchyard towers, cable duct banks, and cable trenches. The transformer yard foundations are reinforced concrete pedestals that are supported by a reinforced qoncrete spread footing at grade or below grade. Structural steel members support the electrical components necessary for the electrical distribution system in the switchyards and are supported by the reinforced concrete pedestals. Transmission and pull-off towers are steel tower structures supported on reinforced concrete pier 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-24 Waterford Steam !=lectric Station, Unit 3 License Renewal Application Technical Information foundations. Therefore, the transformers and supporting structures are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(3). The transformer and switchyard support structures include the transformer and breaker foundations and supporting steel. The transformer and switchyard support structures and foundations have no intended functions for (10, CFR 54.4(a)(1) or (a)(2). The transformer and switchyard support structures and foundations have the following intended function for 1 O CFR 54.4(a)(3).
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) FSAR References Turbine Building None Other Structures Battery House, Control House, Manholes and Duct Banks None Fire Pump House Section 9.5.1.2.2 Section 9.5.1.3 Transformer and Switchyard Support Structures and Foundations Section 1.2.2.4 . Figure 8.1-4 Section 8.2 (system function) Section 8.2.1 Section 8.2.1.3 Figure 8.1-5 Components Subject to Aging Management Review Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. Structural commodities that are unique to. the turbine building and other structures are included in this review. Those that are common to in-scope systems and structures (anchors, embedments, equipment supports, instrument panels, racks, cable trays, and conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-25 Waterford Steam Electric Station,. Unit 3 License Renewal Application Technical Information Table 2.4-3 lists the component types that require aging management review. Table 3.5.2-3 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-26 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Table 2.4-3 Turbine Building and Other Structures Components Subject to Aging Management Review Intended Function . */ .. . . . . ... .. . . . '"*;"' Steel and Other Metals.*. " ' . ' ' . .,A,<, ... . . .. ,',, .. . ' **"* . ... , . Cranes: rails and structural girders Support for Criterion (a)(2) equipment Steel components: all structural steel Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: metal siding Enclosure protection Support for Criterion (a)(2) equipment Steel components: roof decking or floor Enclosure protection decking Fire barrier Steel piles Support for Criterion (a)(3) equipment Transmission tower, angle tower, pull-off Support for Criterion (a)(3) equipment tower ' .. ... ' ' '* *<< *'* ** ... ..**:, .:; > ,* ! :: Concrete .. .. .. , . ': . ' ," ,,_,,.,, " . ' . *:* ,, .. '; .. . : ;.*r ** .. *.:: '.: *:' :. .. '. Beams, columns and floor slabs Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): all Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): below-grade Enclosure protection exterior; foundation Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): interior and Enclosure protection above-grade exterior Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): exterior above-Enclosure protection and below-grade; foundation Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): all Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results <;/ ,., . . ; *-,.> '* . . Page 2.4-27 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-3 (Continued) Turbine Building and Other Structures Components Subject to Aging Management Review _Component Concrete (inaccessible areas): exterior above-and below-grade; foundation Duct banks Foundations (e.g., switchyard, transformers, tanks, circuit breakers) Manholes and handholes Masonry walls Wooden piles. Intended Function Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure Protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enelosure protection Fire barrier _Flood barrier Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Fire barrier
Support for Criterion (a)(2) equipment Support for (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-28 2.4.4 Bulk Commodities Description Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information Bulk commodities subject to aging management review are structural components or commodities that perform or support intended functions of in-scope systems, structures and components (SSCs). Bulk commodities unique to a specific structure are included in the review for that structure (Sections 2.4.1, 2.4.2, and 2.4.3). Bulk commodities common to in-scope SSCs (e.g., concrete embedments and anchors, bolted connections/bolting, component supports, cable trays, compressible joints and seals, conduit, decking, doors [including air locks and bulkhead doors], electrical panels and enclosures, hatches/plugs, instrument panels and racks, miscellaneous steel, racks, piping and equipment supports, tube track supports) are addressed in this review. Bulk commodities evaluated in this section are designed to support both safety-related and nonsafety-related equipment during normal and accident conditions in the event of external events '(tornadoes, earthquakes, floods, missiles) and internal events (LOCA, pipe breaks). Bulk commodities are structural components that support the various intended functions performed by the structures in which they are located. These functions for 10 CFR 54.4(a)(1), (a)(2), and (a)(3) include the following.
Provide support, shelter and protection for safety-related equipment and related equipment within the scope of license renewal. 1 O CFR 54.4(a)(1)
Maintain integrity of nonsafety-related structural components such that safety functions are not affected. 1 O CFR 54.4(a)(2)
Provide support and protection for equipment credited in the Appendix R safe shutdown analysis and for fire protection (1 O CFR 50.48), for environmental qualification (10 CFR 50.49), for anticipated transients without scram (10 CFR 50.62), and for station blackout (10 CFR 50.63). 10 CFR 54.4(a)(3) Insulation may have the specific intended functions of (1) maintaining local area temperatures within design limits or (2) maintaining integrity such that falling insulation does not damage safety-related equipment. FSAR References None 2.0 Scoping and Screening Methodology for Identifying Structures and Components . Page 2.4-29 Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Bulk commodities subject to aging management review are structural components or commodities that perform or support intended functions of in-scope SSCs. Bulk commodities unique to a specific structure are addressed in the aging management review for that structure. Bulk commodities common to in-scope SSCs (anchors, embedments, pipe and equipment supports, instrument panels and racks, cable trays, conduits, etc.), as well as seismic II/I supports, are ir:icluded in this evaluation. Insulation is subject. to aging management review if it performs an intended function as described above. . . Table 2.4-4 lists the component types that require aging management review. Table 3.5.2-4 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging M*anagement Review and Implementation Results Page 2.4-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 Bulk Commodities Components Subject to Aging Management Review Component Anchorage/embedments Cable tray Conduit Constant and variable load spring hangers;* guides; stops (Supports for ASME Class 1, 2 and 3 piping and components) Doors Fire doors Fire hose reels Fire protection components: miscellaneous steel, including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Manways, hatches, manhole covers and hatch covers Mirror insulation Missile shields Intended Function Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Enclosure protection Flood barrier Missile barrier Pressure boundary Fire barrier Support for Criterion (a)(3) equipment Support for Criterion (a)(3) equipment Fire barrier Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Flood barrier Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support. for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(2) equipment Enclosure protection Missile barrier 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 (Continued) Bulk Commodities Components Subject to Aging Management Review Component Miscellaneous steel (decking, grating, handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc.) Penetration seals (end caps) Penetration sleeves (mechanical/electrical not penetrating PC boundary) Racks, panels, cabinets and enclosures for electrical equipment and instrumentation Tube track Supports for ASME Class 1, 2, 3 piping and components (constant and variable load spring hangers; guides; stops) Support members; welds; bolted connections; support anchorage to building structure Anchor bolts Intended Function Enclosure protection Flood barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Enclosure protection Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Enclosure protection Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Endosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)°(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-32 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 (Continued) Bulk Commodities ComponentS Subject to Aging Management Review Component High-strength structural bolting (supports for ASME Class 1, 2, and 3 piping and components Structural bolting; structural steel and miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc.) Structural bolting Building concrete at locations of expansion and grouted anchors; grout pads for support base plates Equipment pads/foundations Curbs . Manways, hatches/plugs, manhole covers and hatch covers Missile shields Structural fire barriers, walls, ceilings, floor slabs, curbs, dikes Support pedestals Intended Function Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Flood barrier Support for Criterion (a)(2) equipmenf Support for Criterion (a)(3) equipmen_t Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Missile barrier Fire barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table-2.4-4 (Continued) Bulk Commodities Components Subject to Aging Review Compressible joints and seals Fire stops Fire wrap Insulation (includes jacketing, wire mesh, tie wires, straps, dips) Penetration seals . Roof membranes Seals and gaskets (doors, manways and hatches) Vibration isolators Support for Criterion (a)(1) equipment .support for Criterion (a)(2) equipment Fire barrier Fire barrier *Insulation Support for Criterion (a)(2) equipment Enclosure protection Fire barrier
Flood barrier Pressure boundary Support for Criterion (a)(2) equipment Enclosure protection Support for Criterion (a)(2) equipment Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-34 \

( Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS Description As stated in Section 2.1.1, plant electrical and instrumentation and control (l&C) systems are included in the scope of license renewal as are electrical and l&C components in mechanical systems. The default inclusion of plant electrical and l&C systems in the scope of license renewal is the bounding approach used for the scoping of electrical systems. The basic philosophy used in the electrical and l&C -components IPA is that components are included in the review unless specifically screened out. When used with the plant spaces approach, this method eliminates the need for unique identification of individual components and specific component locations. This assures components are not improperly excluded from an aging management review. The electrical and l&C IPA began by grouping the total population of com*ponents info commodity groups. The commodity groups include similar electrical and l&C*components with common characteristics. Component level intended functions of the commodity groups were identified. During the IPA screening process, commodity groups and specific plant systems were eliminate.d from further review if they did not perform or su.pport an intended function. *

In addition to the plant electrical systems, certain switchyard components used to restore offsite power following a station blackout (SBO) were conservatively included within the scope of license renewal even though those components are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). The April 1, 2002, SBO guidance letter 1 and NUREG-1800 Section 2.5.2.1.1 provide scoping guidance to include equipment needed.for site power recovery, which includes equipment not explicitly required for compliance with 10 CFR 50.63.* LRA Drawing LRA-G285 depicts the electrical interconnection between Waterford 3 and the offsite transmission network. LRA Drawing LRA-G285 identifies* major components or commodities associated with off-site power recovery following SBO. The highlighted portions depict the components in the SBO recovery path that are subject to aging management review. Components in the off-site power circuits that are not highlighted have no intended function for license renewal and thus a.re not subject to aging management review. 1. NRG.to NEI, "Staff Guidance on Scoping of Equipment Relied on to Meet the Requirements of the Station Blackout (SBO) Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3))," letter dated April 1, 2002 (ISG-02). ADAMS accession number ML020920464. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-1 FSAR References Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for electrical systems and commodities can be found in FSAR Chapters 7 and 8. Scoping Boundaries Plant electrical and l&C systems are included in the scope of license renewal as are electrical and l&C components in mechanical systems. Waterford 3 preferred (offsite) power is from the 230 kV switchyard via two physically and independent circuits via overhead transmission lines to the switching station and then to the startup transformers. The .startup transformers supply power to the nonsafety-related buses (3A2 and 382). The nonsafety-related buses (3A2 and 382) supply power to the related buses (3A3-S and 383-S). The ESF buses 3A3-S and 383-S may also receive power from the two diesel generators, should the preferred power from buses 3A2 or 382 be unavailable. All safety-related loads receive power from these two buses. Waterford 3 takes no credit for backfeed through the main transformers as an offsite .power source. . The offsite power source required to support SBO recovery. actions is the source from the 230 kV switchyard supplying the startup transformers. The path for offsite power recovery includes two 230 kV switchyard circuit breakers feeding each startup transformer, the circu_it transformer and ttansformer-to:onsite electrical distribution)nterconnections, and the associated control circuits and structures. Steel transmission towers and foundations, structures housing switchyard batteries, and structures supporting breakers, disconnects, transformers, transmission conductors, and switchyard bus utilized in the 230-kV off-site power recovery paths are evaluated in Section 2.4, Scoping and Screening Results: Structures. Commodity Groups Subject to AMR As discussed in Section 2.1.2.3.1, Waterford 3 passive electrical commodity groups corresponµ to two of the passive commodity groups identified in NEI 95-1 O:
High voltage insulators. ,
Cables and connections, bus, electrical portions of electrical and l&C penetration assemblies, fuse holders outside of cabinets of active electrical components. The commodity group cables, connections, bus, electrical portions of electrical and l&C penetration assemblies, and fuse holders outside of cabinets of active electrical components is further subdivided into the following. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Cable connections (metallic parts).
Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements.
Electrical cables and connections subject to 10 CFR 50.49 EQ requirements.2
Electrical cables and connections not subject to 1 O CFR 50.49 EQ requirements used in instrumentation circuits.
Electrical and l&C penetration cables and connections not subject to 10 CFR 50.49 EQ requirements. 3 *
Fuse holders -insulation material.
Fuse holders -metallic clamp.4
Inaccessible power(?_ 400 V) cables (e.g., installed underground In conduit, duct bank or direct buried) not subject to 10 CFR 50.49 EQ requirements.
Metal enclosed bus -bus I connections.
Metal enclosed bus -enclosures assemblies (elastomers, external surfaces).
enclosed bus -insulation I insulators.
Switchyard bus and connections.
Transmission conductors and connections.
Uninsulated ground conductors.5 Commodity Groups Not Subject to AMR Electrical and l&C Penetration Assemblies All Waterford 3 electrical and l&C penetration assemblies are in the EQ program (1 O CFR 50.49). Waterford 3 electrical and l&C penetration assemblies in the EQ program are subject to replacement based on their qualified life, so they are not subject to aging management review. Non-EQ cables and connections to electrical and l&C penetrations are evaluated in the insulated cable and connection commodity group. Fuse Holders -Metallic Clamp A review of Waterford 3 documents (e.g., drawings, procedures, FSAR, Waterford 3 Equipment Database (Asset Suite) functional location list, and electrical design basis documents) identified fuse holders. No circuits with an LR intended function with fuse holders were identified needing 2. Waterford 3 electrical cables and connections subject to 10 CFR 50.49 EQ requirements are not subject to aging management review (STAMR) since the components are subject to replacement based on qualified life.
3. All Waterford 3 electrical and l&C penetration assemblies are in the EQ Program (10 CFR 50.49). Waterford 3 EiC penetration assemblies in the EQ Program are not STAMR since the components are subject to replacement based on qualified life. 4. Waterford 3 fuse holders (metallic clamp) are part of an active component and are.not STAMR. 5. Waterford 3 uninsulated ground conductors limit equipment damage in the event of a circuit failure, but do not perform a license renewal intended function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information further evaluation. From reviewing the fuses and associated drawings, a determination was made that each fuse holder was part of an active component.. Uninsulated Ground Conductors A review of the Waterford 3 FSAR did not identify a license renewal intended function for uninsulated ground conductors. These components are not safety-related and are not credited for mitigation of regulated events .. Industry and plant-specific operating experience for uninsulated ground conductors does not indicate credible failure modes that would adversely affect an intended function; therefore, credible uninsulated ground conductor failures that could prevent satisfactory accomplishment of safety functions are hypothetical. As di.scussed in Section 2.1.3.1.2 of NUREG-1800 and Section 111.c(iii) of the Statements of Consideration (60FR22467), hypothetical failures that are not part of the current licensing basis and have not been previously experienced are not required to be considered for license renewal scoping. Table 2.5-1 lists the component types that require aging management review. Table 3.6.2-1 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.5-1 Electrical and Instrumentation and Control Systems Components Subject to Aging Management Review Structure and/or Component/Commodity Intended Function Cable connections (metallic parts) Conducts electricity Insulation material for electrical cables and connections Insulation. (electrical) (including terminal blocks, fuse holders, etc.) not subject to 10 CFR 50.49 EQ requirements Insulation material for electrical cables not subject to 10 CFR Insulation (electrical) 50.49 EQ requirements used in instrumentation circuits Fuse holders (not part of active equipment): insulation material Insulation (electrical) Fuse holders (not part of active equipment): metallic clamps Conducts electricity High voltage insulators (for SBO recovery) Insulation (electrical) Conductor insulation for inaccessible power cables (:::_ 400 V) Insulation (electrical) not subject to 10 CFR 50.49 EQ requirements Metal enclosed bus: bus/connections Conducts electricity Metal enclosed bus: enclosure assemblies Conducts electricity Metal enclosed bus: insulation/insulators Insulation (electrical) Switchyard bus and connections (for SBO recovery) Conducts electricity Transmission conductors and connectors (for SBO recovery) Conducts electricity Connector contacts for electrical connectors exposed to borated Conducts electricity water leakage 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.0 AGING MANAGEMENT REVIEW RESULTS This section provides the results of the aging management review (AMR) for structures and components identified in Section 2 as subject to aging management review. Tables 3.0-1, 3.0-2, and 3.0-3 provide descriptions of the mechanical, structural, and electrical service environments, respectively, used in the AM Rs to determine aging effects requiring management. Results of the AM Rs are presented in the following two table types.
Table 3.x.1 where 3 indicates the table pertaining to a Section 3 aging management review. x indicates the table number from NUREG-1800 (Ref. 3.0-1). 1 indicates that this is the first table type in Section 3.x. For example, in the reactor coolant system section, this is Table 3.1.1, and in the engineered safety features section, this is Table 3.2.1. For ease of discussion, these table types will hereafter be referred to as "Table 1." These tables are derived from the corresponding tables in NUREG-1800 and present summary information from the AM Rs.
Table 3.x.2-y where 3 indicates the application section number. x indicates the table number from NUREG-1800. 2 indicates that this is the second table type in Section 3.x. y indicates the system table number. For example, within the reactor coolant system section, the AMR results for the reactor vessel are presented in Table 3.1.2-1, and the results for the reactor vessel internals are in Table 3.1.2-2. In the engineered safety features section, the containment spray system results are presented in Table 3.2.2-1, and the safety injection system is in Table 3.2.2-2. For ease of discussion, these table types will hereafter be referred to as "Table 2." These tables present the results of the AM Rs. 3.0 Aging Management Review Results Page 3.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information TABLE DESCRIPTION Table 1 The purpose of a Table 1 is to provide a summary comparison of how the WF3 AMR results align with the corresponding table of NUREG-1800. These tables are essentially the same as Tables 3.1-1 through 3.6-1 provided in NUREG-1800 as amended by applicable Interim Staff Guidance documents, with the following exceptions.
The "ID" (identification) column is labeled "Item Number and the number has been expanded to include the table number.
The "Type" column has been deleted. Items applicable to BWRs only are noted as such.
The "Rev 2 Item" and "Rev 1 Item" columns have been replaced by a "Discussion" column. The "Item Number" column provides a means to cross-reference to Table 1 from the Table 2s. Information in the following columns of Table 1 is taken directly from NUREG-1800.
Component
Aging Effect/Mechanism
Aging Management Programs
Further Evaluation Recommended Further information is provided in the "Discussion" column. The Discussion column explains, in summary, how the WF3 evaluations align with NUREG-1800 and NUREG-1801 (Ref. 3.0-2). The following are examples of information that might be contained within this column:
Any "Further Evaluation Recommended" information or reference to the location of that information.
The name of a plant-specific program being used.
Exceptions to the NUREG-1800 and NUREG-1801 assumptions.
A discussion of how the line item is consistent with the corresponding line item in NUREG-1800, when it may not be intuitively obvious.
A discussion of how the line item is different from the corresponding line item in NUREG-1800, when it may appear to be consistent. 3.0 Aging Management Review Results Page 3.0-2 Table 2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2s provide the results of the aging management reviews for those structures and components identified in Section 2 as being subject to aging management review. There is a Table 2 for each aging management review within a system group. For example, the engineered safety features system group contains tables specific to the containment spray system, safety
injection system, and containment penetrations. Table 2s also provide a comparison of the AMR results with the AMR results in NUREG-1801. Comparison to NUREG-1801 is performed by considering the component type, material, environment, aging effect requiring management, and aging management program (AMP) listed in each Table 2 line item to determine the degree of consistency with an appropriate NUREG-1801 line item, if one exists. The comparison is documented in columns 7, 8, and 9, as discussed below. Each Table 2 consists of the following nine columns. Component Type Column 1 identifies the component types from Section 2 of this application that are subject to aging management review, with the addition of insulated piping components. The term "piping" in component lists includes pipe and pipe fittings (such as elbows, flued heads, reducers, tees, etc.). The term "Insulated piping components" may include insulated indoor tanks with capacity less than or equal to 100,000 gallons. Intended Function Column 2 identifies the license renewal intended functions (using abbreviations* where necessary) for the listed component types. Definitions and abbreviations of intended functions are listed in Table in Section 2. Material Column 3 lists the particular materials of construction for the component type being evaluated. Environment Column 4 lists the environment to which the component types are exposed. Internal and external service environments are indicated using (int) or (ext), respectively. A description of these environments is provided in Tables 3.0-1, 3.0-2, and 3.0-3 for mechanical, structural, and electrical components, respectively. 3.0 Aging Management Review Results Page 3.0-3 Aging Effect Requiring Management Wate,rford Steam Electric Station, Unit 3 License Renewal Application Technical Information Column 5 lists the aging effeGts requiring management for material and environment combinations for each component type. Aging Management Programs (AMP) Column 6 lists the programs used to manage the aging effects requiring management. NUREG-1801 Item Each combination of the following faCtors listed in.Table 2 is compared to NUREG-1801 to identify consistencies.
Component type
Material
Environment
Aging effect requiring management
Aging management program Column 7 documents identified consistencies by noting the NUREG-1801 item number. If there is no corresponding item number in NUREG-1801 for a particular combination of factors, column 7 is left blank. . '. Comparisons of system and structure aging result!:! to NUREG-1801 items are generally within the corresponding system group and preferably within the specific system or structure. For* example, aging management results for the safety injection system will generally .
be compared to NUREG-1801 ESF system results iri Chapter V, and preferably to items in . Table V.01 for the 'emergency core cooling systems for PWRs. In _some cases where a particular aging management review result has _no valid comparison _within the system group, a comparison is outside the system group. For example, a material, environment, aging effect, and
program combint;iti_on in the safety injection system aging management result!; may have no comparable item in the ESF system results, but a match can be found in the auxiliary systems tables .. fable 1 Jtem Column 8 lists the corresponding line item from Table 1. If there is no corresponding item in NUREG-1800, then column 8 is left blank. Each combination of the following that ht;is an identified NUREG-1801 item number also has a Table 1 line item reference number.
Component type
Material 3.0 Aging Management Review Results Page 3.0-4
Environment *
Aging effect requiring management
Aging management program Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Column 9 contains notes that are used to describe the degree of consistency with the line items in NUREG-1801. Notes that use letter designations are standard notes based on Table 4.2-2 of NEI 95-10 (Ref. 3.0-3). Notes that use numeric designators are specific to the plant site. Some of the NUREG-1801 evaluations refer to plant-specific programs. In these cases, Note E is used for correlations between the combination in Table 2 ahd a combination for a line item in NUREG-1801. FURTHER EVALUATION REQUIRED The Table 1s in NUREG-1800 indicate that further evaluation is necessary for certain aging effects and other issues discussed in NUREG-1800. Section 3 includes discussions Of these issues numbered in accordance with the discussions in NUREG-1800. The discussions explain ) the site's approach to these areas requiring further evaluation. 3.0 Aging Management Review Results Page 3.0-5 REFERENCES Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.0-1 NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U. S. Nuclear Regulatory Commission, December 2010. 3.0-2 NUREG-1801, Generic Aging. Lessons Learned (GALL) Report, Revision 2, U. S. Nuclear Regulatory Commission, December 2010. 3.0-3 NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54 -The License Renewal Rule, Nuclear Energy Institute (NEI), Revision 6, June 2005. 3.0 Aging Management Review Results Page 3.0-6 Table 3.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor Air in an environment protected from ... Air -indoor uncontrolled precipitation. .. Air -indoor uncontrolled > 35°C (> 95°F) Air with borated water leakage Air with metal temperature up to 2aa0c (550°F) Air with reactor coolant leakage Air with steam or water leakage '-, System temperature up to 340°C (644 °F) Air .:... outdoor The outdoor environment consists of atmqspheric Air -outdoor. air, ambient temperature and humidity, and exposure to precipitation. Concrete Components in contact with concrete. Concrete. Condensation Air and condensation on surfaces bf indoor Condensation systems with temperatures below dew point; condensation is considered untreated water due to potential for surface contamination. For compressed air systems with dryers, condensation may be conservatively identified as the internal environment. Exhaust gas Gases, fluids, particulates present in diesel Diesel* exhaust engine exhaust. Fuel oil. Diesel oil, No. 2 oil, or other liquid hydrocarbons Fuel oil used to fuel diesel engines, boilers; etc. Gas Internal dry non-corrosive gas environments such Gas as nitrogen, carbon dioxide, Freon, and Halon. Lube oil Lubricating oils are low-to medium-viscosity Lubricating oil hydrocarbons used for bearing, gear, and engine lubrication. An oil analysis program may be credited to preclude water contamination. 3.0 Aging Management Review Results Page 3.0-7 Table 3.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1S01 Environment . Description Environments Neutron fluence Neutron flux integrated time. Neutron Neutron flux fluence is specified as an environment for the High fluence (> 1 *x 1021 n/cm2, limiting reactor vessel components with material E > 0.1 million electron volts properties that may be significantly affected by [MeV]) neutron irradiation. Raw water Consists of untreated surface or ground water, Raw water whether fresh, brackish, or saline in nature, or water not treated by a chemistry program such as water supplied from an off-site source for fire protection. Soil External environment for components buried .in Soil the soil; exposure to ground water is assumed in soil environments Steam Steam, subject to a water chemistry program. In Steam determining aging effects, steam is Reactor coolant treated water. Treated borated Treated 6r demineralized borated water. Treated borated water water Reactor coolant Treated borated Treated or demineralized borated water above Treated borated water > 60°C water> 140°F stress corrosion cracking (SCC) threshold for (> 140°F) ,* stainless steel. . Reactor coolant > 60°C (> 140°F) Treated borated Treated or demineralized borated water above Treated borated water > 250°C water> 482°F thermal embrittlement thi"e$hold for cast . (> 482°F). austenitic stainless steel (CASS). Reactor coolant > 250°C (> 482°F) Treated water Treated water is demineralized water and is the Treated water base water for all* clean systems.1 . Closed-cycle cooling water Secondary feedwater Raw water (potable) Treated water Treated water above the SCC threshold for Treated.water> 60°C (> 140°F) > 14Q°F stainless steel Closed-cycle cooling water > 60°C (> 140°F) 3.0 Aging Management Review Results Page 3.0-8 Table 3.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environment$ Waste water Water in liquid waste drains such as in liquid Waste water radioactive waste systems, oily waste systems, floor drainage systems, chemical waste water systems, and secondary waste water systems. Waste waters may contain contaminants, including oil and boric acid, as well as treated water not monitored by a chemistry program. 1. For the aging management review process, and the Table 2 presentation of review results, "treated water" encompasses a range of water types, all of which were chemically treated or demineralized. These. water types include treated water, reactor coolant, raw (potabie) water, and closed cycle cooling water as defined in NUREG-1801. In the Table 2 results, tile type of water can normally be inferred from the context of the result (e.g., if Water Chemistry Control -Closed Treated Water Systems [Section B.1.40] is the aging management program, then tile treated water is equivalent to closed cycle cooling water as defined by NUREG-1801), Where such an inference is not clear, a plant-specific note identifies the water type. . . . . For the comparison of the aging management review results with those of NUREG-1801, as presented in the last three Table 2 columns, and for the summary of results discu.ssed in Table 1, the NUREG-1801 definitions of water types were used. In other words, the "treated water" listed in the results was compared to the corresponding water type of NUREG-1801. The discussions in Table 1, and in the text sections *
referenced in Table 1 for further evaluatio!1, use the water types defined by NUREG-1801. In these discussions, "treated water refers only to water controlled by the Water Chemistry Control -Primary and Secondary Program (Section B.1.41). " *'
3.0 Aging Management Review Result$ Page 3.0-9 Table 3.0-2 Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Service Environments for Structural Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor Air with temperature less than 150°F, humidity up Air -indoor uncontrolled uncontrolled to 100 percent and protected from precipitation. The Air -indoor uncontrolled (External) environment is for indoor locations that are sheltered or protected from weather. Humidity levels up to 100 percent are assumed and the surfaces of components in this environment may be wet. This environment may contain aggressive chemical species including oxygen, halides, sulfates, or other aggressive corrosive substances that can influence the nature, rate, and severity of corrosion effects. It is assumed that these contaminants can concentrate to levels that will promote corrosive effects because of factors such as cyclic (wet-dry) condensation, contaminated insulation, accidental contamination, or leakage areas. Air -outdoor Exposed to the weather with air temperature less Air -outdoor than 115°F, humidity up to 100 percent. This . environment is subject to periodic wetting and wind. This environment may contain aggressive chemical species including chlorides, oxygen, halides, sulfates, or other aggressive corrosive substances that can influence the nature, rate, and severity of corrosion effects. Concrete This environment consists of components Concrete embedded in concrete. 3.0 Aging Management Review Results Page 3.0-10 Table 3.0-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Structural Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Exposed to fluid Fluid environment for structures at WF3 is Ground water environment defined as raw water or treated water. Treate_d "Yater
Raw water -Water from the Mississippi River Treated water> 140°F provides the source of raw water utilized at WF3. Water -flowing Raw water is also rain or ground water.* Raw water is water that has not been demineralized or Water -standing chemically treated to any significant extent. Raw water may contain contaminants. WF3 building sumps may be exposed to a variety of untreated water that is classified as raw water for the determination of aging effects. ..
Treated water -Treated water is demineralized water .or chemically purified water and is ttie base water for clean systems. Treated water could be deaerated and include corrosion inhibitors, biocides, or some combination of these treatments.
Soil External environment for co_mponents at the air/ Soil soil interface, buried in the soil, or exposed to groundwater in the soil. This environment can be "aggressive" or "non-aggressive" depending on its soil properties as defined in NUREG-1801. 3.0 Aging Management Review Results Page 3.0-11 Table 3.0-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Electrical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor This environment is one to which the specified Air -indoor controlled controlled internal or external surface of the component or structure is exposed; a humidity-controlled (i.e., air conditioned) environment_. For electrical purposes, control must be sufficient to eliminate the 'cited aging effects of contamination and oxidation without affecting the resistance. Air-indoor Uncontrolled indoor air is associated with Air -indoor uncontrolled uncontrolled systems with temperatures higher.than the dew point (i.e., condensation can occur, but only rarely; equipment surfaces are normally dry). Air -outdoor The outdoor environment consists of moist, Air -outdoor possibly salt-laden atmospheric air, ambient temperatures and humidity, and exposure to weather, including precipitation.and wind. The component is exposed to air and local weather conditions, including salt water spray (if present). . . A component is considered susceptible to a wetted environment when it is submerged, has the potential to collect water, or is subject to external condensation. Air with borated Air and untreated borated water leakage on Air with borated water leakage water leakage indoor or outdoor systems with temperatures either above or below the dew point. The water from leakage is considered to be untreated, due to the potential for water contamination at the surface (germane to PWRs). Heat, moisture, Condition in a limited plant area that is Adverse localized environment or radiation and significantly more severe than the plant design caused by heat, radiation or air environment for the cable or connection moisture insulation materials caused by heat, radiation, or *moisture, and air. 3.0 Aging Management Review Results Page 3.0-12 Table 3.0-3 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Electrical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Significant Condition in a limited plant area that is Adverse localized environment moisture significantly more severe than the plant design caused by significant moisture environment for the cable or connection insulation materials caused by significant moisture (moisture that lasts more than a few days-e.g., cable in standing water) 3.0 Aging Management Review Results Page 3.0-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1 REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM 3.1.1 Introduction This section provides the results of the aging management reviews for components in the reactor vessel, internals and reactor coolant system that are subject to aging management review. The following component groups are addressed in this section (component group descriptions are available in the referenced sections). * -* * *
Reactor Vessel (Section 2.3.1.1)
Reactor Vessel Internals (Sedtion 2.3.1.2)
Reactor Coolant Pressure Boundary (Section 2.3.1.3)
Steam *Generators (Section 2.3.1.4)
RCS systems in scope for 1 O CFR 54.4(a)(2) (Section 2.3.1.5) Table 3.1.1, Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801, provides the summary .of the programs evaluated in NUREG-1801 for the reactor co_olant system (RCS) component groups. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.1.2 Results The following tables summarize the results of aging management reviews and the NUREG-1801 comparison for the reactor vessel, internals and reactor coolant system components ..
Table 3.1.2-1 Reactor Vessel_;_Summary of Aging Management Evaluation
Table 3.1.2-2 Reactor Vessel Internals-Summary of Aging Management Evaluation
Table 3.1.2-3 Reactor Coolant Pressure Boundary-Summary of Aging Management Evaluation
Table 3.1.2-4 Steam Generators-Summary of Aging Management Evaluation RCS Systems in Scope for 10 CFR 54.4(a)(2) . ,
Table 3.1.2-5-1 Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Review
Table 3.1.2-5-2 Steam Generators, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Review 3.0 Aging Management Review Results Page 3.1-1.

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the reactor vessel, internals and reactor coolant system components. Programs are described in Appendix B. Further details are provided in Tables 3.1.2-1 through 3.1.2-5-2. 3.1.2.1.1 Reactor Vessel Materials Reactor vessel components are constructed of the following materials. Carbon steel Carbon steel clad with stainless steel High strength steel Low alloy steel

Nickel alloy Stainless steel Environments Reactor vessel components are exposed to the following environments. Air-indoor Neutron fluence Treated borated water Treated borated water > 140°F Aging Effects Requiring Management The following aging effects associated with the reactor vessel require management. Cracking Cracking -fatigue Loss of material Loss of material -wear Loss of preload Reduction of fracture toughness 3.0 Aging Management Review Results Page 3.1-2 Aging Management Programs Waterford Steam Electric Station, Unit 3 L_icense Renewal Application Technical Information The following aging management programs manage the aging effects for t_he reactor vessel components. Bolt\ng Integrity Boric Acid Corrosion lnservice Inspection Reactor Head Closure Studs Reactor Vessel Surveillance Water Chemistry Control -Primary and Secondary 3.1.2.1.2 Reactor-Vessel Internals Materials Reactor vessel internals components are constructed of the following materials. CASS Nickel alloy Stainless steel Zircaloy Environments .. Reactor vessel internals components are exposed to the following environments. Neutron fluence Treated borated water Treated borated water> 140°F Treated borated water> 482°F Aging Effects Requiring Management The following aging effects-associated with the reactor vessel internals require management. Change. in dimension*s Cracking Cracking -fatigue Loss of material Loss of material -wear Loss of preload Reduction of fracture toughness 3.0 Aging Management Review Results Page 3.1-3 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the reactor vessel internals components. Reactor Vessel Internals Water Chemistry Control -Primary and Secondary 3.1.2.1.3 Reactor Coolant Pressure Boundary Materials Reactor coolant pressure boundary components are constructed of the following materials. *
Carbon steel Carbon steel clad with nickel alloy Carbon steel clad with stainless steel CASS Copper alloy Copper alloy > 15% zinc or > 8% aluminum. High strength steel Nickel alloy Stainless steel Environments coolant pressure boundary components are exposed to the following environments. Air-indoor Lube oil Steam Treated borated water Treated borated water> 140°F Treated borated water> 482°F
Treated water Aging Effects Requiring Management The following aging effects associated with the reactor coolant pressure boundary require management. Cracking Cracking -fatigue 3.0 Aging .Management Review Results Page 3.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Loss of material Loss of preload *
Reduction of fracture toughness Aging Management Programs The following aging management programs manage the aging effects for the reactor coolant pressure boupdary components. Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring lnservice Inspection Nickel Alloy Inspection Oil Analysis One-Time Inspection One-Time Inspection -Small-Bore Piping
Selective Leaching
Thermal Aging Embrittlement of CASS Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.1.2.1.4 Steam Generators Materials Steam generator components are constructed of the following materials. Carbon steel Carbon steel clad with nickel alloy Carbon steel clad with stainless steel Nickel alloy Stainless steel Environments Steam generator components are exposed to the following environments. Air-indoor Treated borated water Treated borated water> 140°F Treated water Treated water> 140°F 3.0 Aging Management Review Results Page 3.1-5 Aging Effects Requiring Management Waterford Steam Electric Station, Unit 3 License Renewal Application Information The following aging effects associated with the steam generators require management. Cracking Cracking -fatigue Loss of material Loss of material -erosion Loss of material -FAC Loss of material -wear Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the steam generator components. Bolting Integrity Boric Acid Corrosion Flow-Accelerated Corrosion lnservice Inspection One-Time Inspection Stea.m Generator Integrity Water Chemistry Control -Primary and Secondary 3.1.2.1.5 RCS Components in Scope for 1 O CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.1.2-5-x tables. Materials Nonsafety-related components affecting safety-related systems are constructed of the following materials. *Aluminum Carbon steel Glass Stainless steel 3.0 Aging Management Review Results Page 3.1-6 Waterford Steam. Eledric station, Unit 3 License Renewal Application Technical Information Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments. Air-indoor Lube oil
Treated borated water Treated borated water> 140°F Wastewater Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. Cracking Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for related components affecting safety-related systems. *
Bolting Integrity . Boric Acid Corrosion
External Surfaces Monitoring _ . Internal Surfaces in Miscellaneous Piping and Ducting Components Oil Analysis
One-Time Inspection Periodic Surveillance and Preventive Maintenance Water Chemistry Control -Primary and Secondary 3.1.2.2 Further.Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.1.2.2 of NUREG-1800. The following sections are numbered in accordancewith the discussions in NUREG-1800 and explain the WF3 approach to these areas requiring further evaluation. Programs are described in Appendix B. 3.1.2.2.1 Cumulative Fatigue Damage. Fatigue is considered a time-limited aging analysis (TLAA) as defined in 10 CFR 54.3 for the reactor vessel, selected components of the reactor vessel internals and most 3.0 Aging Management Review Results Page 3.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information components of the reactor coolant pressure boundary including the reactor coolant pumps, pressurizer and steam generators. TLAAs are evaluated in accordance with 10 CFR 54.21 (c). The evaluation of fatigue. for the reactor vessel is discussed in Section 4.3.1.1. The evaluation of fatigue TLAAs for the ASME Class 1 portions of the reactor coolant
pressure boundary piping and components, including those for interconnecting systems, is discussed in Sections 4.3.1.3 through 4.3.1.7. 3.1.2.2.2 Loss of Material Due to General. Pitting. and Crevice Corrosion 1. Loss of material due to general, pitting, and crevice corrosion for the steel steam generator upper and lower shell and transition cone exposed to secondary feedwater and steam is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The steam generators have been replaced with Westinghouse Model Delta-110 generators. The replacement steam generators do not have the high-stress region at the shell to transition cone weld found in Model 44 and 51 generators. 2. This paragraph in NUREG-1800 pertains to plants where partial steam generator replacements have been made. The original steam generators were replaced with Westinghouse Model Delta-110 generators ... 3.1.2.2.3 Loss of Fracture Toughness due to Neutron Irradiation Embrittlement *1. Neutron irradiation embrittlement is a TLAA evaluated for the period of extended' operation in accordance with 10 CFR 54.21(c). The evaluation of loss of fracture toughness for the reactor vessel beltline shell and welds is discussed in Section . 4.2. 2. The Reactor Vessel Surveillance Program manages reduction in fracture toughness due to neutron embrittlement of reactor vessel beltline materials. This program monitors changes in the fracture toughness properties of ferritic *materials in the reactor pressure vessel (RPV) beltline region. As described.in Appendix B, the Reactor Vessel Surveillance Program is consistent with the program described in NUREG-1801, Section Xl.M31, Reactor Vessel Surveillance, including recommendations to submit the proposed withdrawal schedule for approval prior to implementation. 3. This paragraph in NUREG-1800 pertains to a plant-specific TLAA.for Babcock arid Wilcox reactor internals and is therefore not applicable to WF3. 3.0 Aging Management Review Results Page 3.1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.2.4 Cracking due to Stress Corrosion Cracking CSCC) and lntergranular Stress Corrosion Cracking CIGSCC) Both paragraphs in NUREG-1800 apply to BWRs only. 3.1.2.2.5 Crack Growth due to Cyclic Loading Crack growth due to cyclic loading could occur in reactor vessel shell forgings clad with stainless steel using a high-heat-input welding process. The major portion of the reactor vessel material protected by cladding from. exposure to reactor coolant is SA-533, Grade B, Class 1 plate which, as discussed in Regulatory Guide 1.43, is immune to underclad cracking. Cladding performed on SA-508, Class 2 forging material (vessel flange, and nozzles including safe ends) uses low-heat input welding processes controlled to minimize heating of the base metal. Low-heat-input welding processes are not known to induce underclad cracking. 3.1.2.2.6 Cracking due to Stress Corrosion Cracking 1. Cracking due to sec of the non-Class 1 stainless steel reactor vessel closure head flange leak detection line will be managed by the One-Time Inspection Program. The One-Time Inspection Program will use visual or other
nondestructive examination (NOE) techniques to verify the absence of significant cracking of the line. The WF3 vessel has no bottom-mounted instrument guide tubes. 2. Cracking due to SCC of cast austenitic stainless steel Class 1 piping, piping -components, and piping elements exposed to reactor coolant'will be managed by the Water Chemistry Control -Primary and Secondary and lnservice Inspection Programs. The Water Chemistry Control -Primary and Secondary Program minimizes contaminants which promote SCC. The, lnservice Inspection Program provides qualified inspection techniques to monitor cracking. SlJsceptibility tO thermal aging embrittlement will be evaluated in the Thermal Aging Embrittlement of CASS Program. Aging management for components that are determined to be susceptible to thermal aging embrittlement is accomplished using either enhanced visual examinations or component-specific flaw tolerance evaluations. Additional inspection or evaluations are not required for components that are determined not to be* susceptible to thermal aging embrittlement. 3.1.2.2.7 Cracking due to Cyclic Loading This paragraph in NUREG-1800 applies to BWRS only. 3.0 Aging Management Review Results Page 3.1-9 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.2.8 Loss of Material due to Erosion This paragraph in pertains to loss of material due to erosion in steel steam generator feedwater impingement plates and supports. The WF3 steam generators do not have feedwater impingement plates. 3.1.2.2.9 Removed as a result ofLR-ISG-2011-04 This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.1.2.2.10 Removed as a result of LR-ISG-2011-04 This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.1.2.2.11 Cracking_ due to Primarv Water Stress Corrosion Cracking CPWSCC) 1. Foreign operating experience in steam generators with a similar,design to that of Westinghouse Model 51 has identified extensive cracking due to primary water stress corrosion cracking (PWSCC) in steam generator divider plate assemblies fabricated of Alloy 600 and/or the associated Alloy 600 weld materials. The divider plate assemblies and the associa.ted welds oflhe WF3 replacement steam generators use Alloy 600 materials in limited applications and none is exposed to reactor coolant. The primary head is clad with stainless steel with the exception of areas near junctions with the tubesheet and partition plate which are clad with Alloy 690. The partition plate is composed of Alloy 690 and the tubesheet is clad with Alloy 690. WF3 replacement steam generators (RSGs) use Alloy 600 as a

cladding buffer between the channel head and the Alloy 690 weld build-up in the area of the partition plate. The area under the partition plate is filled with Alloy 600 with weld build-up of Alloy 690 over the Alloy 600. Also, a zone approximately 14.50 inches wide centered on the tubesheet 90°-270° axis is buttered with Alloy 600 and followed by subsequent layers of Alloy 690 filler metal. All nickel alloy in contact with primary coolant is Alloy 690. 2. Cracking due to PWSCC could occur in steam generator nickel alloy tube-to-* tubesheet welds exposed to reactor coolant. The WF3 replacement steam generators use Alloy 690 steam generator tubes with Alloy 690 tubesheet cladding. Cracking of nickel alloy tube to tubesheet welds is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. 3.1.2.2.12 Removed as a result of LR-ISG-2011-04 . This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.0 Aging Management Review Results Page 3.1-10 3.1.2.2.13 Removed as a result of LR-ISG-2011-04 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This paragraph was removed from._NUREG-1.800 by LR-ISG-2011-04. 3.1.2.2.14 Removed as a result of LR-ISG-2011:.04 This paragraph was removed from NUREG-1_800 by LR-ISG-2011-04. 3.1.2.2.15 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section B.0:3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3. 1.2.2.16 Ongoing Review of Operating Experience See Appendix B Section B.0.4 for discussion *of WF3 operating experience review .programs. Time-Limited Aging Analyses TLAAs identified for the reactor coolant syster:n include reactor vessel neutron embrittlement and metal fatigue. These topics are addressed in Section 4. * ' 3.1.3 Conclusion The vessel, internals and reactor coolant system components that are subject to aging management review havebe_en identified in accordance with the-requirements of 1OCFR54.21. The aging management programs selected to manage the aging *effects for the reactor vessel, internals anq reactor coolant system components are identified in Section 3.1.2: 1 and in the following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of *extended operation . . Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the reactor vessel, internals and reactor coolant system components will *be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the currehtlicensing basis during the period of extended operation. 3.0 Aging Management Review Results . Page3.1-11 Table 3.1.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Further Evaluation Number Component Mechanism Programs Recommended Discussion 3.1.1-1 High strength, low-alloy Cumulative fatigue Fatigue is a TLAA, Yes, TLAA Fatigue is a TLAA. steel top head closure damage due to fatigue evaluated for the period See Section 3.1.2.2.1. stud assembly exposed to of extended operation air with potential for (See SRP, Sec 4.3 reactor coolant leakage "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) 3.1.1-2 Nickel alloy tubes and Cumulative fatigue Fatigue is a TLAA Yes, TLAA Fatigue is a TLAA. sleeves exposed to damage due to fatigue evaluated for the period See Section 3.1.2.2.1. reactor coolant and of extended operation secondary feedwater/ (See SRP, Sec 4.3 steam "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1)) 3.1.1-3 Stainless steel or nickel Cumulative fatigue Fatigue is a TLAA, Yes, TLAA Fatigue is a TLAA. alloy reactor vessel damage due to fatigue evaluated for the period See Section 3.1.2.2.1. internal components of extended operation exposed to reactor (See SRP, Section 4.3 coolant and neutron flux "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) 3.0 Aging Management Review Results Page 3.1-12 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-4 Steel pressure vessel Cumulative fatigue support skirt and damage due to fatigue attachment welds 3.1.1-5 Steel, stainless steel, or Cumulative fatigue steel (with stainless steel damage due to fatigue or nickel alloy cladding) steam generator components, pressurizer relief tank components or piping components or bolting 3.1.1-6 BWRonly 3.1.1-7 BWRonly 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA, evaluated for the period of extended operation (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) Fatigue is a TLAA evaluated for the period of extended operation (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA The WF3 reactor vessel does not use a support skirt. Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Page 3.1-13 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-8 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), or stainless steel; or nickel alloy steam generator components exposed to reactor coolant 3.1.1-9 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), stainless steel; nickel alloy RCPB piping; flanges; nozzles & safe ends; pressurizer shell heads & welds; heater sheaths & sleeves; penetrations; thermal sleeves exposed to reactor coolant 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA evalu!'lted for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 1 O CFR 54.21 (c)(1 )) Fatigue is a TLAA evaluated for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 1 O CFR 54.21(c)(1)) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Fatigue is a TLAA. Section 3.1.2.2.1. Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Page 3.1-14 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-10 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), stainless steel; nickel alloy reactor vessel flanges; nozzles; penetrations; pressure housings; safe ends; thermal sleeves; vessel shells, heads and welds exposed to reactor coolant 3.1.1-11 BWR only 3.1.1-12 Steel steam generator Loss of material due to components: upper and general, pitting, and lower shells, transition crevice corrosion cone; new transition cone closure weld exposed to secondary feedwater or steam 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA evaluated for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21(c)(1)) Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD," and Chapter Xl.M2, "Water Chemistry," and, for Westinghouse Model 44 and 51 SIG, if corrosion of the shell is found, additional inspection procedures are developed Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Yes, detection of Consistent with NUREG-1801. aging effects is _to be Loss of material for steam evaluated generator head, shell and transition cone components exposed to secondary feedwater or steam is managed by the I nservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The WF3 replacement steam generators are Westinghouse Model Delta-110. See Section 3.1.2.2.2, Items 1 and 2 Page 3.1-15 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-13 Steel (with or without Loss of fracture stainless steel cladding) toughness due to reactor vessel beltline neutron irradiation shell, nozzles, and welds embrittlement exposed to reactor coolant and neutron flux 3.1.1-14 Steel (with or without Loss of fracture cladding) reactor vessel toughness due to beltline shell, nozzles, and neutron irradiation welds; safety injection embrittlement nozzles 3.1.1-15 Stainless steel Babcock & Reduction of ductility and Wilcox (including CASS, fracture toughness due martensitic SS, and PH to neutron irradiation SS) and nickel alloy embrittlement, and for reactor vessel internal CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement 3.1.1-16 BWR only 3.1.1-17 BWR only 3.0 Aging Management Review Results Aging Management Programs TLAA is to be evaluated in accordance with Appendix G of 10 CFR Part 50 and RG 1.99. The applicant may choose to demonstrate that the materials of the nozzles are not controlling for the TLAA evaluations Chapter Xl.M31, "Reactor Vessel Surveillance" Ductility -Reduction in fracture toughness is a TLAA to be evaluated for the period of extended operation. See the SRP, Section 4.7, "Other Plant-Specific TLAAs," for acceptable methods of meeting the requirements of 10 CFR 54.21 (c). Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Neutron irradiation embrittlement is a TLAA. See Section 3.1.2.2.3, Item 1. Yes, plant specific or Consistent with NUREG-1801. integrated The Reactor Vessel surveillance program Surveillance Program will manage loss of fracture toughness of the recictor vessel beltline materials. See Section 3.1.2.2.3 Item 2. Yes, TLAA The WF3 reactor vessel internals were designed by Combustion Engineering. See Section 3.1.2.2.3, Item 3. Page 3.1-16 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-18 Reactorvessel shell Crack growth due to fabricated of SA508-CI 2 cyclic loading forgings clad with stainless steel using a high-heat-input welding process exposed to reactor coolant 3.1.1-19 Stainless steel reactor Cracking due to stress vessel closure head corrosion cracking
flange leak detection line and bottom-mounted instrument guide tubes (external to reactor vessel) 3.0 Aging Management Review Results Aging Management . Programs Growth of intergranular separations is a TLAA evaluated for the period of extended operation. The Standard Review Plan, Section 4.7, Plant-Specific Time-Limited Aging Analysis," provides guidance for ** meeting the requirements of 10 CFR 54.21 (c). A plant-specific aging management program is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion . Yes, TLAA Most reactor vessel material protected by cladding is SA-533, Grade B, Class 1 plate. Cladding performed on SA-508, Class 2 forging material (vessel flange, and nozzles including safe ends) used low-heat.input welding processes. See Section 3.1.2.2.5. Yes, plant-specific Cracking of the stainless steel reactor vessel closure head \ flange leak detection line will be managed by the One-Time Inspection Program. The WF3 reactor vessel has no bottom-mounted instrument guide tubes. See Section 3.1.2.2.6, Item 1. Page 3.1-17 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-20 Cast austenitic stainless Cracking due to stress Chapter Xl.M2, "Water steel Class 1 piping, corrosion cracking Chemistry" and, for piping components, and CASS components that piping elements exposed do not meet the NUREG-to reactor coolant 0313 guidelines, a plant specific aging management program 3.1.1-21 BWR only 3.1.1-22 Steel steam generator Loss ofmaterial due to A plant-specific aging feedwater impingement erosion management program is plate and support exposed to be evaluated to secondary feedwater 3.1.1-23 [There is no 3.1.1-23 in NUREG-1800 as modified by the ISGs.] 3.1.1-24 [There is no 3.1.1-24 in NUREG-1800 as modified by the ISGs.] 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific Cracking of cast austenitic stainless steel Class 1 piping, piping components, and piping elements exposed to reactor coolant will be managed by the lnservice Inspection, Thermal Aging Embrittlement of CASS and Water Chemistry Control -Primary and Secondary Programs. See Section 3.1.2:2.6, Item 2. Yes, plant-specific The WF3 steam generators do not have steel steam generator feedwater impingement plates. See Section 3.1.2.2.8. Page 3.1-18 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-25 Steel (with nickel-alloy Cracking due to primary Chapter Xl.M2, "Water cladding) or nickel alloy water stress corrosion Chemistry" steam generator primary cracking side components: divider plate and tube-to-tube sheet welds exposed to reactor coolant .. 3.1.1-26 [There is no 3.1.1-26 in NUREG-1800 as modified by the ISGs.] 3.1.1-27 [There is no 3.1.1-27 in NUREG-1800 as modified by the ISGs.] 3.1.1-28 Stainless steel Loss of material due to Chapter Xl.M16A, "PWR Combustion Engineering wear; cracking due to Vessel Internals," and "Existing Programs" stress-corrosion Chapter Xl.M2, "Water components exposed to cracking, irradiation-Chemistry" (for SCC reactor coolant and assisted stress-mechanisms only) neutron flux corrosion cracking, or fatigue 3.1.1-29 BWRonly 3.1.1-30 BWRonly 3.1.1-31 BWRonly 3.0 Aging Management Review Results / -Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific Cracking of nickel alloy tube to tubesheet welds is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. Cracking of the nickel alloy (Alloy 690) steam generator primary side divider plate exposed to reactor coolant is managed by the Water Chemistry Control -Primary and Secondary Program. See Section 3.1.2.2.11, Items 1and2 No The WF3 reactor vessel internals design does not include thermal shield positioning pins. Page 3.1-19 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-32 Stainless steel, nickel Cracking, or loss of alloy, or CASS reactor material due to wear vessel internals, core support structure (not already referenced as ASME Section XI Examination Category 8-N-3 core support structure components in MRP-227-A}, exposed to reactor coolant and neutron flux 3.1.1-33 Stainless steel, steel with Cracking due to stress stainless steel cladding corrosion cracking Class 1 reactor coolant pressure boundary components exposed to reactor coolant 3.1.1-34 Stainless steel, steel with Cracking due to stress stainless steel cladding corrosion cracking pressurizer relief tank (tank shell and heads, flanges, nozzles) exposed to treated borated water >60°C {>140°F) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" or Chapter Xl.M16A, "PWR Vessel Internals," invoking applicable 10 CFR 50.55a and ASME Section XI inservice inspection requirements for these components Chapter Xl.M1, "ASME Section XI lnservicei Inspection, Subsections IWB, IWC, and IWD" for ASME components, and Chapter Xl:M2, "Water Chemistry" Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for ASME components, and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Cracking and loss of material due to wear of the reactor vessel internals core support structure components is managed by the Reactor Vessel Internals Program which uses ASME Section XI lnservice Inspection, Subsection IWB as required. These AMR results are compared to other table items (3.1.1-52a, 3.1..1-52b, 3.1.1-52c, 3.1.1-55b and 3.1.1-56c). No Consistent with NUREG-1801. Cracking of stainless steel reactor coolant pressure boundary components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. No The nonsafety-related relief tank is not subject to ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD. Page 3.1-20 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-35 Stainless steel, steel with Cracking due to cyclic stainless steel cladding loading reactor coolant system cold leg, hot leg, surge line, and spray line piping and fittings exposed to reactor coolant 3.1.1-36 Steel, stainless steel Cracking due to cyclic pressurizer integral loading support exposed to air with metal temperature up . to 288°C (550°F) 3.1.1-37 Steel reactor vessel flange Loss of material due to wear 3.1.1-38 Cast austenitic stainless Loss of fracture steel Class 1 pump toughness due to thermal ca,sings, and valve bodies aging embrittlement and bonnets exposed to reactor coolant >250 deg-C (>482 deg-F) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components Chapter Xl.M1, "ASME Section XI Inspection, Subsections IWB, IWC, arid IWD" for Class 1 components Chapt.er Xl.M1, "ASME , Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD".for Class 1 components. For pump casings and valve bodies, screening for susceptibility to thermal aging is not necessary. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No with NUREG-1801. Cracking of Class 1 reactor coolant piping is managed by the lnseivice Inspection Program. No Consistent with NUREG-1801. Cracking of the pressurizer support skirt is managed by
the lnservice Inspection Program. No Consistent with NUREG-1801. Loss. of material due to wear, of the vessel flange is managed by the lnservice Inspection Program .. No . Consistent with NUREG-1801. The lnservice Inspection Program manages the reduction of fracture toughness in cast austenitic stainless ste'el pump casings and valve bodies in the reactor coolant pressure boundary. Page 3.1-21 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-39 Steel, stainless steel, or Cracking due to stress steel with stainless steel corro.sion cracking, cladding Class 1 piping, intergranular stress fittings and branch corrosion cracking (for connections < NPS 4 stainless steel only), and exposed to reactor thermal, mechanical, and coolant vibratory loading .. 3.1.1-40 Steel with stainless steel* Cracking due to cyclic or nickel alloy cladding; or loading stainless steel pressurizer components exposed to reactor coolant . 3.1.1-40.5 Nickel alloy core support Cracking due to primary pads;. core guide lugs water stress corrosion exposed tp reactor coolant cracking 3.0 Aging Management Review Results Aging Management Programs . Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, Chapter Xl.1\112, "Water Chemistry," and Xl.M35, "One-Time Inspection of ASME Code Class 1 Small-bore Piping" . Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M1, "ASME Section XI lnservice
Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Cracking in stainless steel components of the reactor coolant pressure boundary exposed to reactor coolant is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs .. The One-Time Inspection -Small-Bore Piping Program will verify the effectiveness of the water chemistry program and will manage cracking in piping and fittings < 4" NPS. No Consistent with NUREG-1801. Cracking of Class 1 pressurizer components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking of nickel alloy vessel internal attachments is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Page 3.1-22 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-41 BWRonly 3.1.1-42 Steel with stainless steel Cracking due to stress or nickel alloy cladding or corrosion cracking; stainless steel primary primary water stress side components; steam corrosion cracking generator upper and lower heads, and tube sheet weld; or pressurizer components exposed to reactor coolant 3.1.1-43 BWRonly 3.1.1-44 Steel steam generator Loss of material due to secondary manways and erosion handholes (cover only) exposed to air with leak.ing secondary-side water and/ or steam -, 3.0 Aging Management Review Results / Aging Management Programs Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M1, "ASME
Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 2 components Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of steel with stainless steel or nickel alloy cladding and stainless steel pressurizer components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. WF3 uses recirculating steam generators. No Consistent with NUREG-1801 for manways and handholes without seal welded diaphragms. The lnservice Inspection Program manages loss of material due to erosion for steel secondary side steam generator manway and handhole covers. Page 3.1-23 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-45 Nickel alloy and steel with Cracking due to primary Chapter Xl.M1, "ASME nickel-alloy cladding water stress corrosion Section XI ISi, IWB, IWC reactor coolant pressure cracking & IWD," and Chapter boundary components Xl.M2, "Water exposed to reactor coolant Chemistry," and, for nickel-alloy, Chapter Xl.M118, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced Corrosion in RCPB Components (PWRs Only)" 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for nickel alloy (Alloy 600) components. Cracking of nickel alloy (Alloy 600) components is managed by the lnservice Inspection, Nickel Alloy Inspection and Water Chemistry Control -Primary and Secondary Programs. For other nickel alloy (Alloy 690) components, cracking is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Loss of material due to boric acid corrosion in steel external surfaces near nickel alloy (Alloy 600) pressure boundary components is addressed in Item 3.1.1-48. Page 3.1-24 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-46 Stainless steel, nickel-Cracking due to stress alloy, riickel-alloy welds corrosion cracking, and/or buttering control primary water stress rod drive head penetration corrosion cracking pressure housing or nozzles safe ends and welds (inlet, outlet, safety injection) exposed to. reactor coolant 3.1.1-47 Stainless steel, nickel-Cracking due to stress alloy control rod drive corrosion cracking, head penetration pressure primary water stress housing exposed to corrosion cracking reactor coolant 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME Section XI ISi, IWB, IWC & IWD," and Chapter Xl.M2, "Water Chemistry," and, for nickel-alloy, Chapter Xl.M11 B, "Cracking of
Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced* corrosion in RCPB Components (PWRs Only)" Chapter Xl.M1, "ASME Section XI ISi, IWB, IWC & IWD," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended -Discussion No_ The control element drive mechanism (CEDM) motor housing lower end fitting is composed of Alloy 690. Cracking of this component is managed.by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The reactor vessel safe ends are carbon steel clad with stainless steel and are compared to Item 3 .1.1-33. No Consistent with NUREG-1801. Cracking of the stainless CEDM motor housing components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Nickel alloy components are compared to Item 3.1.1-46. Page 3.1-25 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-48 Steel external surfaces: Loss of material due to reactor vessel top head, boric acid corrosion reactor vessel bottom head, reactor coolant pressure boundary piping or components adjacent to dissimilar metal (Alloy 82/ 182) welds exposed to air with borated water leakage 3.1.1-49 .Steel reactor coolant Loss of material due to pressure boundary boric acid corrosion external surfaces or closure bolting exposed to a!r with borated water leakage 3.1.1-50 Cast austenitic stainless Loss of fracture steel Class 1 piping, toughness due to thermal piping component, and aging embrittlement piping elements and control rod drive pressure housings exposed to reactor coolant >250 deg-C (>482 deg-F) 3.0 Aging Management Review Result!? Aging Management Programs Chapter Xl.M10, "Boric Acid Corrosion," and Chapter Xl.M11 B, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in RCPB Components (PWRs Only)" . Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M12, * "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)" .. " *. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Loss of material due to boric acid corrosion in steel external surfaces near nickel alloy (Alloy 600) pressure boundary components, is managed by. the Boric Acid Corrosion and Nickel Alloy Inspection Programs. No Consistent with NUREG-1801. Loss of material due to boric acid corrosion in steel components is managed by the Boric Acid Corrosion Program. No Consistentwith NUREG-1801. Loss of fracture toughness in CASS components is managed by the Thermal Aging Embrittlement of CASS Program. Page 3. 1-26.

Table 3.1.1 : Reactor Coolant Item " Aging Effect/ Number Component Mechanism 3.1.1-51a Stainless steel or nickel Cracking (jue to stress alloy Babcock & Wilcox corrosion cracking, reactor internal "Pr.imary" irradiation-assisted components exposed to

stress corrosion reactor coolant and . . cracking, *or fatigue neutron flux 3.1.1-51b Stainless steel or nickel Cracking due to stress alloy Babcock *& Wilcox. corrosion cracking, reacfor internal
irradiation-assisted "Expansion" components stress corrosion exposed to reactor cracking, fatigue, or coolant and neutron flux overload 3.1.1-52a Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering ,reactor '*irradiation-assisted intern;al "Primary" stress corrosion components exposed to . cracking, or fatigue reactor coolarit and neutron flux '* 3.p Agirig Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals,. and . Chapter Xl.M2, "Water Chemistry" (for SCC * , mechanisms only) ... Chapter Xl.M16A, "PWR *. Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and . Chapter Xl.M2, ."Water Chemistr-Y" (for SCC mechani.sms only) .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801 for stainless steel "Primary" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Contra! -Primary a.nd Secondary Programs.
There are no nickel alloy "Primary" internals components. Page 3.1-27
Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-52b Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering reactor irradiation-assisted internal "Expansion" stress corrosion components exposed to cracking, or fatigue reactor coolant and . neutron flux 3.1.1-52c Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering reactor irradiation-assisted internal "Existing stress corrosion Programs" components cracking, or fatigue exposed to reactor coolant and neutron flux 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Expansion" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Control -Primary and Secondary Programs. There are no nickel alloy "Expansion" internals components. No Consistent with NUREG-1801 for stainless steel "Existing Programs" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Control -Primary and Secondary Programs. There are no nickel alloy "Existing Programs" internals components. Page 3.1-28 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-53a . Stainless steel or nickel Cracking due to stress alloy Westinghouse corrosion cracking, reactor internal "Primary" irradiation-assisted components exposed to stress corrosion reactor coolant and cracking, or fatigue neutron flux 3.1.1-53b Stainless steel Cracking due to stress Westinghouse reactor corrosion cracking, internal "Expansion" irradiation-assisted components exposed to stress corrosion reactor coolant and cracking, or fatigue flux 3.1.1-53c Stainless steel or nickel Cracking due to stress alloy Westinghouse corrosion cracking, reactor internal "Existing irradiation-assisted Programs" components stress corrosion exposed to reactor cracking, or fatigue coolant and neutron flux 3.1.1-54 Stainless steel bottom Loss of material due to mounted instrument wear system flux thimble tubes (with or without chrome plating) exposed to reactor coolant and neutron flux Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," or Chapter Xl.M37, "Flux Thimble Tube Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation -Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No The Combustion Engineering designed reactor vessel does not use bottom mounted instrument system flux thimble tubes. 3.0 Aging Management Review Results Page 3.1-29 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-55a Stainless steel or nickel No additional aging alloy Babcock and Wilcox management for reactor reactor internal "No internal "No Additional Additional Measures" Measures" components components exposed to unless required by ASME reactor coolant and Section XI, Examination neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A. 3.1.1-55b Stainless steel or nickel No additional aging alloy Combustion management for reactor Engineering reactor internal "No Additional internal "No Additional Measures" components Measures" components unless required by ASME exposed to reactor Section XI, Examination coolant and neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A. 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801 for stainless steel or nickel alloy "No Additional Measures" components. The Reactor Vessel Internals Program manages aging effects for these components. The Water Chemistry Control -Primary and Secondary Program supplements the Reactor Vessel Internals Program for the prevention of stress corrosion cracking. Page 3.1-30 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component
Mechanism 3.1.1-55c Stainless steel or nickel No additional aging alloy Westinghouse. management for reactor reactor internal "No internal "No Additional . Additional Measures" Measures" components components exposed to unless required by ASME
reactor coolant and Section XI, Examination neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A'. 3.1.1-56a Stainless steel (SS, Loss of fracture including CASS, PH SS or. toughness due to martensitic SS) or nickel neutron irradiation alloy Combustion embrittlement and for Engineering reactor CASS, martensitic SS, internal "Primary" and PH SS due to components exposed to
thermal aging reactor coolant and embrittlement; or neutron flux changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss o,f material. due to wear ' ' 3.0 Aging Management Review Results ( Aging Management Programs Chapter Xl.M16A, "P.WR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801
for stainless steel "Primary" components. Reduction of fracture toughness and changes in dimension of stainless steel reactor vessel internals components are . managed by the Reactor Vessel Internals Program. There are no nickel alloy "Primary" internals components. Page 3.1-31 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-56b Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) neutron irradiation Combustion Engineering embrittlement and for "Expansion" reactor CASS, martensitic SS, internal components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Expansion" components. Reduction of fracture toughness and changes in dimension of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals Program. Page 3.1-32 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-56c Stainless steel (SS, Loss offracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Combustion embrittlement and for Engineering reactor CASS, martensitic SS, internal "Existing and PH SS due to Programs" components thermal aging exposed to reactor embrittlement; or coolant and neutron flux changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.1.1-57 [There is no 3.1.1-57 in NUREG-1800.] 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" ,---Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Existing" components. Reduction of fracture toughness, loss of preload and loss of material due to wear of stainless steel and Zircaloy reactor vessel internals components is managed by the Reactor Vessel Internals Program. There are no nickel alloy "Existing" internals components. Page 3.1-33 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-58a Stainless steel (SS, Loss offracture including CASS, PH SS or toughness due to martensitic SS) or nickel
neutron irradiation alloy Babcock & Wilcox embrittlement and for reactor internal "Primary" CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to wear; or loss of material due to wear 3.1.1-58b Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Babcock & Wilcox embrittlement and for reactor internal CASS, martensitic SS, "Expansion" components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. Page 3.1-34 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechariism 3.1.1-59a Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Westinghouse embrittlement and for reactor. internal "Primary" CASS, martensific SS, components exposed to . and PH SS due to reactor coolant and thermal aging
neutron. flux
embrittlement; or changes in oimensions due _to void swelli'ng or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material. due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" " Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. ' Page 3.1-35

. Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-59b Stainless steel (SS,

Loss of fracture including CASS, PH SS or toughness due to martensitic SS) neutron irradiation Westinghouse reactor embrittlement and for internal "Expansion" CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement; or ' changes in dimensions . due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information. Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. Page 3.1-36 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-59c Stainless steel (SS, Loss -of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Westinghouse embrittlement and for reactor internal "Existing CASS, martensitic SS, Programs" components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or . distortion; or los*s of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.1.1-60 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactOr vessel internals were designed by Combustion Engineering. Page 3.1-37 Table 3.1.1: Reactor Coolant Systein Item Aging Effect/ Number Component Mechanism 3.1.1-61 Steel steam generator Wall thinning due to flow-steam nozzle and safe accelerated corrosion end, feedwater nozzle and safe end, AFW nozzles and safe ends exposed to secondary feedwater/ steam 3.1.1-62 High-strength, low alloy Cracking due to stress steel, or stainless steel corrosion cracking closure bolting; stainless steel control rod drive head penetration flange bolting exposed to air with reactor coolant leakage 3.1.1-63 BWRonly 3.1.1-64 Steel closure bolting Loss of material due to exposed to air -indoor general, pitting, and uncontrolled crevice corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M17, "Flow-Accelerated Corrosion" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for the steam generator blowdown nozzles. The Flow-Accelerated Corrosion Program manages loss of material due to FAC for these nozzles. The steam generator outlet nozzles use nickel alloy flow inserts which protects the steel nozzle from flow accelerated corrosion (FAC). The feedwater nozzles contain a nickel alloy thermal sleeve that isolates the carbon steel nozzle from feedwater flow, so the feedwater nozzles are not susceptible .to FAC. No Consistent with NUREG-1801. Cracking of stainless steel and high-strength steel bolting is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Loss of material for steel closure bolting is managed by the Bolting Integrity Program. Page 3.1-38 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism .3.1.1-65 Stainless steel control rod Loss of material due to drive head penetration wear flange bolting exposed to air with reactor coolant leakage 3.1.1-66 IC?W alloy Loss of preload due to steel, or stainless steel thermal effects.gasket ' closure bolting; stainless creep, and self-steel control rod drive loosening head penetration flange ; bolting exposed to air with ; reactor coolant leakage 3.1.1-67 Steel or stainless steel Loss of preload due to closure bolting exposed to thermal effects, gasket air ""'" indoor with potential creep, and * . for reactor coolant leakage 3.1.1-68 Nickel alloy steam
qhanges in dimension generator tubes exposed ("denting") due to
to secondary feedwater or corrosion of carbon steel . steam* . tube support plate 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Boltin!;J Integrity" Chapter Xl.M18, "Bolting Integrity"_ ; Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water C.hemistry" Waterford Steam Electric Station, Unit 3 License Renewal*.Application . Technical* Information Further Evaluation Recommended Discussion No WF3 does not use bolting for the control rod drive head *.* penetration flange .. No . Consistentwith NUREG-1801. Loss of preload for steel, high-strength steel and stainless steel closure bolting is managed by the 1;3olting Integrity Program. No Consistent with NUREG-1801. Loss of preload for steel closure bolting is managed by the Bolting Integrity Program. Loss:of preload for stainless . steel closure bolting is compared to Item 3.1.1-66. No The WF3 replacement steam generators do not use carbon steel tube support plates. Page 3.1-39 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-69 Nickel alloy steam Cracking due to outer generator tubes and diameter stress corrosion sleeves exposed to cracking and secondary feedwater or intergranular attack steam 3.1.1-70 Nickel alloy steam Cracking due to primary generator tubes, repair water stress corrosion sleeves, and tube plugs cracking exposed to reactor coolant 3.1.1-71 Steel, chrome plated Cracking due to stress steel, stainless steel, corrosion cracking or nickel alloy steam other mechanism(s); loss generator U-bend of material due general supports including anti-(steel only), pitting, and vibration bars exposed to crevice corrosion secondary feedwater, or steam 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam, Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter ,XlM2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Cracking of nickel alloy steam generator components is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking of nickel alloy steam generator components is managed by the Steam Generator Integrity and Water -Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking and loss of material for steam generator tube support components is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. Page 3.1-40 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-72 Steel steam generator Loss of material due to tube support plate, tube erosion, general, pitting, bundle wrapper, supports and crevice corrosion, and mounting hardware ligament cracking due to exposed to secondary. corrosion feedwater or steam -* . 3.1.1-73 Nickel alloy steam Loss of material due to generator tubes and wastage and pitting sleeves exposed to . corrosion phosphate chemistry in secondary feedwater or steam 3.1.1-74 Steel steam generator Wall thinning due to flow-upper assembly and accelerated corrosion separators including feedwater inlet ring and support exposed to secondary feedwater or steam 3.1.1-75 Steel steam generator Wall thinning due to flow-tube support lattice bars accelerated corrosion exposed to secondary and general corrosion feedwater or steam 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information I Further Evaluation
Recommended Discussion No Consistent with NUREG-1801. Loss of material for carbon steel steam generator support
components exposed to secondary feedwater or steam is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. The WF3 replacement steam generators do not use carbon
steel tube support plates. No ' WF3 does not use phosphate chemistry in the secondary feedwater. No The WF3 replacement steam generator steel feedwater piping components are composed of alloy steel (Cr-* Mo) which is.resistant to FAC. No The WF3 replacement steam generators do not use carbon steel tube support lattice bars. Page 3.1-41 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-76 Steel, chrome plated Loss of material due to steel, stainless steel, fretting nickel alloy steam generator U-bend supports including anti-vibration bars exposed to secondary feedwater or steam 3.1.1-77 Nickel alloy steam Loss of material due to generator tubes and wear and fretting sleeves exposed to secondary feedwater or steam 3.1.1-78 Nickel alloy steam Cracking due to stress generator components corrosion cracking such as, secondary side nozzles (vent, drain, and instrumentation) exposed to secondary feedwater or steam 3.1.1-79 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam Generators" Chapter Xl.M19, "Steam Generators" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection," or Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD." Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to fretting (wear) for steel, stainless steel and nickel alloy steam generator tube support components is managed by the Steam Generator Integrity Program. No Consistentwith NUREG-1801. Loss of material due to fretting (wear) nickel alloy steam generator tubes is managed by the Steam Generator Integrity Program. No Consistent with NUREG-1801. Cracking of nickel alloy steam generator components exposed to secondary feedwater or steam is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-42 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-80 Stainless steel or steel Cracking due to stress with stainless steel corrosion cracking cladding pressurizer relief
tank: tank shell and heads, flanges, nozzles (none-ASME Section XI components) exposed to treated borated water >60°C (>140°F) 3.1.1-81 Stainless steel pressurizer Cracking due to stress spray head exposed to corrosion* cracking reactor coolant 3.1.1-82 Nickel alloy pressurizer Cracking due to stress spray head exposed to corrosion cracking, reactor coolant primary water stress corrosi.on cracking 3.0 Aging Management Review Resuits Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" ' Chapter Xl.M2, "Water Chemistry," and Chapter XLM32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information *Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless s.teel non-Class 1 components is managed by the Water Chemistry Control ...,. Primary and Secondary Program. The One-Time Inspection Program . will the effectiveness of the water chemistry program. No The pressurizer spray head components are made of nickel alloy. No
ConsistentwithNUREG-1801. Cracking of nickel alloy spray head components is managed by tlie Water Chemistry
Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-43 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-83 Steel steam generator Loss of material due to shell assembly exposed to general, pitting, and secondary feedwater or crevice corrosion steam 3.1.1-84 BWRonly 3.1.1-85 BWRonly 3.1.1-86 Stainless steel steam Cracking due to stress generator primary side corrosion cracking divider plate exposed to reactor coolant 3.1.1-87 Stainless steel or nickel-Loss of material due to alloy PWR reactor internal pitting and crevice components exposed to corrosion reactor coolant and neutron flux 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry" Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Loss of material of steel steam generator components exposed to secondary feedwater or steam is managed by the Water Chemistry Control -Primary and Secof1dary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No The steam generator primary side divider plate is made of nickel alloy (Alloy 690). No Consistentwith NUREG-1801. Loss of material of stainless steel or nickel alloy reactor vessel internal components is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-44 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-88 Stainless steel; steel with Loss of material due to nickel-alloy or stainless pitting and crevice steel cladding; and nickel-corrosion alloy reactor coolant pressure boundary components exposed to reactor coolant . 3.1.1-89 Steel piping, piping Loss of material due to components, and piping general, pitting, and elements exposed to crevice corrosion closed cycle cooling water 3.1.1-90 Copper alloy piping, piping Loss of material due to components, and piping pitting, crevice, and elements exposed to galvanic corrosion closed cycle cooling water 3.1.1-91 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry" Chapter Xl.M21A,, "Closed Trea.ted Water Systems" *
Chapter Xl.M21A, "Closed Treated Water Systems" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of steel with nickel alloy or stainless steel cladding, stainless steel, and nickel-alloy components exposed to reactor coolant is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No Consistentwith NUREG-1801. Loss of material of steel components exposed to closed cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems. Program. No Consistent with NUREG-1801. Loss of material of copper alloy components exposed to closed cycle cooling water is managed by the Water . Chemistry Control -Closed Treated Water Systems Program.

Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-92 High-strength low alloy Cracking due to stress steel closure head stud corrosion cracking; loss* . assembly exposed to air of material due to with potential for reactor general, pitting, and coolant leakage crevice corrosion, or wear(PWR) 3.1.1-93 Copper alloy >15% Zn or Loss of material due to > 8% [aluminum] Al piping, selective leaching piping components, and piping elements exposed to closed cycle cooling water 3.1.1-94 BWRonly 3.1.1-95 BWRonly 3.1.1-96 BWRonly 3.1.1-97 BWRonly 3.1.1-98 BWRonly 3.1.1-99 BWRonly 3.1.1-100 BWRonly 3.1.1-101 BWRonly 3.1.1-102 BWRonly 3.1.1-103 BWRonly 3.1.1-104 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M3, "Reactor Head Closure Stud Bolting" Chapter Xl.M33, "Selective Leaching" ,, Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking, loss of material, and loss of material due to wear of the closure head stud assembly is*managed by the Reactor Head Closure Studs Program. No Consistent with NUREG-1801. Loss of material of copper alloy >15% Zn or> 8% Al components exposed to closed cycle cooling water is managed by the Selective Leaching Program. Page 3.1-46 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-105 Steel piping, piping None components and piping element exposed to . concrete 3.1.1-106 Nickel alloy piping, piping None components and piping element exposed to air.-indoor, uncontrolled, or air with borated water leakage 3.1.1-107 Stainless steel piping, None piping components and piping element exposed to gas, concrete, air with borated water leakage, air -indoors, uncontrolled 3.1.1-108 [There is no 3.1.1-108 in NUREG-1800.] 3.1.1-109 [There is no 3 .. in NUREG-1800.] 3.1.1-f10 BWRonly 3.0 Aging Management Review Results Aging Management Programs None, provided 1) attributes of the concrete are consistent with [American Concrete Institute] ACI 318 or ACI 349 (low water-to-cement

ratio, low permeability", and adequate air entrainment) as cited in NUREG-1557, and 2) plant"[operating experience] OE indicates no degradation of the concrete None Waterford Steam Electric Station,. Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No, if conditions are No steel reactor coolant met. system or reactor coolant pressure boundary piping components are embedded in concrete. NA -No [aging effecU Consistent with NUREG-1801. mechanism] AEM or AMP '. None NA -No AEM or AMP Consistent-with NUREG-1801 for components exposed to air. There are no stainless steel RCS components exposed to gas or concrete in the scope of license renewal. ... ,, Page 3.1-47 Notes for Tables 3.1.2-1 through 3.1.2-5-2
Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 .fine item. AMP is consistent with f\JUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 101. The One-Time Inspection Program wiil verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 102. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 103. This component is not composed of Alloy 600/82/182 materials. Alloy 690 is not considered susceptible to primary water stress corrosion cracking. 104. Nuts and washers are high strength steel but stud materials are not high strength steel. Measured yield strength of stud material < 150 kilo-pounds per square inch (ksi). 105. High component surface temperature precludes moisture accumulation that could result in corrosion. 3.0 Aging Management Review Results Page 3.1-48 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Reactor vessel Pressure components boundary Reactor vessel Pressure components boundary
Closure head stud assemblies Bolting Pressure ICl/HJTC-CET boundary assemblies
Swageloc modified, bodies
Compression collar
Hold down nuts Closure head Pressure
Center dome boundary 3.0 Aging Management Review Results Table 3.1.2-1 Reactor Vessel Summary of Aging Evaluation
Aging Effect Aging Requiring Management Material Environment Management Programs Carbon steel, Treated borated Cracking-TLAA-metal Carbon steel water (int) fatigue fatigue clad with stainless steel, Nickel alloy, Stainless steel Low alloy Air -indoor (ext) Cracking-TLAA-metal steel *fatigue fatigue Stainless Air-indoor (ext) Loss of preload Bolting Integrity steel** .. Carbon steel Treated borated Loss of material Water Chemistry clad with water> 140°F Control -Primary stainless steel (int) and Secondary / Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-219 3.1.1-10 A IV.A2.RP-54 3.1.1-1 A, 104 IV.A2.R-80 3.1.1-66 B IV.A2.RP-28 3.1.1-88 A Page 3.1-49 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Material Environment Closure head Pressure Carbon steel Treated borated
Center dome boundary clad with water > 140°F stainless steel (int) Closure head Pressure Carbon steel Air-indoor (ext)
Center dome boundary Closure head Pressure Carbon steel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon s.teel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon steel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon steel Air-indoor (ext)
Flange boundary Closure head Pressure Nickel alloy Treated borated penetrations boundary (Alloy 690) water (int)
Vent pipe nozzle
CEDM and ICI nozzles 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material lnservice -wear Inspection Loss of material Boric Acid Corrosion Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-87 3.1.1-37 A IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A Page 3.1-50 Table 3.1.2-1: Reactor Vessel Intended Component Type Function Material Environment Closure head Pressure Nickel alloy Treated -borated penetrations boundary (Alloy 690) water (int)
Vent pipe nozzle
CEDM and ICI nozzles Closure head Pressure Nickel alloy Air -indoor (ext) penetrations boundary (Alloy 690)
Vent pipe nozzle
CEDM and ICI nozzles Closure head bolting Pressure High strength Air -indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure High strength Air-indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure High strength Air-indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure Low alloy Air -indoor (ext)
Studs boundary steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary None None Loss of material Boric Acid Corrosion Reactor Head Closure Studs Loss of material Reactor Head -wear Closure Studs Cracking Reactor Head Closure Studs Loss of material Boric Acid Corrosion Reactor Head Closure Studs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-90 3.1.1-45 E, 103 IV.E.RP-378 3.1.1-106 A IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.R-17 3.1.1-49 IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.RP-52 3.1.1-92 A, 104 IV.A2. RP-53 3.1.1-92 A, 104 IV.A2.R-17 3.1.1-49 Page 3.1-51 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Material Environment Closure head bolting Pressure Low alloy Air-indoor (ext)
Studs boundary steel Control rod drive Pressure Stainless Treated borated assembly boundary steel water> 140°F
CEDM motor (int) housing (tube) and Pressure Stainless Treated borated upper end fitting boundary steel water> 140°F
Versa vent assembly (int) ICI assembly
Flange adaptor *Seal plug Pressure Stainless Air-indoor (ext)
Swageloc modified boundary steel body
Compression collar/ nut Control rod drive Pressure Nickel alloy Treated borated assembly boundary (Alloy 690) water (int)
CEDM motor housing lower end fitting Control rod drive Pressure Nickel alloy Treated borated assembly boundary (Alloy 690) water (int)
CEDM motor housing lower end fitting Flow skirt Pressure Nickel alloy Treated borated boundary water (inUext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Reactor Head -wear Closure Studs Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondarv Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.RP-28 3.1.1-88 c IV.A2.RP-55 3.1.1-47 A IV.E.RP-04 3.1.1-107 c IV.A2.RP-28 3.1.1-88 A IV.A2.RP-234 3.1.1-46 E, 103 IV.A2.RP-28 3.1.1-88 c Page 3.1-52 Table 3.1.2-1: Reactor Vessel Intended Component Type Function Material Environment Flow skirt Pressure Nickel alloy Treated borated boundary water (int/ext) Nozzles (including Pressure Carbon steel Treated borated safe ends) boundary clad with water> 140°F Inlet I outlet stainless steel (int) Nozzles (including Pressure Carbon steel Treated borated safe ends) boundary clad with water > 140°F
Inlet I outlet stainless steel (int) Nozzles (including Pressure Carbon steel Air -indoor (ext) safe ends) boundary
Inlet I outlet Vessel external Structural Carbon steel Air-indoor (ext) attachment support '
Vessel support pads Vessel external Pressure Carbon steel Air-indoor (ext) attachment boundary
Closure head lifting lugs 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-57 3.1.1-40.5 c IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.R-17 3.1.1-49 A IV.A2.R-17 3.1.1-49 A Page 3.1-53 Table 3.1.2-1: Reactor Vessel Intended Component Type Function . Material Environment Vessel internal Structural Nickel alloy Treated borated attachments support water (ext)
Core.stabilizing lugs
Core stop lugs Vessel internal Structural Nickel alloy Treated borated attachments support water (ext)
Core stabilizing lugs
Core stop lugs Vessel flange Pressure Carbon steel Treated borated (including core barrel boundary clad with water> 140°F support ledge) Structural stainless steel (int) support Vessel flange Pressure Carbon steel. Treated borated (including core barrel boundary clad with water> 140°F support ledge) Structural stainless steel (int) support
Vessel flange Pressure Carbon steel Treated borated (including core barrel bounda,ry clad with water> 140°F support ledge) Structural stainless steel (int) support Vessel flange Pressure
Carbon steel Air -indoor (ext) (including core barrel boundary support ledge) Structural support 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary -' and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material lnservice -wear Inspection Loss-of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-28 3.1.1-88 c IV.A2.RP-57 3.1.1-40.5 A IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-87 3.1.1-37 A IV.A2.R-17 3.1.1-49 A Page 3.1-54 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function '.Material Environment
Vessel shell .assembly Pressure Carbon steel Treated borated (including welds) boundary clad with water.> 140°F
Bottom head stainless steel (int) -Torus -Dome Vessel shell assembly Pressure Carbon steel
Treated borated (including welds) boundary clad with water> 140°F
Bottom head stainless steel (int) -Torus -Dome Vessel shell assembly Pressure Carbon steel Air-indoor (ext) (including welds) boundary
Bottom head -Dome Vessel shell assembly Pressure Carbon steel Treated borated' (including welds) boundary : clad with water > 140°F *Upper shell stainless steel (int)
Intermediate shell *Lower shell Vessel shell assembly Pressure Carbon steel Treated borated (including welds) boundary clad with water> 140°F *Upper shell stainless steel (int}
Intermediate shell
Lowershell 3.0 Aging Management Review Results Aging Effect Aging Requiring Management . Management Programs Loss of material Water Chemistry . Control -Primary ' . and Secondc:iry Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of ma_terial Boric Acid Corrosion ' Loss of material
Water Chemistry Control -Primary and Secondary Cracking* lnservice. Inspection Water Chemistry Control.-Primary and Secondary Waterford Steam Electric StatiorJ, Unit 3 License Renewal Application Technical Information NU REG-Table 1 18.01 Item Item *Notes IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A IV.C2*.R-30 3.1, 1-33 c Page 3.1-55 Table 3.1.2-1: Reactor Vessel Aging Effect Intended Requiring Component Type Function Material Environment Management Vessel shell assembly Pressure Carbon steel Treated borated Reduction of (including welds) boundary clad with water > 140°F fracture
Upper shell stainless steel (int) toughness
Intermediate shell Neutron fluence
Lower shell Vessel shell assembly Pressure Carbon steel Air -indoor (ext) Loss of material (including welds) boundary
Upper shell
Intermediate shell *Lower shell 3.0 Aging Management Review Results Aging Management Programs TLAA -neutron fluence Reactor Vessel Surveillance Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-84 3.1.1-13 A IV.A2.RP-229 3.1.1-14 IV.A2.R-17 3.1.1-49 A Page 3.1-56 Table 3.1.2-2 Reactor Vessel Internals Summary of Aging Management Evaluation Table 3.1.2-2: Reactor Vessel Internals Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program Reactor vessel Structural Stainless Treated borated Cracking-TLAA -metal fatigue internals components support* steel, nickel water fatigue Flow alloy, CASS distribution Lower support Structural Stainless Treated borated Cracking Reactor Vessel structure assembly support steel water> 140°F Internals (P)
Core support plate Flow Neutron fluence Water Chemistry distribution Control -Primary and Secondary Lower support Structural Stainless Treated borated Loss of material Water Chemistry structure assembly support steel water> 140°F Control -Primary
Core support plate Flow Neutron fluence . and. Secondary distribution Lower support Structural Stainless Treated borated Change in Reactor Vessel structure assembly support steel water> 140°F dimension Internals (N)
Core support plate Flow Neutron fluence Lower support Structural Stainless Treated borated Reduction of Reactor Vessel structure assembly support steel water > 140°F fracture lnternais (P).
Core support plate Flow Neutron fluence toughness distribution 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV. 83. RP-339 3.1.1-3 A 83. RP-343 3.1.1-52a A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-365 3.1.1-56a A Page 3.1-57 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Reactor vessel Structural Stainless Treated borated internal connector support .steel water > 140°F components: Neutron fluence
Bolts
Studs *Nuts Structural Stainless Treated borated *Washers support steel water> 140°F
Locking bars Neutron fluence
Locking caps
Locking keys Structural
Stai.nless Treated borated *Dowels support steel water> 140°F *Cap screws Neutron fluence Structural Stainless Treated borated *support steel water> 140°F
Neu.tron fluence Structural Stainless Treated borated support steel water > 140°F Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Fuel alignment pins Neutron fluence Lower support Strucfural Stainless Treated borated structure assembly support steel water> 140°F
Fuel alignment pins Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals. (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vess.el Internals (N) Reduction of Reactor Vessel fracture Internals (N) Cracking Reactor Vessel* Internals (X) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control ....: Primary and Secondary Waterford Steam Electric l)tation, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A rv. B3. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-334 3.1.1-52c A IV.83.RP-24 3.1.1-87 A Page 3.1-58 Table 3.1.2-2: Reactor Vessel Internals Intended . Compor:ient Type Function Material Environment Lower support Structural Stainless Treated borated structure assembly support *steel . water> 140°F
Fuel alignment pins Neutron fluence Lower support Structural
Stainless Treated borated structure assembly support steel . water> 140°F
Fuel alignment pins Neutron fluence Low.er support Structural . Stainless Treated borated structure assembly support water> 140°F ,
Core support column . Neutron fluence welds lower support Structural Stainless Treated borated structure assembly support steel water> 140°F*
Core support column Neutron fluence welds Lower support Structural Stainless Treated borated structure assembly support steel water > 140°F
Core support column Neutron fluence welds Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management
Management Program Loss of material Reactor Vessel -wear Internals (X) Reduction of Reactor Vessel fracture Internals (X) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture internals (P) toughness Cracking Reactor Vessel Internals (E) .. .. Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information NU Table 1 1801 Item Item Notes IV. 83. RP-336 3.1.1-56c A IV. 83. RP-336 3.1.1-56c A IV.83.RP-363 A IV.83.RP-24 '3.1.1-87 A IV.83.RP-364 3.1.1-56a A IV. 83. 3.1.1-52b A Page 3.1"59 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper cylinder, Neutron fluence including welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of . Reactqr Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-335 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-331 3.1.1-56b c IV. 83. RP-329 3.1.1-52b A Page 3.1-60 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper cylinder, Neutron fluence including welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper cylinder, Neutron fluence including welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder axial Neutron fluence welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (P) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b c 362b IV.83.RP-3.1.1-52a A 362a IV.83.RP-24 3.1.1-87 A IV.83.RP-362 3.1.1-56a A IV.83.RP-3.1.1-52b A 362c Page 3.1-61 Table 3.1.2-2: Reactor Vessel Internals Intended 'Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower cylinder axial Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower cylinder axial Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange weld 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (X) Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b A 362b IV.83.RP-329 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-332 3.1.1-56c A IV. 83. RP-327 3.1.1-52a A Page 3.1-62 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower section flange Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys 3.0 Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Loss of material Water Chemistry
Control -*Primary and Secondary Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Loss of material Water Chemistry Control -Primary and Secondary Cracking Reactor Ves*sel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material
Water Chemistry Control -Primary and Secondary Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV. 83. RP-333 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-328 3.1.1-52a A IV.83.RP-24' 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A Page 3.1-63 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A Page 3.1-64 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment. Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Upper guide structure support plate assembly Upper internals Structural Stainless Treated borated assembly support steel water > 140°F
Upper guide structure support plate assembly 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vessel Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A . Page 3.1-65 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals Structural Stainless Treated borated assembly support steel water> 140°F .
Upper guide structure support plate assembly Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel *water> 140°F
Fuel alignment plate Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Reactor Vessel *-wear Internals (X) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Reduction of Reactor Vessel fracture Internals (N). toughness Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-332 3.1.1-56c c IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b . A Page 3.1-66 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core shroud assembly Structural Stainless Treated borated
Shroud vertical support steel water> 140°F plates Neutron fluence
Former plates
Axial and horizontal weld seams near the Structural Stainless Treated borated central flange and support steel water> 140°F horizontal stiffeners Neutron fluence Structural Stainless Treated borated support steel water> 140°F Neutron fluence Structural Stainless Treated borated support steel water> 140°F Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Change in Reactor Vessel dimension Internals (P) Reduction of Reactor Vessel fracture Internals (P) toughness Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-3.1.1-52a A 326a IV.83.RP-24 3.1.1-87 A IV. 83. RP-326 3.1.1-56a A IV. 83. RP-326 3.1.1-56a A Page 3.1-67 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Gore shroud assembly Structural Stainless Treated borated
Shroud vertical plate support steel water > 140°F to former plate axial Neutron fluence and horizontal weld seams in extended area around core Structural Stainless Treated borated *-midplane support steel water> 140°F Neutron fluence Structural* Stainless . Treated borated support steel water> 140.°F Neutron fluence Structural Stainless Treated borated support steel . water> 140°F Neutron fluence Core shroud assembly Structural Stainless Treated borated
Weld between upper support steel water> 140°F and lower vertical Neutron fluence ring sections Core shroud assembly Structural Stainless Treated borated
Weld between upper support steel water > 140°F .and lower vertical Neutron fluence ring sections 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals. (E) Water Chemistry Control -Primary ' and Secondary Loss of material Water Chemistry Control -Primary and Secondary Change in Reactor Vessel dimension Internals (E) Reduction of Reactor Vessel fracture Internals (P) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Seconda,.Y Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-*Table 1 1801 Item Item Notes IV.83.RP-323 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b c '359a IV. 83. RP-326 3.1.1-56a A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A .. Page .3.1-68 Table 3.1.2-2: Reactor Vessel Internals Intended Component tvpe Function Material Environment Core shroud assembly Structural Stainless Treated borated*
Weld between upper support steel water> 140°F and lower vertical Neutron fluence ring sections Core shroud assembly Structural Stainless Treated borated *
Weld between upper support steel water> 140°F and lower vertical
Neutron fluence ring sections Core shroud lug and Structural Stainless* Treated borated lug* inserts support steel water> 140°F fluence, ' Core shroud lug and Structural Stainless Treatedborated lug inserts supp.ort steel water> 140°F ' ,. Neutron fluence Core shroud lug and Structural Stainless Treated borated* lug inserts support steel water> 140°F Neutron* fluence Core shroud lug and Structural .Stainless Treated borated lug inserts support i;;teel water > 140°F Neutron fluence Core shroud lug and Structural Stainless Treated borated. lug inserts suppqrt steel water> 140°F Neutron fluence
3.0 Aging Management Review Results r' ) Aging Effect Aging Requiring Management Management.* Program. Change in Reactor Vessel dimension Internals (P) Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary toss of material Water Chemistry . Control -Primary and Secondary ,, . Loss of material Reactor Vessel -wear. Internals (X) *t*. Change in. Reactor Vessel dimension Internals (N) Loss of preload
Reactor Vessel Internals (X) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV. 83. RP-326 3.1.1-56a A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-319 3.1.1-56c A IV.83.RP-306 3.1.1-55b A IV.83.RP-319 3.1.1-56c A Page 3.1-69 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core shroud lug and Structural Stainless Treated borated lug inserts support. steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water> 140°F
Peripheral Neutron fluence instrument tubes 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (X) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (X) Change in Reactor Vessel dimension Internals (N) Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-306 3.1.1-55b A IV.83.RP-320 3.1.1-52c A IV.83.RP-24 3.1.1-87 A IV.83.RP-319 3.1.1-56c A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-312 3.1.1-52a A Page 3.1-70 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals CEA Structural Stainless Treated .borated shroud assembly suppqrt steel water > 140°F
Peripheral Neutron. fluence instrument tubes Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water> 140°F
Peripheral .. Neutron fluence instrument tubes Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water > 140°F
Non-peripheral Neutron-fluence instrument tubes Upper internals CEA Structural Stainless Treated .borated shroud assembly support steel water > t40°F
Non-peripheral Neutron fluence instrument tubes Upper internals CEA Structural Stainless . Treated borated shroud assembly support steel water>_ 140°F
Non-peripheral Neutron fluence instrument tubes Upper internals Flow* CASS(CF8 Treated borated assembly distribution Casting) water > 482°F
Flow bypass insert Neutron fluence assembly 3.0 Aging Management Review Results \._ Aging Effect Aging Requiring Manageme_nt Management Program Loss of material . Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel lntern*a1s (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary* Reduction of Reactor Vessel fracture Internals (N) toughness .. Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary \ . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-313 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A . Page 3.1-71 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals Flow CASS(CFB Treated borated assembly distribution Casting) water> 482°F
Flow bypass insert Neutron fluence assembly Upper internals Flow CASS(CFB Treated borated assembly distribution Casting) water> 482°F
Flow bypass insert Neutron fluence assembly Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness . Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of preload Reactor Vessel Internals (N) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A Page 3.1-72 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment CEA shroud assembly Structural CASS(ASTM Treated borated
Modified shroud ext. support
A351-72 water > 4S2°F shaft guide sub-Grade CFS) assembly
Extension shaft *guide CEA shroud assembly Structural CASS(ASTM Treated borated
Modified shroud ext. support A351-72 water > 4S2°F shaft guide sub-Grade CFS) assembly
Extension shaft guide CEA shroud assembly Structural CASS (ASTM Treatedbora.ted
Modified shroud ext. support A351-72 water > 4S2°F shaft guide sub-. Grade CFS) assembly
Extension shaft guide CEA .extension shaft Structural Stainless Treated borated guides support steel water> 140°F CEA extension shaft Structural Stainless Treated borated guides support steel water> 140°F 3.0 Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry . Control -Primary an*d Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -*Primary . and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-' Table 1 1801 Item Item Notes IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-S7 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-S7 A Page 3.1-73 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment CEA extension shaft Structural Treated borated guides support steel water> 140°F CEA shroud assembly Structural CASS (CPF8 Treated borated *Tube support 304 SS water > 482°F casting) Neutron fluence CEA shroud assembly Structural CASS(CPF8 Treated borated *Tube* support 304SS water > 482°F casting) Neutron fluence CEA shroud assembly Structural CASS(CPF8 Treated borated *Tube support 304 SS water> 482°F casting) Neutron fluence Holddown spring Structural Stainless Treated borated ' support steel water> 140°F *, Holddown spring Structural Stainless Treated borated support steel water> 140°F Holddown spring Structural Stainless Treated borated support steel water> 140°F Holddown spring Structural Stainless Treated borated support steel water> 140°F 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Program Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and *secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vessel Internals (N) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1ao11tem Item Notes IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A ' IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A .Page 3.1-74 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment lncore Instrumentation Structural Zircaloy Treated borated
Thimble -lower part support water > 140°.F Neutron fluence Reactor vessel Structural . Stainless Treated borated internal components support steel water > 140°F not addressed in Flow Neutron fluence* another line item distribution Reactor vessel Structural* Stainless Treated borated internal components support steel water> 140°F not addressed in Flow Neutron fluence another line item distribution Reactor vessel Structural Stainless Treated borated internal components support steel water > 140°F not addressed in Flow Neutron fl.uence another line item distribution Reactor vessel Structural Nickel alloy Treated borated internal components support water not addressed in Neutron fluence another line item Reactor vessel
Structural . Nickel alloy Treated borated internal components support water not addressed in Neutron fluence another line item .. 3.0 Aging Management Review Results I \ Aging Effect Aging Requiring Management Management Program Change in Reactor Vessel dimension Internals (X) Cracking Reactor Vessel
l,nternals (N) Water Chemistry Control --Primary and Secondary Loss of material Water Chemistry . Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----H IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A Page 3.1-75 Table 3.1.2-3 Reactor Coolant Pressure Boundary Summary of Aging Management Evaluation Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program .Bolting Pressure Carbon steel, Air-indoor Cracking -fatigue TLAA-metal boundary Stainless (ext) fatigue steel RCS pressure Pressure Carbon steel, T(eated borated Cracking -fatigue TLAA-metal boundary boundary Carbon steel water> 140°F fatigue components clad with (int) stainless steel, Carbon steel clad with nickel alloy, CASS, Nickel alloy, Stainless steel Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity bound.ary (ext) Boric Acid Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload* Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-18 3.1.1-5 A IV.C2.R-223 3.1.1-9 A IV.C2.RP-166 3.1.1-64 B IV.C2.RP-167 3.1.1-49 A IV.C2.R-12 3.1.1-66 B IV.C2.R-11 3.1.1-62 B *Page 3.1-76 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Bolting Pressure High strength Air-indoor boundary steel (ext) Bolting Pressure High strength Air-indoor boundary steel (ext) Bolting Pressure Stainless Air-indoor boundary steel (ext) Bolting Pressure Stainless Air-indoor boundary steel (ext) Flow element (non-Pressure Stainless Air-indoor Class 1) boundary steel (ext) Flow element (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Flow element (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Heat exchanger coil Pressure Copper alloy Lube oil (ext) (RCP lower oil boundary cooler) Heat exchanger coil Pressure Copper alloy Treated water (RCP lower oil boundary (int) cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Bolting Integrity Boric Acid Corrosion Loss of preload Bolting Integrity Cracking Bolting Integrity Loss of preload Bolting Integrity None None Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-166 3.1.1-64 B IV.C2.RP-167 3.1.1-49 A IV.C2.R-12 3.1.1-66 B IV.C2.R-11 3.1.1-62 B IV.C2.R-12 3.1.1-66 B IV.E.RP-04 3.1.1-107 A IV. C2. RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c Page 3.1-77 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger -Pressure Stainless Treated borated water jacket boundary steel water> 140°F (seal heat (ext) exchanger) Heat exchanger -Pressure Stainless Treated borated water jacket boundary steel water> 140°F (seal heat (ext) exchanger) Heat exchanger -Pressure Stainless Treated water water jacket boundary steel (int) (seal heat exchanger) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) (RCP upper oil cooler) Heat exchanger Pressure ' Carbon steel Treated water (channel head) boundary (int) (RCP upper oil cooler) Heat exchanger Pressure Carbon steel Air-indoor (shell) boundary (ext) (RCP upper oil cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-09 3.1.1-33 c IV.C2.RP-23 3.1.1-88 c V.A.EP-93 3.2.1-31 c Vll.F1.AP-41 3.3.1-80 c IV.C2.RP-221 3.1.1-89 c Vll.F1.AP-41 3.3.1-80 c Page 3.1-78 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel Lube oil (int) (shell) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Lube oil (int) (tube sheet) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Treated water (tube sheet) boundary (ext) (RCP upper oil cooler) Heat exchanger Pressure . Copper alloy Lube oil (ext) (tubes) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Air-indoor (tubes) boundary (ext) (RCP motor air cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Oil Analysis Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s Vll.H2.AP-131 3.3.1-98 C, 102 V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c V.F.EP-10 3.2.1-57 c Page 3.1-79 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) (RCP motor air cooler) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) (RCP motor air cooler) Heat exchanger Pressure Carbon steel Treated water (channel head) boundary (int) (RCP motor air cooler) Heat exchanger Pressure Copper alloy Air-indoor (tube sheet) boundary (ext) (RCP motor air cooler) Heat exchanger Pressure Copper alloy Treated water (tube sheet) boundary (int) (RCP motor air cooler) Orifice Pressure Nickel alloy Air-indoor boundary (Alloy 690) (ext) Flow control 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems None None Loss of material Water Chemistry Control -Closed Treated Water Systems None No.ne Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-222 3.1.1-90 c Vll.F1.AP-41 3.3.1-80 c IV.C2.RP-221 3.1.1-89 c V.F.EP-10 3.2.1-57 c IV.C2.RP-222 3.1.1-90 c IV.E.RP-03 3.1.1-106 A Page 3.1-80 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Orifice Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Flow control Orifice Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Flow control Orifice Pressure Stainless Air-indoor boundary steel (ext) Flow control Orifice Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Piping 4" NPS Pressure Carbon steel Air-indoor boundary clad with (ext) stainless steel Piping 4" NPS Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Nickel Alloy Inspection Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-30 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV. C2. RP-380 3.1.1-48 A IV.C2.R-30 3.1.1-33 A Page 3.1-81 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component type Function Material Environment Piping 4" NPS Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel Piping 4" NPS Pressure CASS Air-indoor boundary (ext) Piping 4" NPS Pressure CASS Treated borated boundary water (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 482°F (int) Piping < 4" NPS Pressure CASS Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Thermal Aging Embrittlement of CASS Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Thermal Aging fracture Embrittlement of toughness CASS None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1-88 A IV.C2.R-52 3.1.1-50 A IV.E.RP-04 3.1.1-107 A Page 3.1-82 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management Piping < 4" NPS Pressure CASS Treated borated Loss of material boundary water (int) Piping < 4" NPS Pressure CASS Treated borated Cracking boundary water> 140°F (int) Piping < 4" NPS Pressure CASS Treated borated Loss of material boundary water> 140°F (int) Piping < 4" NPS Pressure CASS Treated borated Reduction of boundary water> 482°F fracture (int) toughness Piping ;:: 4" NPS Pressure Stainless Air-indoor None boundary steel (ext) Piping ;:: 4" NPS Pressure Stainless . Treated borated Cracking boundary steel water> 140°F (int) Piping ;:: 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary lnservice Inspection Thermal Aging Embrittlement of CASS Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Thermal Aging Embrittlement of CASS None lnservice Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1-88 A IV.C2.R-52 3.1.1-50 A IV.E.RP-04 3.1.1-107 A IV.C2.R-30 3.1.1-33 A IV.C2.R-56 3.1.1-35 IV.C2.RP-23 3.1.1-88 A Page 3.1-83 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management Piping < 4" NPS Pressure Stainless Air-indoor None boundary steel (ext) Piping < 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water (int) Piping < 4" NPS Pressure Stainless Treated borated Cracking boundary steel water > 140°F (int) Piping < 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) Piping (non-Class 1) Pressure Stainless Air-indoor None boundary steel (ext) Piping (non-Class 1) Pressure Stainless Treated borated Loss of material boundary steel water (int) Piping (non-Class 1) Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Piping (non-Class 1) Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Management Program None Water Chemistry Control -Primary and Secondary lnservice Inspection One-Time Inspection -Small-Bore Piping Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.RP-235 3.1.1-39 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A V.A.EP-41 3.2.1-22 A, 101 IV.C2.RP-383 3.1.1-80 C, 101 V.A.EP-41 3.2.1-22 C, 101 Page 3.1-84 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Piping (non-Class 1) Pressure Copper alloy Air-indoor (RCP lower oil boundary > 15% Zn or (ext) cooler) >8%AI Piping (non-Class 1) Pressure Copper alloy Treated water (RCP lower oil boundary >15%Znor (int) cooler) >8%AI Piping (non-Class 1) Pressure Copper alloy Treated water (RCP lower oil boundary >15%Znor (int) cooler) >8%AI Piping (non-Class 1) Pressure Stainless Air-indoor RV flange leak off boundary steel (ext) lines Piping (non-Class 1) Pressure Stainless Treated borated RV flange leak off boundary steel water (int) lines Piping (non-Class 1) Pressure Stainless Treated borated RV flange leak off boundary steel water (int) lines Pressurizer heater Pressure Stainless Treated borated sheath boundary steel water > 140°F (ext) 3.0 Aging M*anagement Review Results Aging Effect Aging Requiring Management Management Program None None Loss of material Selective Leaching Loss of material Water Chemistry Control -Closed Treated Water Systems None None Cracking One-Time Inspection Loss of material One-Time Inspection Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s V.F.EP-10 3.2.1-57 c IV.C2.RP-12 3.1.1-93 A IV.C2.RP-222 3.1.1-90 A IV.E.RP-04 3.1.1-107 A IV.A2.R-74 3.1.1-19 E ----H IV.C2.R-217 3.1.1-33 A IV.C2.R-58 3.1.1-40 Page 3.1-85 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer heater Pressure Stainless Treated borated* sheath boundary steel water> 140°F (ext) Pressurizer heater Pressure Stainless Air-indoor sleeve end caps boundary steel (ext) Pressurizer heater Pressure Stainless Treated borated sleeve end caps boundary steel water> 140°F (int) Pressurizer heater Pressure Stainless Treated borated sleeve end caps boundary steel water> 140°F (int) Pressurizer heater Pressure Nickel alloy Air-indoor plug, heater sleeves boundary (Alloy 690) (ext) and heater sheath to sleeve welds PrE!ssurizer heater Pressure Nickel alloy Treated borated plug, heater sleeves boundary (Alloy 690) water (int) and heater sheath to sleeve welds Pressurizer heater Pressure Nickel alloy Treated borated plug, heater sleeves boundary (Alloy 690) water (int) and heater sheath to sleeve welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary an_d Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A Page 3.1-86 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer heater Structural Nickel alloy Treated borated internal support support water (ext) structure Pressurizer heater Structural Nickel alloy Treated borated internal support support water (ext) structure Pressurizer heater Structural Stainless Treated borated internal support support steel water> 140°F structure (int) Pressurizer heater Structural Stainless Treated borated internal support support steel water > 140°F structure (int) Pressurizer Pressure Nickel alloy Air-indoor instrument nozzle boundary (Alloy 690) (ext) Pressurizer Pressure Nickel alloy Treated borated instrument nozzle boundary (Alloy 690) water (int) Pressurizer Pressure Nickel alloy Treated borated instrument nozzle boundary (Alloy 690) water (int) Pressurizer lower Pressure Carbon steel Air-indoor head boundary clad with (ext) nickel alloy 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 A IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A Page 3.1-87 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer lower Pressure Carbon steel Treated borated head boundary clad with water (int) nickel ailoy Pressurizer lower Pressure . Carbon steel Treated borate.d head boundary clad with water (int) nickel alloy Pressurizer manway Pressure Carbon steel Air-indoor cover boundary (ext) Pressurizer manway Pressure Stainless Steam (int) gasket retainer plate boundary steel
Pressurizer manway Pressure Stainless Steam (int) gasket retainer plate boundary steel Pressurizer nozzles Pressure Carbon steel Air-indoor (spray nozzle, surge boundary clad with (ext) nozzle, safety stainless nozzle) st43el Pressurizer nozzles Pressure Carbon steel Treated borated (spray nozzle, surge boundary clad with water> 14.0°F' nozzle, safety .. stainless (int) nozzle) steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secon9ary Loss of material* Water Chemistry Control -Primary and Secondary .Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 -A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.)-40 Page 3.1-88 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer nozzles Pressure Carbon steel Treated borated (spray nozzle, surge boundary clad with water> 140°F
nozzle, safety stainless (int) nozzle) steel Pressurizer shell Pressure Carbon steel Air-indoor and upper head boundary clad with (ext) stainless steel Pressurizer shell Pressure Carbon steel Treated borated and upper head boundary clad with water> 140°F stainless (int) steel Pressurizer shell Pressure Carbon steel Treated borated and upper head boundary clad with water > 140°F stainless (int) steel Pressurizer spray Flow control Nickel alloy Treated borated head water (int) Pressurizer spray Flow control Nickel alloy Treated borated head water (int) Pressurizer support Structural Carbon steel Air-indoor skirt support (ext) Pressurizer support Structural Carbon steel Air-indoor skirt support (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A IV.C2.RP-40 3.1.1-82 A, 101 IV.C2.RP-23 3.1.1-88 A IV.C2.R-19 3.1.1-36 A IV.C2.R-17 3.1.1-49 A Page 3.1-89 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer welds -Pressure Nickel alloy Air-indoor instrument sleeve to boundary (Alloy 690) (ext) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pressurizer welds -Pressure Nickel alloy Treated borated instrument sleeve to boundary (Alloy 690) water (int) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pressurizer welds -Pressure Nickel alloy Treated borated instrument sleeve to boundary (Alloy 690) water (int) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pump casing Pressure CASS Air-indoor (RCP) boundary. (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-03 3.1:1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.U-107 A Page 3.1-90 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pump casing Pressure CASS Treated borated (RCP) boundary water> 140°F (int) Pump casing Pressure CASS Treated borated (RCP) boundary water> 140°F (int) Pump casing Pressure CASS Treated borated (RCP) boundary water> 482°F (int) Pump cover Pressure Carbon steel Air-indoor (RCP) boundary clad with (ext) stainless steel Pump cover Pressure Carbon steel Treated borated (RCP) boundary clad with water> 140°F stainless (int) steel Pump cover Pressure Carbon steel Treated borated (RCP) boundary clad with water> 140°F stainless (int) steel RCS cold leg welds Pressure Nickel alloy Air-indoor boundary (alloy 600) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary
Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
NUREG-1801 Table 1 Note Item Item s IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-08 3.1.1-38 A IV.C2.R-17 3.1.1-49 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A Page 3.1-91 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management RCS cold leg welds Pressure Nickel alloy Treated borated Cracking boundary (alloy 600) water (int) RCS cold leg welds Pressure Nickel alloy Treated borated Loss of material boundary (alloy 600) water (int) Safe end Pressure Stainless Air-indoor None (pressurizer spray, boundary steel (ext) drain, pressurizer instrument nozzles) Safe end Pressure
Stainless Treated borated Cracking (pressurizer spray, boundary steel water> 140°F drain, pressurizer (int) instrument nozzles) Safe end Pressure Stainless Treated borated Loss of material (pressurizer spray, boundary steel water> 140°F drain, pressurizer (int) instrument nozzles) 3.0 Aging Management Review Results Aging Management Program lnservice Inspection Nickel Alloy Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary None lnservice Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-159 3.1.1-45 A IV.C2.RP-23 3.1:1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A Page 3.1-92 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material .Environment Safe end Pressure CASS Air -indoor. (hot leg and (ext) pressurizer surge, shutdown cooling and pressurizer safety) Safe end Pressure CASS Treated borated (hot leg and boundary water > 140°F pressurizer surge, (int) shutdown cooling and pressurizer safety) '* Safe end Pressure CASS Treated borated' (hot leg and boundary > 140°F (int). pressurizer surge, shutdown cooling and pressurizer safety) Safe end Pressure CASS Treated borated* (hot leg and boundary water :> 482°F pres'st1rizer (int) shutdown cooling and pressurizer '. safety) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None ' Cracking .lnservice Inspection Thermal Aging Embrittleinent of CASS Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary ' . and Se96ndary ' Reduction of Thermal Aging fracture Embrittlement of toughness CASS ,. Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-04 3.1.1-107 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1,-88 A IV.C2.R-52 3.1.1-50 A Page 3.1-93 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Thermal sleeve Structural Nickel alloy Treated borated (charging, SI, surge, integrity water (int) pressurizer spray) Thermal sleeve Structural Nickel alloy Treated borated (charging, SI, surge, integrity water (int) pressurizer spray) Thermowell Pressure Nickel alloy Air-indoor boundary (Alloy 690) (ext) Thermowell Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Thermowell Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubing (non-Class Pressure Stainless Air-indoor 1) boundary steel (ext) Tubing (non-Class Pressure Stainless Treated borated 1) boundary steel water (int) Tubing (non-Class Pressure Stainless Treated borated 1) boundary steel water> 140°F (int) Tubing (non-Class Pressure Stainless Treated borated 1) bound.ary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry ,.. Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-159 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A Page 3.1-94 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component ,Type Function Material Environment
Valve body NPS Pressure CASS Air-indoor boundary (ext) Valve body NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body NPS Pressure CASS Treated borated boundary water> 482°F (int) Valve body NPS Pressure Stainless Air-indoor boundary steel (ext) Valve body NPS Pressure Stainless* Steam (int) boundary steel Valve body NPS Pressure Stainless Steam (int) boundary steel Valve body NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Cracking lnservice Inspection . Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking ' lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item . Item s IV.E.RP-04 3.1.1-107 A \ IV.C2.R-09 3.1.1-33 A --IV.C2.RP-23 3.1.1-88 A IV.C2.R-08 . 3.1.1-38 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-09 3.1.1-33 A Page 3.1-95 Table 3.1.2-3: Reactor Coolant Pressure Boundary ' Intended Component Type Function Material Environment Valve body <::4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body <4" NPS Pressure CASS Air-indoor boundary (ext) Valve body <4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body <4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body <4" NPS Pressure CASS Treated borated boundary water> 482°F (int) Valve body <4" NPS Pressure Stainless Air-indoor boundary steel (ext) Valve body <4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body <4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body (non-Pressure CASS Air-indoor Class 1) boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A 3.1.1-88 A IV.C2.R-08 3.1.1-38 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A Page 3.1-96 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Valve body (non-Pressure CASS Treated borated Class 1) boundary water> 140°F (int) Valve body (non-Pressure CASS Treated borated Class 1) boundary water > 140°F (int) Valve body (non-Pressure Stainless Air -*indoor Class 1) boundary steel (ext) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water (int) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s V.A.E-12 3.2.1-20 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A V.A.EP-41 3.2.1-22 A, 101 IV.C2.RP-383 3.1.1-80 C, 101 V.A.EP-41 3.2.1-22 C, 101 Page 3.1-97 Table 3.1.2-4: Steam Generators Intended Component Type Function Steam generator Pressure components boundary Steam generator Pressure components boundary 3.0 Aging Management Review Results Table 3.1.2-4 Steam Generators Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Material Environment Management Program Carbon steel, Air-indoor Cracking -fatigue TLAA-metal stainless (ext) fatigue steel, nickel alloy (Alloy 690), carbon steel clad with stainless steel, carbon steel clad
with nickel alloy (Alloy 690) Carbon steel, Treated borated Cracking -fatigue TLAA-metal stainless water> 140°F fatigue steel, nickel (int) alloy (Alloy 690), carbon steel clad with stainless steel, carbon steel clad with nickel alloy (Alloy 690) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.R-18 3.1.1-5 c IV.D1 .R-221 3.1.1-8 A 'IV.01 .R-46 3.1.1-2 Page 3.1-98 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Steam generator Pressure Carbon steel, Treated water > components boundary stainless 140°F (int) steel, nickel alloy (Alloy 690) Pressure boundary Pressure Carbon steel Air-indoor closure bolting boundary (ext) Pressure boundary Pressure Carbon steel Air-indoor closure bolting boundary (ext) Tubesheet Pressure Carbon steel Air-indoor boundary clad with (ext) nickel alloy (Alloy 690) Tubesheet Pressure Carbon steel Treated borated boundary clad with water (int) nickel alloy (Alloy 690) Tubesheet Pressure Carbon steel Treated borated boundary clad with water (int) nickel alloy (Alloy 690) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking -fatigue TLAA-metal fatigue Loss of material Bolting Integrity Boric Acid Corrosion Loss of preload Bolting Integrity Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.R-33 3.1.1-5 A 'IV.01 .R-46 3.1.1-2 IV.C2.RP-166 3.1.1-64 D IV.C2.RP-167 3.1.1-49 c IV.01 .RP-46 3.1.1-67 B IV.01.R-17 3.1.1-49 A IV.01 .RP-36 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 c Page 3.1-99 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tubesheet Pressure Carbon steel Treated water boundary clad with (int) nickel alloy (Alloy 690) Tube to tubesheet Pressure Nickel alloy Treated borated weld boundary (Alloy 690) water Tube to tubesheet Pressure Nickel alloy Treated borated weld boundary (Alloy 690) water Channel head Pressure Carbon steel Air-indoor boundary . clad with (ext) stainless steel or nickel alloy (Alloy 690) Channel head Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel or nickel alloy (Alloy 690) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking In service Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-372 3.1.1-83 C, 101 IV.01 .RP-385 3.1.1-25 A IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 c Page 3.1-100 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Channel head Pressure Carbon steel Treated borated boundary clad with water > 140°F stainless (int) steel or nickel alloy (Alloy 690) Partition plate Pressure Nickel alloy Treated borated boundary (Alloy 690) water Partition plate Pressure Nickel alloy Treated borated boundary (Alloy 690) water Primary inlet and Pressure Carbon steel Air-indoor outlet nozzle boundary clad with (ext) transition pieces stainless steel Primary inlet and Pressure Carbon steel Treated borated outlet nozzle boundary clad with water> 140°F transition pieces stainless (int) steel Primary inlet and Pressure Carbon steel Treated borated outlet nozzle boundary clad with water> 140°F transition pieces stainless (int) steel Primary side Pressure Nickel alloy Air-indoor pressure nozzle boundary (Alloy 690) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -*Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.RP-23 3.1.1-88 c IV.01 .RP-367 3.1.1-25 A IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A IV.01 .RP-232 3.1.1-33 A IV.C2.RP-23 3.1.1-88 c IV.E.RP-378 3.1.1-106 A Page 3.1-101 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary side Pressure Nickel alloy Treated borated pressure nozzle boundary (Alloy 690) water (int) Primary side Pressure Nickel alloy Treated borated pressure nozzle boundary (Alloy 690) water (int) Inlet and outlet Pressure Nickel alloy Treated borated nozzle dam rings boundary (Alloy 690) water Inlet and outlet Pressure Nickel alloy Treated borated nozzle dam rings boundary (Alloy 690) water Primary manway Pressure Stainless Treated borated drain tube boundary steel water> 140°F Primary manway Pressure Stainless Treated borated drain tube boundary steel water> 140°F Primary manway Pressure Carbon steel Air-:--indoor cover boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking In service Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.RP-36 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 c IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 c IV.01 .RP-232 3.1.1-33 c IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A Page3.1-102 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary manway Pressure Stainless Treated borated insert boundary steel water> 140°F (int) Primary manway Pressure Stainless Treated borated insert boundary steel water> 140°F (int) Tubes Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubes Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 c IV.01.R-44 3.1.1-70 A IV.C2.RP-23 3.1.1-88 c IV.01.R-47 3.1.1-69 A IV.01 .RP-226 3.1.1-71 c IV.01 .RP-233 3.1.1-77 A Page 3.1-103 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tubes Heat transfer Nickel alloy Treated borated (Alloy 690) water (int) Tubes Heat transfer Nickel alloy Treated water (Alloy 690) (ext) Tube plugs Pressure Nickel alloy Treated borated boundary (Alloy 690) water Tube plugs Pressure Nickel alloy Treated borated boundary (Alloy 690) water Secondary shell Pressure Carbon steel Air-indoor (elliptical head with boundary (ext) integral steam nozzle, upper, intermediate and lower shells, transition cone) Secondary shell Pressure Carbon steel Treated water (elliptical head with boundary (int) integral steam nozzle, upper, intermediate and lower shells, transition cone) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material In service Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes --H ----H IV.01.R-40 3.1.1-70 A IV.C2.RP-23 3.1.1-88 c ----G, 105 IV.01.RP-368 3.1.1-12 A Page 3.1-104 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Flow limiter insert Flow control Nickel alloy Treated water (Alloy 690) Flow limiter insert Flow control
Nickel alloy Treated water (Alloy 690) Feedwater nozzle Pressure Carbon steel Air-indoor boundary (ext) Feedwater nozzle Pressure Carbon steel Treated water boundary (int) Feedwater nozzle Pressure Nickel alloy Treated water thermal sleeve boundary (Alloy 690) Feedwater nozzle Pressure Nickel alloy Treated water thermal sleeve boundary (Alloy690) Instrument and Pressure Carbon steel Air-indoor sampling nozzles boundary (ext) Instrument and Pressure Carbon steel Treated water sampling nozzles boundary (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D2.R-36 3.1.1-78 C, 101 Vlll.81.SP-157 3.4.1-16 C, 101 ----G, 105 IV.01 .RP-368 3.1.1-12 c IV.02.R-36 3.1.1-78 C, 101 Vlll.81 .SP-157 3.4.1-16 C, 101 ----G, 105 IV.01 .RP-368 3.1.1-12 c Page 3.1-105 Table 3.1.2-4: Steam Generators Aging Effect Intended Requiring Component Type Function Material Environment Management. Slowdown nozzle. Pressure Carbon steel Air-indoor None boundary (ext) Slowdown nozzle Pressure Carbon steel Treated water Loss of material boundary (int) Slowdown nozzle Pressure Carbon steel Treated water Loss of material -boundary (int) FAG Secondary manway, Pressure Carbon steel Air-indoor None handhole, inspection boun.dary (ext) .. port, and recirculation nozzles Secondary manway, Pressure Carbon steel Treated water Loss of material handhole, inspection boundary (int) port, and recirculation nozzles Secondary manway, Pressure Carbon steel Air-indoor None handhole, inspection boundary (ext) port, and recirculation nozzle cover plates 3.0 Aging Management Review Results Aging Management Program None lnservice Inspection Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion None lnservice Inspection Water Chemistry Control -:-Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes ----G, 105 IV.01.RP-368 3.1.1-12 c IV.01.R-37 3.1.1-61 c ---G, 105 IV.01 .RP-368 3.1.1-12 c ----G, 105 Page 3.1-106 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Secondary manway, Pressure Carbon steel Treated water handhole, inspection boundary (int) port, and recirculation nozzle cover plates Secondary manway, Pressure Carbon steel Treated water handhole, inspection boundary (int) port, and recirculation nozzle cover plates Handhole and Pres.sure Carbon steel Air-indoor inspection port (with boundary (ext) seal welded diaphragms) cover plates Handhole and Pressure Nickel alloy Air-indoor inspection port boundary (Alloy 690) (ext) diaphragms Handhole and Pressure Nickel alloy Treated water inspection port boundary (Alloy 690) diaphragms Handhole and Pressure Nickel alloy Treated water inspection port boundary (Alloy 690) diaphragms External shell Pressure Carbon steel Air -indoor attachments boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material -lnservice erosion Inspection None None None None Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.RP-368 3.1.1-12 c IV.02.R-31 3.1.1-44 c ----G, 105 IV.E.RP-03 3.1.1-106 A IV.02.R-36 3.1.1-78 C, 101 Vlll.81.SP-157 3.4.1-16 C, 101 ----G, 105 Page 3.1-107 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Wrapper barrel, Structural Carbon steel Treated water associated integrity components Recirculation nozzle Structural Nickel alloy Treated water sleeve, wrapper integrity (Alloy 690) plug seal plates 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-384 3.1.1-71 A IV.01 .RP-226 3.1.1-71 A IV.01 .RP-225 3.1.1-76 A IV.01.RP-161 3.1.1-72 A IV.01 .RP-384 3.1.1-71 c Page 3.1-108 Table 3.1.2-4: Steam Generators Intended Component Type Function Material* Environment Recirculation nozzle Structural Nickel alloy Treated water sleeve, wrapper integrity (Alloy 690) plug seal plates Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim 3.0 Aging Management Review Results ( Aging Effect Aging Requiring . Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D1 .RP-226 3.1.1-71 c IV.01 .RP-384 3.1.1-71 A IV.01 .RP-226 3.1.1-71 A IV.D1 .RP-225 3.1.1-76 A Page 3.1-109 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Stayrods, wedges, Structural Carbon steel Treated water tube support integrity components Stayrods, wedges, Structural Carbon steel Treated water tube support integrity components Feedwater header Structural Carbon steel Treated water and support integrity components Feedwater spray Structural Nickel alloy Treated water nozzles, nozzle integrity (Alloy 690) caps, filler plates Feedwater spray Structural Nickel alloy Treated water nozzles, nozzle integrity (Alloy 690) caps, filler plates 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-226 3.1.1-71 A IV.01.RP-225 3.1.1-76 A IV.01.RP-226 3.1.1-71 c IV.01 .RP-384 3.1.1-71 c IV.01 .RP-226 3.1.1-71 c Page 3.1-110 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary separator Structural Carbon steel Treated water assembly integrity components Drain bucket Structural Stainless Treated water assembly integrity steel > 140°F components Drain bucket Structural Stainless Treated water assembly integrity steel > 140°F . components Lower deck Structural Carbon steel Treated water components integrity Middle deck Structural Carbon steel Treated water components integrity 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D1 .RP-226 3.1.1-71 c IV.D1 .RP-384 3.1.1-71 c IV.D1 .RP-226 3.1.1-71 c IV.D1.RP-226 3.1.1-71 c IV.D1.RP-226 ,3.1.1-71 c Page 3.1-111 Table 3.1.2-4: Steam Generators Aging Effect Intended Requiring Component Type Function Material Environment Management Sludge collector Structural Carbon steel Treated water Loss of material assembly integrity Secondary Structural Carbon steel Treated water Loss of material separator integrity components Pedestal support Structural Carbon steel Air-indoor Loss of material support (ext) Snubber lug, key Structural Carbon steel Air-indoor None bracket support (ext) 3.0 Aging Management Review Results Aging Management Program Steam Generator Integrity Water Chemistry Control -Primary and Secondary Steam Generator Integrity Water Chemistry Control -Primary and Secondary Boric Acid Corrosion None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-226 3.1.1-71 c IV.01.RP-226 3.1.1-71 c IV.01.R-17 3.1.1-49 A . ----G, 105
Page 3.1-112 Table 3.1.2-5-1 Reactor Coolant System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related* systems Summary of Aging Management Evaluation Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity IV.C2.R-12 3.1.1-66 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity IV.C2.RP-166 3.1.1-64 B boundary (ext} Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.RP-167 3.1.1-49 A boundary (ext) Corrosion Filter housing Pressure Aluminum Air-indoor None None V.F.EP-3 3.2.1-56 c boundary (ext) Filter housing Pressure Aluminum Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-162 3.3.1-99 C, 102 boundary Filter housing Pressure steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Filter housing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Flex hose Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Flex hose Pressure Stainless Lube oil (int) Loss of material Oil Analysis V.01.EP-80 3.2.1-50 C, 102 boundary steel Orifice Pressure Stainless Air-indoor None ". None IV.E.RP-04 3.1.1-107 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.1-113 )

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging* Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Orifice Pressure Stainless Lube oil (int) Loss of material Oil Analysis V.01.EP-80 3.2.1-50 C, 102 boundary steel Piping Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Piping Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary

Piping Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion 3.0 Aging Management Review Results Page 3.1-114 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Pump casing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Rupture disc Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Rupture disc Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Rupture disc Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Sight glass Pressure Glass Air-indoor None None V.F.EP-15 3.2.1-60 c boundary (ext) Sight glass Pressure Glass Treated borated None None V.F.EP-30 3.2.1-60 c boundary water (int) Sight glass Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Sight glass Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary. steel water> 140°F Control -Primary (int) and Secondary Sight glass Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Strainer housing Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion 3.0 Aging Management Review Results Page 3.1-115 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Strainer housing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Strainer housing Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Strainer housing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 c boundary steel (ext) Tank Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Tubing Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary water> 140°F Control -: Primary (int) and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.1-116 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Valve body Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Valve body Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.1-117 Table 3.1.2-5-2 Steam Generators Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.1.2-6: Steam Generators, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring . Management NUREG-1801 Table 1 Component Type Function .. Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity IV.01 .RP-46 3.1.1-67 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity IV.C2.RP-166 3.1.1-64 D boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.1-118 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.2 ENGINEERED SAFETY FEATURES 3.2, 1 Introduction This section provides the results of the aging management reviews for components in the ESF systems that are subject to aging management review. The following systems are addressed in this section (system descriptions are available in the referenced sections).
Containment Spray (Section 2.3.2.1)
Safety Injection (Section 2.3.2.2)
Containment Penetrations (Section 2.3.2.3)
ESF Systems in Scope for 10 CFR 54.4(a)(2) (Section 2.3.2.4) Table 3.2.1, Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the engineered safety features component groups. This table uses the format described in the introdu.ction to Section 3. Hyperlinks are provided to the program evaluations in
Appendix B. 3.2.2 Results The following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for systems in the ESF system group.
Table 3.2.2-1 Containment Spray System-Summary of Aging Management Evaluation
Table 3.2.2-2 Safety Injection Systerh---Summary of Aging Management Evaluation
Table 3.2.2-3 Containment Penetrations-Summary of Aging Management Evaluation ESF Systems in Scope for*10 CFR 54.4(a)(2)
Table 3.2.2-4-1 Containment Spray System;*Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation
Table 3.2.2-4-2 Safety Injection System, Nonsafety-Relc;1ted Con:iponents Affecting Safefy-Related Systems-Summary of Aging Management Evaluation 3.2.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the ESF systems. Programs are described in Appendix B. Further details are provided in the system tables.
3.0 Aging Management Review Results Page 3.2-1 _

3.2.2.1.1 Containment Spray Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment spray system components are constructed of the following materials. * *

Carbon steel Carbon steel clad with stainless steel Carbon steel with internal coating Stainless steel Environments Containment spray system components are exposed to the following environments.
Air -indoor
Lube oil
Treated borated water
Treated borated water> 140°F _
Treated water Aging Effects Requiring Management The following aging effects associated with the containment spray system require management. *
* * *
Cracking Cracking -fatigue Loss of coating integrity Loss of material Los;s of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the effects of aging on the containment spray system components. * * * * *
Bolting Integrity Boric Acid Corrosion Coating Integrity External Surfaces Monitoring Oil Analysis One-Time Inspection 3.0 Aging Management Review Results Page 3.2-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.2.2.1.2 Safety Injection Materials* Safety injection system components are constructed of the following materials.
Carbon steel
Carbon steel clad with stainless steel
Carbon steel with internal coating
High strength steel
Nickei alloy
Stainless steel Environments Safety injection system components are exposed to the following environments.
Air -indoor
Gas
Treated borated water * *Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects .associated with the safety injection system require management. * * * * *
Cracking Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results Page 3.2-3 Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Aging Management Programs The following aging management programs manage the effects of aging on the safety injection system components. * * * * * *
Bolting Integrity Boric Acid Corrosion Coating Integrity External Surfaces Monitoring One-Time I nspectiori Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.2.2.1.3 Containment Penetrations Materials Containment penetrations components are constructed of the following materials.
Carbon steel
Stainless steel Environments Containment penetrations components are exposed to the following environments.
Air -indoor
Treated borated water
Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects associated with the containment penetrations require management.
Cracking
Cracking -fatigue
Loss of material
Loss of preload 3.0 Aging Management Review Results Page 3.2-4 Waterford Steam Electric Station, Unit 3 /. License Renewal Application (, Technical Information Aging Management Programs The following aging management programs manage the effects of aging on the containment penetrations components.
Bolting Integrity
External Surfaces Monitoring
One-Time Inspection * . Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.2.2.1.4 ESF Systems in Scope for 1 O CFR 54.4CalC2) The following lists encompass materials, envrronments, aging effects requiring management, and aging management programs for the series 3.2.2-4-x tables. Materials Nonsafety-related components affecting safety-related systems are constructed of the following materials. *
Carbon steel
Staf nless steel Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments.
Air -indoor
Treated borated water
Waste water Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. *
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the effects of aging on nonsafety-related components affecting safety-related systems. 3.0 Aging Management Review Results Page 3.2-5

( Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information * *

*
Bolting Integrity Boric Acid Corrosion Internal Surfaces in Piping andDucting Components One-Time Inspection Water Chemistry Control -Primary and Secondary 3.2.2.2 Further Evaluation of Aging Management as Recommended _by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.2.2.2 of NUREG-1800. The following sections are numbered in. accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further evaluation. Programs are described in Appendix B. 3.2.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management, the analysis of fatigue is a TLAA as defined in 10 CFR 54.3. _ TLAAs are evaluated in accordance with 1*0 CFR 54.21 (c). Evaluation of this TLAA is addressed in Section 4.3. 3.2.2.2.2 Loss of Material due to Cladding [Breach] This paragraph in NUREG-1800 pertains to steel charging pump casings with stainless steer cladding .. Loss of material could occur for the steel casing material if exposed to treated borated water due to a cladding breach. The WF3 safety injection system pump.s have solid stainless steel casings.
3.2.2.2.3 Loss of Material due to Pitting and Crevice Corrosion 1. This paragraph in NUREG-1800 pertains to loss of material. due to pitting and crevice corrosion in partially encased stainless steel tanks exposed to raw water due to cracking of the perimeter seal from weathering. At WF3, ESF system tanks included in the scope of license renewal are located indoors. There are no stainless steel tanks exposed to raw water in the ESF systems. 2. Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping components, piping elements, and tanks exposed to outdoor air, .including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including.chemical manufacturers. Chloride contamination of components exposed to outdoot air may However, at WF3 there are no ESF system components exposed to outdoor air in the scope of license renewal. At WF3, there are no stainless steel ESF system components located indoors near unducted air intakes. 3.0 Aging Management Review Results Page 3.2-6 3.2.2.2.4 Loss of Material due to Erosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Loss of material due to erosion could occur in the stainless steel pump miniflow recirculation orifice of a high-pressure safety injection (HPSI) pump used for normal char!;ling. The HPSI pumps at WF3 are not used for normal charging. 3.2.2.2.5* Loss of Material due to General Corrosion and Fouling that Leads to Corrosion This paragraph in NUREG-1800 applies to 8WRs only. 3.2.2.2.6 . Cracking due to Stress* Corrosion Cracking
Cracking due to stress. corrosion cracking could occur for stainless steel piping, piping components, piping elements and tanks exposed to outdoor air, including air which ha.s recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. However, at WF3 *_there are no ESF system components exposed to outdoor air in the scope of license renewal. At WF3, there are no stainless steel ESF system components located indoors near unducted air intakes. 3.2.2.2.7 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix 8 Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.2.2.2.8 Ongoing Review of Operating Experience Se.e Appendix 8 Section 8.0.4 for discussion of WF3 operating experience review programs. 3.2.2.2.9 Loss of Material due to Recu,rring Internal Corrosion A review of 1 O years of plant operating experience identified no conditions of recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in the piping components of the engineered safety features systems in the scope of license renewal. *
3.2.2.3 Time-Limited Ag_il')g.Analyses The only time-limited aging analysis identified for ttie ESF systems components is metal fatigue. This is evaluated in Section 4.3.
3.2.3 Conclusion The ESF system components that are subject to aging management review have been identified in accordance with the requirements of 1 O CFR 54.21. The aging management programs 3.0 Aging Management Review Results Page 3.2-7 \ ,I Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information selected to manage the effects of aging on ESF components are identified in Section 3.2.2.1 and in the following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the ESF components will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.2-8 Table 3.2.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801 Table 3.2.1: Engineered Safety Features Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-1 Stainless steel, steel piping, Cumulative fatigue Fatigue is a time-limited Yes, TLAA Fatigue is a TLAA. piping components, and damage due to aging analysis (TLAA) to be. piping elements exposed to fatigue evaluated for the period of See Sectio"n 3.2.2.2.1. treated water (borated) extended operation: See theSRP, Section 4.3 "Metal Fatigue," for acceptable methods for meeting the requirements of 10 CFR 54.21 (c)(1 ). 3.2.1-2 Steel (with stainless steel Loss of material due A plant-specific aging Yes, verify that The WF3 safety injection system cladding) pump casings to cladding breach management program is to plant-specific pump casings are solid stainless exposed to treated water be evaluated Reference program steel. (borated) NRG Information Notice 94-addresses clad 63, "Boric Acid Corrosion-of breach See Section 3.2.2.2.2. Charging Pump Casings Caused by Cladding Cracks." 3.0 Aging Management Review Results Page 3.2-9 /

Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-3 Stainless steel partially-Loss of material due encased tanks with to pitting and crevice breached moisture barrier corrosion exposed to raw water 3.2.1-4 Stainless steel piping, piping Loss of material due components, and piping to pitting and crevice elements; tanks exposed to corrosion Air -outdoor 3.2.1-5 Stainless steel orifice Loss of material due (miniflow recirculation) to erosion exposed to treated water (borated) 3.2.1-6 BWRonly 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated for pitting and crevice corrosion of tank bottom because moisture and water can egress under the tank due to cracking of the perimeter seal from weathering. Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" A plant-specific aging management program is to be evaluated for erosion of the orifice due to extended use of the centrifugal HPSI pump for normal charging. See LER 50-275/94-023 for evidence of erosion. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-There are no stainless steel specific tanks exposed to raw water in the EFW systems in the scope of license renewal. See Section 3.2.2.2.3, Item 1. Yes, There are no ESF syster:n environmental components exposed to outdoor conditions need to air in the scope of license be evaluated renewal. See Section 3.2.2.2.3, Item 2. Yes, plant-The WF3 HPSI pumps are not specific used for normal charging. See Section 3.2.2.2.4. Page 3.2-10 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component 3.2.1-7 Stainless steel piping, piping Cracking due to components, and piping stress corrosion elements; tanks exposed to cracking air -outdoor. 3.2.1-8 Aluminum, copper alloy Loss of material due {> 15% Zn or >8% Al) piping, to boric acid piping components, and corrosion piping elements exposed to air with borated water leakage 3.2.1-9 Steel external surfaces, Loss. of due bolting exposed to air with to boric acid borated water leakage corrosion 3.2.1-10 Cast austenitic stainless Loss of fracture steel piping, piping toughness due to components, and piping thermal aging elements exposed to treated embrittlement . water (borated) >250°C (>482°F), treated water >250°C {>482°F) 3.2.1-11 BWRonly 3.0 Aging Management Review Results Aging Management Programs_ Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M10, "Boric

Acid Corrosion" Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)" Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, There are no ESF system environmental components exposed to outdoor conditions need to air in the scope of license be evaluated renewal. See Section 3.2.2.2.6. No There are no aluminum or copper alloy ESF components exposed to air with borated water leakage, in the scope of license renewal. No* Consistent with NUREG-1801. Loss of material for steel external sur:faces and bolting exposed to air with borated water leakage is managed by the Boric Acid Corrosion Program. No There are no CASS components exposed to water > 482°F in the ESF systems. Page 3.2-11 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-12 Steel, high-strength closure Cracking due to bolting exposed to air with cyclic loading, stress steam or water leakage corrosion cracking 3.2.1-13 Steel; stainless steel bolting, Loss of material due closure bolting exposed to to general (steel air-outdoor (external), air-only), pitting, and indoor, uncontrolled crevice corrosi,on (external) 3.2.1-14 Steel closure bolting Loss of material due exposed to air with steam or to general corrosion water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of high strength steel bolting exposed to air with steam or water leakage is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Loss of material for steel closure bolting exposed to indoor air is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, the Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. No As stated in Item Number 3.2.1-13, loss of material of steel
bolting exposed to air in the ESF systems is managed by the Bolting Integrity Program. However, steam or water leakage is not considered as a separate aspect of the indoor air environment. Page 3.2-12 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.2.1-15 Copper alloy, nickel alloy, Loss of preload due Chapter Xl.M18, "Bolting steel; stainless steel, to thermal effects, Integrity" stainless steel, steel; gasket creep, and stainless steel bolting, self-loosening closure bolting exposed to any environment, air -outdoor (external), raw water, treated borated water, fuel oil, treated water, air -indoor, uncontrolled < (external) 3.2.1-16 Steel containment isolation Loss of material due Chapter Xl.M2, "Water piping and components to general, pitting, . Chemistry," and Chapter (internal surfaces), piping, and crevice corrosion Xl.M32, "One-Time piping components, and
Inspection" piping elements exposed *to treated water ' 3.2.1-17 BWRonly 3.0 Aging Management Review Results ---"" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Lqss of preload for steel and stainless steel bolting is managed by the Bolting Integrity Program. There is no copper alloy or nickel alloy bolting included in the scope of license renewal for ESF systems. No Loss of material for steel containment isolation
components exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. However, these steel containment isolation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. Page 3.2-13 Waterford Steam Electric Station, Unit 3 , License Renewal Application Technical Information Table 3.2.1: Engineered Safety Features Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-18 Stainless steel containment Loss of material due Chapter Xl.M2, "Water No Loss of material for stainless isolation piping and to pitting and crevice Chemistry," and Chapter steel components exposed to components (internal corrosion Xl.M32, "One-Time treated water is managed by the surfaces) exposed to treated Inspection" Water Chemistry Control -water Primary and Secondary Program. The One-Time Inspection Program will verify . the effectiveness of the water .. chemistry control program to manage loss of material. However, these stainless steel containment isolation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. 3.2.1-19 Stainless steel heat Reduction of heat Chapter Xl.M2, "Water No Consistent with NUREG-1801. exchanger tubes exposed to transfer due to Chemistry," and Chapter Reduction of heat transfer for treated water, treated water fouling Xl.M32, "One-Time stainless steel heat exchanger (borated) Inspection" tubes exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time ' Inspection Program will verify the effectiveness of the water chemistry control program to manage reduction. of heat , transfer. 3.0 Aging Management Review Results Page 3.2-14 Table 3.2.1: Engineered Safety Features Item Number Component 3.2.1-20 Stainless steel piping, piping . components, and piping elements; tanks exposed to treated water >60°C (>140°F) 3.2.1-21 Steel (with stainless steel or, nickel-alloy cladding) safety injection tank (accumulator) exposed to treated water (borated) >60°C {>140°F) 3.2.1-22 Stainless steel piping, piping components, and piping elements; tanks exposed to treated water (borated) ,. 3.0 Aging Management Review Results / \ Aging Effect/ Mechanism Cracking due to stress corrosion cracking ' Cracking due to stress corrosion cracking Loss of material due t6 pitting and crevice corrosion Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless steel components exposed to treated borated water >140°F is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. No The WF3 safety injection tanks are maintained at containment ambient conditions (<140°F). . No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. Page 3.2-15 (

Table 3.2.1: Safety Item . Aging Effect/ Number Component

Mechanism 3.2.1-23 Steel heat exchanger Loss of material due conipohents, containment to general, pitting, isolation piping and crevice, and components (internal microbiologically surfaces) exposed to raw influenced corrosion; water fouling that leads to corrosion 3.2.1-24 Stainless steel piping, piping Loss of material due components, and piping to pitting, crevice, elements exposed to raw and water microbiologically-*influenced corrosion 3.2.1-25 Stainless steel heat Loss of material due exchanger components, to pitting, crevice, containment isolation piping and microbiologically and components (internal influenced corrosion; surfaces) exposed to raw fouling that leads to water corrosion 3.2.1-26 BWR.only 3.2.1-27 Stainless steel, steel heat Reduction of heat exchanger tubes exposed to transfer due to raw water fouling *' 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-. Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no steel ESF components exposed to raw water in the scope of license renewal. No There are no stainless steel ESF components exposed to raw water in the scope of license renewal. No There are nc;> stainless steel ESF components exposed to raw . water in the scope *ot license renewal. No There are no steel or stainless steel ESF components exposed to raw water in the scope of license renewal. Page 3.2-16 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management. Number Component Mechanism Progr;;ams 3.2.1-28 Stainless steel piping, piping Cracking due to Chapter Xl.M21A, "Closed components, and piping stress corrosion Treated Water Systems" elements exposed to closed-cracking cycle cooling water >60°C {>140°F) 3.2.1-29 Steel piping, piping Loss of material due . Chapter Xl.M21A, "Closed components, and piping to general, pitting, Treated Water Systems" elements exposed to closed-and crevice corrosion cycle cooling water 3.2.1-30
Steel heat exchanger Loss of material due Chapter Xl.M21A, "Closed components exposed to to general, pitting, Treated Water Systems" closed-cycle cooling water crevice, and galvanic . corrosion 3.2.1-31 Stainless steel heat. Loss of material due Chapter Xl.M21A, "Closed exchanger components, . to pitting and crevice Treated Water Systems" piping, piping components, corrosion and piping elements exposed to closed-cycle cooling water 3.0 Aging Management Review Results
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no stainless steel ESF components exposed to closed-cycle cooling water >140°F in the scope of license renewal. No There are no steel ESF components exposed to closed-cycle cooling water in the scope of license renewal, other than the heat exchanger components compared to item 3.2.1-30 below. Nb Consistent with NUREG-1801. Loss of material of steel heat exchanger components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material .of stainless steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closec;I Treated Water Systems Program. Page 3.2-17 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-32 Copper alloy heat exchanger Loss of material due components, piping, piping to pitting, crevice, components, and piping and galvanic elements exposed to corrosion cycle cooling water 3.2.1-33 Copper alloy, stainless steel Reduction-of heat Heat exchanger tubes transfer due to exposed to closed-cycle fouling cooling water 3.2.1-34 Copper alloy (>15% Zn or Loss of material due >8% Al) piping, piping to selective leaching components, and piping elements, heat exchanger components exposed to closed-cycle cooling water 3.2.1-35 Gray cast iron motor cooler Loss of material due exposed to treated water to selective leaching 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M33, "Selective Leaching" Chapter Xl.M33, "Selective Leaching" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no copper alloy ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel ESF system heat exchanger tubes exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. There are no copper alloy ESF heat exchanger tubes exposed to closed-cycle cooling water in the scope of license renewal. No There are no copper alloy (>15% Zn or >8% Al) ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No There are no gray cast iron ESF system components exposed to closed-cycle cooling water in the scope of license renewal. Page 3.2-18 Table 3.2.1: Engineered Safety Features Item Aging Effect/ . . Number Component Mechanism 3.2.1-36 Gray cast iron piping, piping Loss of material due components, and piping to selective leaching elements exposed to closed-cycle cooling water 3.2.1-37 Gray cast iron piping, piping Loss of material due components, and piping to selective leaching elements exposed to soil 3.2.1-38 BWRonly 3.2.1-39 Steel containment isolation Loss of material due piping and components to general corrosion. (external surfaces) .exposed to condensation (external) 3.0 Aging Management Review Results \ Aging Management Programs Chapter Xl.M33, "Selective Leaching" Chapt.er Xl.M33, Leaching" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical. Information Further Evaluation Recommended .Discussion No There are no gray cast iron ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No There are no gray cast iron ESF system components exposed to soil in.the scope of license renewal. No Loss of material for steel components externally exposed to condensation is managed by the External Surfaces Monitoring Program. However, these steel containment is9lation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. Page 3.2-19 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-40 Steel ducting, piping, and Loss of material due components (external to general corrosion ' surfaces), ducting, closure bolting, containment isolation piping and components (external surfaces) exposed to air -indoor, uncontrolled (external) 3.2.1-41 Steel external surfaces Loss of material due exposed to air -outdoor to general corrosion (external) 3.2.1-42 Aluminum. piping, piping Loss of material due comf:!onents, and piping to pitting and crevice elements exposed to air -corrosion outdoor 3.2.1-43 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of external surfaces of steel components exposed to indoor air is managed by the External Surfaces Monitoring Program. No There are no steel ESF system components exposed to outdoor air in the scope of license renewal. No -There are no aluminum ESF system components exposed to outdoor air in the scope of license renewal. Page 3.2-20 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component. Mechanism Programs 3.2.1-44 Steel piping and Loss of materic;il due Chapter Xl.M38, components (internal ta general corrosion "Inspection of Internal surfaci;!s), ducting and Surfaces in Miscellaneous components (internal Piping and Ducting* surfaces) exposed to air-Components" * . indoor, uncontrolled (internal) " 3.0 Aging Management Review Results \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for many components. Loss of material from the internal surfaces of steel components exposed to air -indoor is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. For the fire protection system portable smoke exhaust fan housing (Table 3.3.2-6), and for abandoned piping in the secondary sampling system (Table 3.3.2-15-34), loss of material from the internal surface is managed by the Periodic SuNeillance and Preventive Maintenance Program. The External Surfaces Monitoring Program manages loss of material for external carbon steel components by visual inspection of external surfaces. Page 3.2-21 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-45 Steel encapsulation Loss of material due components exposed to air -to general, pitting, indoor, uncontrolled and crevice corrosion (internal) 3.2.1-46 BWR only 3.2.1-47 Steel encapsulation Loss of material due components exposed to air to general, pitting, with borated water leakage crevice, and boric (internal) acid corrosion .. 3.2.1-48 Stainless steel piping, piping Loss of material due components, and piping to pitting and crevice elements (internal corrosion tanks exposed to condensation (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion (continued) For those components where internal carbon steel surfaces are exposed to the same environment as external surfaces (Tables 3.3.2-X), external surface conditions will be representative of internal surfaces. Thus,* loss of material on internal carbon steel surfaces is also managed by the External
Surfaces Monitoring Program. No The WF3 containment spray system does not use encapsulation components. No The WF3 containment spray system does not use encapsulation components. -No There are no stainless steel ESF system components internally exposed to condensation in the scope of license renewal. Page 3.2-22 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.2.1-49 Steel piping, piping Loss of material due Chapter Xl.M39, components, and piping to general, pitting, "Lubricating Oil Analysis," elements exposed to and crevice corrosion and Chapter Xl.M32, "One-lubricating oil Time Inspection" 3.2.1-50 Copper alloy, stainless steel Loss of material due Chapter Xl.M39, piping, piping components,
to pitting and crevice "Lubricating Oil Analysis," . and piping elements . corrosion and Chapter Xl.M32, "One-exposed to lubricating oil Time Inspection" 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended , Discussion No Consistent with NUREG-1801. Loss of material for steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for copper alloy and stainless steel components exposed to lube oil (Tables 3.1.2-X) is managed by the Oil Analysis Program. The One-Time Inspection Program will
verify the effectiveness* of the Oil Analysis Program* to manage loss of material. Page 3.2-23 Table 3.2.1 :. Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-51 Steel, copper alloy, stainless Reduction of heat steel heat exchanger tubes transfer due to exposed to lubricating oil fouling 3.2.1-52 Steel (with coating or Loss of material due wrapping) piping, piping to general, pitting, components, and piping crevice, and elements to soil or microbiologically-concrete influenced corr9sion 3.2.1-53 Stainless steel, nickel alloy Loss of material due piping, piping components, to pitting and crevice and piping elements corrosion exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Qhapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground .Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for steel, and stainless steel heat exchanger tubes exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage reduction of heat transfer. There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the ESF systems in the scope of license renewal. No There are no steel ESF system components exposed to soil or concrete in the scope of license renewal. No There are no ESF system piping components exposed to soil or concrete in the scope of license renewal. Page 3.2-24 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-53.5 Steel; stainless steel, nickel Loss of material due alloy underground piping, to general (steel piping components, and only), pitting and piping elements exposed to crevice corrosion air-indoor uncontrolled or (external) 3.2.1-54 BWRonly 3.2.1-55 , Steel piping, piping None components, and piping elements exposed to concrete 3.2.1-56 Aluminum piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (internal/external) 3.2.1-57 Copper alloy piping*, piping None components, and piping elements exposed to air -indoor, uncontrolled (external), gas 3.0 Aging Management Review.Results Aging Management Programs Chapter Xl.M41, "Buried . and Underground Piping and Tanks" None, provided 1) attributes of the concrete are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG-1557, and 2) plant* OE indicates no degradation ,of the concrete None None Waterford Steam Electric Station, Unit 3 License .Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no ESF system underground piping components in the scope of license renewal. No, if conditions There are no ESF system are met. components* embedded in concrete in the scope of license renewal. NA-NoAEM or Con'sistent with NUREG-1801. AMP This item applies to components in Table 3.1.2-5-1. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air) environments. This item applies to components in Table 3.1.2-3. Page 3.2-25 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-58 Copper alloy (S15% Zn and None S8% Al) piping, piping components, and piping elements exposed to air with borated water leakage 3.2.1-59 Galvanized steel ducting, None piping, and components exposed to air-indoor, controlled (external) 3.2.1-60 Glass piping elements None exposed to air -indoor, uncontrolled (external), lubricating oil, raw water, treated water, treated water (borated), air with borated water leakage, condensation (internal/external), gas, closed-cycle cooling water, air -outdoor 3.2.1-61 Nickel alloy piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (external) 3.2.1-62 Nickel alloy piping, piping None components, and piping elements exposed to air with borated water leakage 3.0 Aging Management Review Results Aging Management Programs None None None None None 1* Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion NA-NoAEM or There are no copper alloy ESF AMP system components exposed to air with borated water leakage in the scope of license renewal. NA-NoAEM or Galvanized steel is evaluated as AMP steel. NA-NoAEM or Consistent with NUREG-1801. AMP for relevant (indoor air and treated borated water) environments. This item applies to components in Table 1. NA-NoAEM or Consistent with NUREG-1801. AMP NA-NoAEM or Consistent with NUREG-1801. AMP Page 3.2-26 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-63 Stainless steel piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (external), air with borated water leakage, concrete, gas, air -indoor, uncontrolled (internal) . 3.2.1-6"4 Steel pipir19, piping None components, and piping elements exposecl to air -indoor, controlled (external), gas 3.2.1-65 Any material, piping, piping Wall thinning due to. components, and piping erosion elements exposed to treated : water, treated water *' (borated) 3.2.1-66 Metallic piping, piping Loss of material due components, and tanks to recurring internal exposed to raw water or corrosion wastewater . 3.0 Aging Review Results ( Aging Management Programs None None ,. Chapter Xl.M17, "Flow-* Accelerated Corrosion" .. A plant-specific aging management program is to be evaluated to address recurring internal corrosion Waterford Steam Station, Unit 3 License Renewal Application Technical Information . Further Evaluation Recommended Discussion NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air, air with borated water.leakage and gas) environments. ' NA-NoAEM or There are no steel ESF system AMP components exposed to controlled indoor air or gas in the scope of license renewal. No " The materials, environments and operating conditions of ESF system components are not conducive to erosion. Yes, plant-specific Recurring internal corrosion was not identified in*the WF3 engineered safety features systems in the scope of license renewal. . See Section 3.2.2.2.9 . Page 3.2-27 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-67 Stainless steel or aluminum Cracking due to tanks (within the scope of stress corrosion Chapter Xl.M29, cracking "Aboveground Metallic Tanks") exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist air, condensation 3.2.1-68 Steel, stainless steel, or Loss of material due aluminum tanks (within the to general (steel scope of Chapter Xl.M29, only), pitting, and "Aboveground Metallic crevice corrosion Tanks") exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist .air, condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, . "Aboveground Metallic Tanks" Chapter Xl.M29, "Aboveground Metallic Tanks" : Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. No -At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Page 3.2-28 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-69 Insulated steel, stainless Loss of material due steel, copper alloy, or to general (steel, and aluminum, piping, piping copper alloy only), components, and tanks pitting, and crevice exposed to condensation, corrosion C!ir-outdoor 3.2.1-70 Steel, stainless steel or Loss of material due aluminum tanks (within the to general (steel scope of Chapter Xl.M29, only}, pitting and "Aboveground Metallic crevice corrosion. Tanks") exposed to treated water, treated borated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, "Aboveground Metallic Tanks," (for tanks only)-Chapter Xl.M29, "Aboveground Metallic Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for insulated stainless steel components exposed to condensation. Loss of material is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy > 15% Zn or > 8% Al piping components or tanks exposed to condensation or outdoor air in the WF3 engineered safety features systems in the scope of license renewal. No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Page 3.2-29 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-71
Insulated stainless steel, Cracking due to aluminum, or copper alloy (> stress corrosion 15% Zn) piping, piping cracking components, and tanks exposed to condensation, air-outdoor 3.2.1-72 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks *with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-cycle delamination, cooling water; raw water, rusting, or physical treated water, *treated damage, and spalling water, or for CE!mentitious oil coc:ltings/linings 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, "Aboveground Metallic Tanks," (for tanks only) / Chapter Xl.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat . and Tanks" ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further-Evaluation Recommended Discussion No Consistent with NUREG-1801 for insulated stainless steel components exposed to condensation. Cracking is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy > 15% Zn or> 8% Al piping components or tanks exposed* to condensation or outdoor air in the WF3 engineered safety features systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of coating or lining integrity for metallic components with internal coating or linings is managed by the Coating Integrity Program. Page Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Table 3.2.1: Engineered Safety Features ' Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-73 Metallic piping, piping Loss of material. due Chapter Xl.M42, "lntemal No* Consistentwith NUREG-1801. components, heat*
to general, pitting, Coatings/Linings for In-Loss of material for metallic exchangers, tanks with crevice, and
Scope Piping, Piping components with internal
internal coatings/linings microbiologically Components, Heat coating or linings is managed by exposed to closed-cycle
influenced corrosion; Exchangers, and Tanks" the Coating Integrity Program. . cooling water, raw water *. fouling that leads to treated water, treated corrosion borated water, or lubricating oil 3.2.1-74 . Gray cast iron piping Loss of material due Chapter Xl.M42, "Internal No There are no gray cast iron components with internal to selective leachi.ng Coatings/Linings for In-components with internal coatings/linings exposed to Scope Piping, Piping coatings or linings in the ESF closed-cycle cooling water, Components, He.at
systems in the scope of license raw water, or treated water Exchangers, and Tanks" renewal. 3.0 Aging Management Review Results Page 3.2-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Notes for Tables 3.2.2-1 through 3.2.2-4-2 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801.identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and. environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 201. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 202. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 3.0 Aging Management Review Results Page 3.2-32 Table 3.2.2-1 Containment Spray System 'Summary of Aging Management Evaluation Table 3.2.2-1: Containment Spray System Aging Effect , Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air -indoor , Loss. of material Bolting Integrity
boundary, (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion .. Bolting. Pressure Carbon steel , Air...: indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary . steel (ext) * '* Flow element Pressure Stainless Air-indoor ., None None boundary steel (ext) Flow element Pressure Stainless Treated borated Loss of material
Water Chemistry boundary steel water (int) Control -Primary and Secondary Heat exchanger Pressure Carbpn steel Air-indoor Loss of material *Boric Acid (channel head) . clad with (ext) Corrosion *stainless steel Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (channel head) . boundary clad with (ext) Monitoring stainless steel *' Heat exchanger Pressure
Carbon steel Treated borated Cracking Water Chemistry (channel head) .. boundary . clad with water> 140°F Control -Primary *stainless steel (int) and Secondary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1so11tem ,Item Notes V.E.EP-70 3.2.1-13 B V.E.E-41 " 3.2.1-9 A V.E.EP-69 3.2.1-15 B V.E.EP-69 . 3.2.1-15 B V.F.EP-18 3.2.1-63 A . V.A.EP-41 3.2.1-22 A, 201 3.2.1-9. A V.E.E-44 3.2.1-40 A V.A.E-12 3.2.1-20 C, 201 Page 3.2-33 Table 3.2.2-1 : Containment Spray System Aging Effect Intended Requiring Component Type Function Material Environment Management Heat exchanger Pressure Carbon steel Treated borated Loss of material (channel head) boundary clad with water> 140°F stainless steel (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) boundary (int) Heat exchanger Pressure Carbon steel Treated water Loss of coating (shell) boundary with internal (int) integrity coating Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) boundary with internal (int) coating Heat exchanger Pressure Carbon steel Treated borated Cracking (tube sheet) boundary clad with water> 140°F stainless steel (ext) Heat exchanger Pressure Carbon steel Treated borated Loss of material (tube sheet) boundary clad with water> 140°F stainless steel (ext) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Water Chemistry Control -Closed Treated Water Systems Coating Integrity Coating Integrity Water Chemistry Control -Primary and Secondar-Y Water* Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 C, 201 V.A.E-28 3.2.1-9 A V.E.E-44 3.2.1-40 A V.A.EP-92 3.2.1-30 A V.A.E-401 3.2.1-72 B V.A.E-414 3.2.1-73 B V.A.E-12 3.2.1-20 C, 201 V.A.EP-41 3.2.1-22 C, 201 Page 3.2-34 Table 3.2.2-1: Containment Spray System Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel Treated water (tube sheet) boundary. clad with (int) stainless steel Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water (int) Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water> 140°F (int) Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water> 140°F (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water> 140°F (int) Heat exchanger Pressure Stainless Treated water (tubes) boundary steel (ext) Heat exchanger Heat transfer Stainless Treated water (tubes) steel (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-93 3.2.1-31 A V.A.EP-41 3.2.1-22 C, 201 V.A.E-20 3.2.1-19 A, 201 V.A.E-12 3.2.1-20 C, 201 V.A.EP-41 3.2.1-22 C, 201 V.A.E-20 3.2.1-19 A, 201 V.A.EP-93 3.2.1-31 A V.A.EP-96 3.2.1-33 A Page 3.2-35 Table 3.2.2-1: Containment Spray System Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel (water jacket) boundary (ext) Heat exchanger Pressure Carbon steel Air-Indoor (water jacket) boundary (ext) .. Heat exchanger Pressure Carbon steel Lube oil (ext) (water jacket) boundary Heat exchanger Heat transfer Carbon steel Lube oil (ext) (water jacket) Heat exchanger Pressure Carbon steel Treated water . (water jacket) boundary (int) Heat exchanger Heat transfer Carbon steel Treated.water (water jacket) (int) Nozzle Pressure Stainless Air-indoor boundary steel (ext) Flow control* Nozzle Pressure Stainless Air -indoor (int) boundary steel Flow control Orifice Pressure Stainless Air-indoor boundary steel (ext) Flow control 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material External Surfaces Loss of material Oil Analysis
Reduction of heat Oil Analysis transfer* Loss of material Water Chemistry Control -Closed . Treated Water Systems Reduction of heat Water Che'mistry transfer Control -Closed Treated Water Systems None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.E-28 3.2.1-9 A V.E.E-44 3.2.1-40 A V.A.EP-77 3.2.1-49 C, 202 V.A.EP-75 3.2.1-51 A,202 V.A.EP-92 3.2.1-30 A Vll.F1 .AP-204 3.3.1-'50 c V.F.EP-18 3.2.1-63 A V.F.EP-82 3.2.1-63 A V.F.EP-18 3.2.1-63 A Page 3.2-36 Table 3.2$1: Containment Spray System .. *Intended Component Type Function Material Orifice Pressure Stainless boundary steel Flow control Piping
Pressure *Stainless boundary . steel Piping Pressure Stainless boundary steel Piping Pressure . Stainless
boundary *steel Piping Pressure .$tainless boundary steel Piping Pressure Stainless boundary steel* Piping Pressure *Stainless boundary steel Pump casing Pressure Stainless boundary steel *. Pump casing Pressure Stainless boundary steel Separator Pressure Stainless boundary steel 3.0 Aging Management Review. Results i I \ <. Environment
Treated borated water (int) Air-indoor (ext) Air -indoor (int) Treated borated water (int) Treated borated water> 140°F (int)* Treated borated water> 140°F (int) Treated borated water> 140°F (int) Air-indoor (ext) Treated borated
water (int) Air-indoor (ext) Aging Effect Aging i Requiring Management : Management Programs .Loss of Water Chemistry Control -Primary and Secondary None None None None Loss of material. Water Chemistry Control -Primary . and Secondary Cracking Water Chemistry : Control -Primary and Secondary Cracking -fatigue . TLAA ;_metal
fatigue Loe;s of material Water Chemistry Control -Primary and Secondary None None** Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 A, 201 .. 3.2.1-63 A V.F.EP-82 3.2.1-63 A
V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A,201 V.F.EP-18 3.2.1-63 A 3.2.1-22 A, 201 V.F .. EP-18 3.2:1-63 A Page 3.2-37 I Table 3.2.2-1: Containment Spray System Aging ,Effect Intended Requiring Component Type Function Material Environment Management Separator Pressure Stainless Treated borated Loss of material boundary steel water (int) Filtration Thermowell Pressure Stainless Air-indoor None boundary steel (ext) Thermowell Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Thermowell Pressure Stainless Treated borated Cracking -fatigue t:>oundary steel water> 140°F (int) Thermowell Pressure* Stainless Treated borated Loss of material boundary steel water> 140°F (int) Tubing Pressure Stainless Air-indoor None boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material boundary steel water (int) Tubing Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated Cracking -fatigue boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary TLAA -metal
fatigue Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c Page 3.2-38 Table 3.2.2-1: Containment Spray System Aging Effect Intended Requiring Component Type Function Material Environment Management Tubing Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) Valve body Pressure Stainless Air-indoor None boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material boundary steel water (int) Valve body Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Cracking -fatigue boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A, 201 Page 3.2-39 Table 3.2.2-2 Safety Injection System Summary of Aging Management Evaluation Table 3.2.2-2: Safety Injection System Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Bolting Integrity boundary Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Boric Acid boundary Corrosion Bolting Pressure Carbon steel Air'.'""" indoor (ext) Loss of preload Bolting Integrity boundary Bolting Pressure High strength Air-indoor (ext) Cracking Bolting Integrity boundary steel Bolting Pressure High strength Air -indoor (ext) Loss of material Bolting Integrity boundary steel Bolting Pressure High strength Air-indoor (ext) Loss of j:>reload Bolting Integrity boundary steel Bolting Pressure *Stainless Air-indoor (ext) Loss of preload Bolting Integrity boundary steel Flow element Pressure Stainless Air-indoor (ext) None* None boundary steel Flow control Flow element Pressure Stainless Treated borated Loss of material Water Chemistry boundary steel water (int) Control -Primary Flow control and Secondary 3.0 Aging Management Review Results WatE!rford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.E.EP-70 3.2.1-13 B V.E.E-41 3.2.1-9 A V.E.EP-69 3.2.1-15 B V.E.E-03 3.2.1-12 B V.E.EP-70 3.2.1-13 B V.E.EP-69 3.2.1-15 B V.E.EP-69 3.2.1-15 B V.F.EP-18 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 Page 3.2-40 Table 3.2.2-2: Safety Injection System Intended Component Type Function Material Environment Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Heat exchanger Pressure Cc;irbon steel Air-indoor (ext) (shell) boundary Heat exchanger Pressure Carbon steel Air-indoor (ext) (shell) boundary Heat exchanger Pressure Carbon steel Treated water (shell) boundary with internal (int) coating Heat exchanger Pressure Carbon steel Treated water (shell) boundary with internal (int) coating Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Cracking Cracking -fatigue Loss of material Loss of material Loss of material Loss of coating integrity Loss of material Loss of material Reduction of heat transfer Aging Management Programs Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01 .E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.01.E-28 3.2.1-9 A External Surfaces V.E.E-44 3.2.1-40 A Monitoring Coating Integrity V.0.1.E-401 3.2.1-72 B Coating Integrity V.01.E-414 3.2.1-73 B Water Chemistry V.01.EP-41 3.2.1-22 C, 201 Control -Primary and Secondary Water Chemistry V.01.E-20 3.2.1-19 A, 201 Control -Primary and Secondary Page 3.2-41 Table 3.2.2-2: Safety Injection System Aging Effect Intended Requiring Component Type Function Material Environment Management Heat exchanger Pressure Stainless Treated water Loss of material (tubes) boundary steel (ext) Heat exchanger Heat transfer Stainless Treated water Reduction of heat (tubes) steel (ext) transfer Orifice Pressure Stainless Air -indoor (ext) None boundary steel Flow control Orifice Pressure Stainless Treated borated Loss of material boundary steel water (int) Flow control Orifice Pressure Stainless Treated borated Cracking boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated b9rated Cracking -fatigue boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated borated Loss of material boundary steel water> 140°F Flow control (int) Piping Pressure Stainless Air-indoor (ext) None boundary steel 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01.EP-93 3.2.1-31 A V.01.EP-96 3.2.1-33 A V.F.EP-18 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 V.01 .E-12 3.2.1-20 A, 201 V.01 .E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A Page 3.2-42 Table Safety Injection System Intended Component Type Function Material Erivfronment Piping Pressure Stainless Air -indoor (int) boundary steel Piping Pressure Stainless Gas (int) boundary steel Piping Pressure Stainless Treated borated boundary steel water (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) , Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Pump casing Pressure Stainless Air -indoor (ext) boundary steel Pump casing Pressure Stainless Treated borated boundary steel water (int) Pump *casing Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management .Programs None None None None Loss of material Water Chemistry Control -Primary and Secondary Cracking . Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-82 3;2.1-63 A VFEP-22 3.2.1-63 A V.01.EP-41 3.2.1-22 A,201 V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A 3.2.1-22 A, 201 V.01.E-12 3.2.1-20 A, 201 Page 3.2-43 Table 3.2.2-2: Safety Injection System Aging Effect Intended Requiring Component Type Function Material Environment Management Pump casing Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) Tank Pressure Carbon steel Air -indoor (ext) Loss of material boundary clad with stainless steel Tank Pressure Carbon steel Air -indoor (ext) Loss of material boundary clad with stainless steel Tank Pressure Carbon steel Gas (int) None boundary clad with stainless steel Tank Pressure Carbon steel Treated borated Loss of material boundary clad with water (int) stainless steel Thermowell Pressure Nickel alloy Air -indoor (ext) None boundary Thermowell Pressure Nickel alloy Treated borated Loss of material boundary water (int) Tubing Pressure Stainless Air-indoor (ext) None boundary steel Tubing Pressure Stainless Treated borated Loss of material boundary steel water (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.D1.EP-41 3.2.1-22 A, 201 V.D1.E-28 3.2.1-9 A External Surfaces V.E.E-44 3.2.1-40 A Monitoring None V.F.EP-22 3.2.1-63 c Water Chemistry V.D1 .EP-41 3.2.1-22 A, 201 Control -Primary and Secondary None V.F.EP-17 3.2.1-61 A V.F.EP-115 3.2.1-62 Water Chemistry ----G Control -Primary and Secondary None V.F.EP-18 3.2.1-63 A Water Chemistry V.D1.EP-41 3.2.1-22 A, 201 Control -Primary and Secondary Page 3.2-44 Table 3.2.2-2: Safety Injection System Intended Component Type Function Material Enyironment Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Air-indoor (ext) boundary steel Valve body Pressure Stainless Gas (int) boundary steel Valve body Pressure Stainless Treated borated boundary steel water (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.F.EP-22 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 Page 3.2-45 Table 3.2.2-3 Containment Penetrations Summary of Aging Management Evaluation Table 3.2.2-3: Containment Penetrations Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary steel (ext) Bolting Pressure Stainless Treated borated Loss of material Bolting Integrity boundary steel water (ext) Bolting Pressure Stainless Treated borated Loss of preload Bolting Integrity boundary steel water (ext) Insulated piping Pressure Stainless Condensation Cracking External Surfaces components boundary steel (ext) Monitoring Insulated piping* Pressure Stainless Condensation Loss of material External Surfaces components boundary steel (ext) . Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Piping Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces boundary Monitoring Piping Pressure Stainless Air-indoor None None boundary steel (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.E.EP-70 3.2.1-13 B V.E.EP-69 3.2.1-15 B V.E.EP:..59 3.2.1-15 B ----H V.E.EP-120 3.2.1-15 B V.C.E-406 3.2.1-71 A V.C.E-403 3.2.1-69 A V.E.E-44 3.2.1-40 A V.A.E-29 3.2.1-44 E V.F.EP-18 3.2.1-63 A Page 3.2-46 Table 3.2.2-3: Containment Penetrations Intended Component Type Function Material Environment Piping Pressure Stainless Air -indoor (int) boundary steel Piping Pressure Stainless Treated borated boundary steel water (ext) Piping Pressure Stainless Treated borated boundary steel water (int) Piping Pressure Stainless Treated borated boundary steel water > 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated water boundary steel (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-82 3.2.1-63 A V.A.EP-41 3.2.1-22 C, 201 V.A.EP-41 3.2.1-22 C, 201 V.01.E-12 3.2.1-20 C, 201 V.01.E-13 3.2.1-1 c V.01.EP-41 3.2.1-22 C, 201 V.C.EP-95 3.2.1-31 A V.E.E-44 3.2.1-40 A V.A.E-29 3.2.1-44 E Page 3.2-47 Table 3.2.2-3: Containment Penetrations Aging Effect Intended Requiring Component Type Function Material Environment Management Valve body Pressure Stainless Air-indoor None boundary steel (ext) Valve body Pressure Stainless Air -indoor (int) None boundary steel Valve body Pressure Stainless Treated borated Loss of material boundary steel water (int) Valve body Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Cracking -fatigue boundary steel water > 140°F (int) Valve body Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) Valve body Pressure Stainless Treated water Loss of material boundary steel (int) 3.0 Aging Management Review Results Aging Management Programs None None Water Chemistry 9ontrol -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-18 3.2.1-63 A V.F.EP-82 3.2.1-63 A V.A.EP-41 3.2.1-22 C, 201 V.01.E-12 3.2.1-20 C, 201 V.01.E-13 3.2.1-1 c V.01.EP-41 3.2.1-22 C, 201 V.C.EP-95 3.2.1-31 A Page 3.2-48 Table 3.2.2-4-1 Containment Spray System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.2.2-4-1 :Containment Spray System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity V.E.EP-69 3.2.1-15 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity V.E.EP-70 3.2.1-13 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid V.E.E-41 3.2.1-9 A boundary (ext) Corrosion Orifice Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1c63 A boundary steel (ext) Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary . steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary . *steel (int) Miscellaneous Piping and Ducting *' Components 3.0 Aging Management Review Results Page 3.2-49 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.2.2-4-1 :Containment Spray System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Pump casing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results P?ge 3.2-50 Table 3.2.2-4-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Safety Injection System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.2.2-4-2:Safety Injection System, Nonsafety-Related Components Affecting Safety-Related Systems* Aging Effect Aging Intended Requiring Management .NUREG-Table 1 Component Type Function Material Environment Management. .Programs 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity. V.E.EP-69 3.2.1-15 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity V.E.EP-70 3.2.1-13 B" boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid V.E.E-41 3.2.1-9 .A boundary (ext) Corrosion Piping Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material

Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and* Secondary Pump casing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless* Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.2-51 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.2.2-4-2:Safety Injection System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Trap Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.D1.EP-.tl1 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.2-52 3.3 AUXILIARY SYSTEMS 3.3.1 Introduction Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of the aging management reviews for those components in the auxiliary systems which are subject to aging management review. The following systems are addressed in this section (system descriptions are available in the referenced sections).

Chemical and Volume Control. (Section 2.3.3.1)
Chilled Water (Section 2.3.3.2)
Component Cooling and Auxiliary Component Cooling Water (Section 2.3.3.3)
Compressed Air (Section 2.3.3.4)
Containment Cooling HVAC (Section 2.3.3.5)
Control Room HVAC (Section 2.3.3.6)
Emergency DiesE!I Generator (Section 2.3.3.7)
Fire Protection -Water (Section 2.3.3.8)
Fire Protection RCP Oil Collection (,Section 2.3.3.9)
Fuel Pool Cooling Purification (Section 2.3.3.1 O)
Nitrogen*(Section 2.3.3.11) .
Miscellaneous HVAC (Section 2.3.3.12) * -Auxiliary Diesel Generator (Section 2.3.3.13)
Plant Drains (Section 2.3.3.14)
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) (Section 2.3.3. 15) Table 3.3.1, Summary of Aging Management Programs for Auxiliary* Systems Evaluated in . . Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the auxiliary systems component group. This table uses the format described in the . introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.3.2 Results The*following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for auxiliary systems. * *
Table 3.3.2-1 Chemical and Volume Control System-Summary of Aging Management Evaluation Table 3.3.2-2 _Chilled Water System-Summary of Aging Management Evaluation Table 3.3.2-3 Component Cooling and Auxiliary Component Cooling Water System_:_ Summary of Aging Management Evaluation
Table 3.3.2-4 Compressed Air System-Summary of Aging Management Evaluation *
Table 3.3.2-5 Containment Cooling HVAC System-Summary of Aging' Management Evaluation 3.0 Agi_ng Management Review Results Page 3.3-1 I ...

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information

Table 3.3.2-6 Control Room HVAC System-Summary of Aging Management Evaluation
Table 3.3.2-7 Emergency Diesel Generator System-Summary of Aging Management Evaluation *
Table 3.3.2-8 Fire Protection -Water System-Summary of Aging Management Evaluation
Table 3.3.2-9 Fire Protection RCP Oil Collection System-Summary of Management Evaluation
Table 3.3.2-10 Fuel Pool Cooling and Purification of Aging
Management Evaluation
Table 3.3.2-11 Nitrogen System-Summary of Aging Management Evaluation
Table-3.3.2-12 Miscellaneous HVAC Systems-Summary of Aging Management Evaluation
Table 3.3.2-13Auxiliary Diesel Generator System-Summary of Aging Management Evaluation
Table 3.3.2-14 Plant Drains -Summary of Aging Management Evaluation * * * *
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Table 3.3.2-15-1 Air Evacuation System, Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation Table 3.3.2-15-2 Airborne Radioactivity Removal System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-3 Annulus Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation
Table 3.3.2-15-4 Auxiliary Steam System, Nonsafety-Related Components Affecting . Safety-Related System$-Summary of Aging Management Evaluation Table 3.3.2-15-5 Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Management Review Results Page 3.3-2 Waterford Steam Electric' Station, Unit 3 License Renewal Application Technical Information
Table 3.3.2-15-6 Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *-Table 3.3.2-15-7 *Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation * * * * *
Table 3.3.2-15-8 Chemical Feed System, Nonsafety-Related Components Affecting . Safety-Related Systems-Summary of Management Evaluation I Table 3.3.?-15-9 Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-10 Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-12 Compressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-13 Containment Atmosphere Purge System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3*.3:2-15-14 Containment Atmosphere Release System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation
Table 3.3.2-15-15 Containment Building, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *
Table 3.3.2-15-16 Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-17 Emergency Diesel Generator System, Nor:isafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Review Results Page 3.3-3
* * * * * * * * * *
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-18 Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related* Systems-Summary of Aging Management Evaluation Table 3.3.2-15-'19 Fuel Pool Cooling and Purification System, Nonsafety-Related Cornponents Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-20 Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-21 Hot Machine Shop and Decqn Facility Ventilation System, Related Components Affectfng Safety-Related Systems.:..._Summary of Aging Management Evaluation Table 3.3.2-15-22 Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-23 Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-'Summary of Aging Management Evaluation
Table 3.3.2-15-24 Nitrogen System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-25 Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related *Systems-Summary of Aging Management *Evaluation *
Table 3.3.2-15-26 Potable Water System, Nonsafety-Related Com.porients Affecting . Safety-Related Systems-Summary of Aging Management Evaluation. Table 3.3.2,..15-27 Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-28 Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary:of Aging Management Evaluation Table. 3.3.2-15-29 Radiation Monitoring System, Nonsafety-Related Components .. Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Management Review Results
Page 3.3-4
* * * * *
Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Table 3.3.2-15-30 Reactor Auxiliary Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-31 Reactor Cavity Cooling System, Nonsafety-Related Components Affecting Systems-Summary of Aging Management Evaluation Table 3.3.2-15-32 Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3_.2-15-33 Secondary Sampling System, Nonsafety-Related Components Affecting Systems-:-Sumniary of Aging Management Evaluation Table 3.3.2-15-34 Solid Waste Management System, Nonsafety-Relatep Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-35 Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-36 Turbine Building Cooling Water System, Nonsafety-Related Componehts Affecting Safety-Related Systems-Summary of Aging . Management Evaluation 3.3.2.1 Materials, Environments; Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the auxiliary systems. Programs are described in Appendix B.
Further details are provided in the system tables. 3.3.2.1.1 Chemical and Volume Control Materials Chemical c;lnd volume control system components are constructed of the following materials.
Carbon steel
CASS
High strength steel
Stainless steel 3.0 Aging Management Review Results Page 3.3-5
Environments Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Chemical and volume control system components are exposed to the following environments.
Air -indoor
Gas
Lube oil
Treated borated water
Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects associated with the chemical and volume control system require management. * * * *
Cracking Cracking -fatigue Loss of material Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for chemical and volume control system components. * * * * * * *
Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring lnservice Inspection Oil Analysis One-Time Inspection Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.3.2.1.2 Chilled Water Materials Chilled water system components are constructed of the following materials.
Carbon steel 3.0 Aging Review Results Page 3.3-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information * * * *
Carbon steel with internal coating . Copper alloy Copper alloy > 15% zinc or > 8% aluminum Glass Stainless steel Environments Chilled water system components are exposed to the following environments.
Air-indoor
Condensation
Gas
Lube oil
Treated water Aging Effects Requiring Management The following aging effects associated with the chilled water system require management.
Loss of coating integrity
Loss of material
Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the chilled water system components. * * * *
Bolting Integrity Coating Integrity External Surfaces Monitoring Oil Analysis Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.3 Component Cooling and Auxiliarv Component Cooling Water Materials Component cooling and auxiliary component cooling water system components are constructed of the following materials. 3.0 Aging Management Review Results Page 3.3-7
Aluminum
Carbon steel
Carbon steel with internal coating
Concrete
Copper alloy
Glass
Gray cast iron
High strength steel
Stainless steel Environments Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Component cooling and auxiliary component cooling water system comporients are exposed to the following environments ...
Air-indoor
Air -outdoor
Condensation * . Lube oil
Raw water
Soil
Treated water Aging Effects Requi.ring Management The following aging effects associated with the component cooling and auxiliary component cooling water system require management. * * * * *
Change in material properties Cracking Loss of coating integrity Loss of material Loss of material -erosior:i Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the component cooling and auxiliary component cooling water system components.
Bolting Integrity
Buried and Underground Piping and Tanks Inspection 3.0 Aging Management Review Results Page 3.3-8
*
*
Coating Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Oil Analysis One-Time Inspection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Periodic Surveillance and Preventive Maintenance Selective Leaching
Service Water Integrity
Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.4 Compressed Air Materials Compressed air system components are constructed of the following materials. * * * * *
Aluminum Carbon steel Copper alloy Elastomer Plastic Stainless steel Environments Compressed air system components are exposed to the following environments.
Air -indoor
Air -outdoor
Condensation Aging Effects Requiring Management The following aging effects associated with the compressed air system require management.
Cracking
Loss of material
Loss of material -wear
Loss of preload 3.0 Aging Management Review Results Page 3.3-9 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The.following aging management programs manage the aging effects for the compressed air system components. * *
Bolting Integrity Compressed Air Monitoring External Surfaces Monitoring 3.3.2.1.5 Containment Cooling HVAC Materials Containment cooling HVAC system components are constructed of the following materials.
Carbon steel
Copper alloy
Elastomer
Stainless steel Environments . Containment cooling HVAC system components are exposed to the following environments.
Air -indoor
Condensation
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the containment cooling HVAC system require management. * * * * *
Change in material properties Cracking Loss of material Loss of material -wear Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results Page 3.3-10 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs . The following aging management programs manage the aging effect$ for the containment cooling HVAC system components. * * *
Bolting Integrity External Surfaces Monitoring . Internal Surfaces in Miscellaneous Piping and Ducting Components Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.6 Control Room HVAC Materials Control room HVAC system components are constructed of the following materials. * * *
Carbon steel Copper alloy Elastomer Stainless steel Environments
Control room HVAC system components are exposed to the following envirC?nments.
Air-indoor
Air -outdoor
Condensation
Treated water
Wastewater *Aging Effects Requiring Management The following aging effects associated with the control room HVAC system require management. * * * * *
Change in material properties Cracking Loss of material Loss of material -wear Loss of preload Reduction of heat transfer 3.0 Aging ManagementReview Results Page 3.3-11 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the control room HVAC system components.
Bolting Integrity
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping and Ducting Components
Periodic Surveillance and Preventive Maintenance
Water Chemistry Control -Closed Treated Water Systems 3.3.2.1. 7 Emergency Diesel Generator Materials Emergency diesel generator system components are constructed of the following materials. * * * * * * *
Aluminum Carbon steel Carbon steel with internal coating Copper alloy Copper alloy >
15% zinc (inhibited) Copper alloy > 15% zinc or.> 8% aluminum Glass Stainless steel Environments Emergency diesel generator system components are exposed to the following environments.
Air-indoor
Air -outdoor
Concrete
Condensation *
Exhaust gas
Fuel oil
Lube oil
Soil
Treated water
Treated water> 140°F 3.0 Aging Man(:lgement Review Results Page 3.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Effects Requiring Management The following aging effects associated with the emergency diesel generator system require management.
Cracking
Cracking -fatigue
Loss of coating integrity
Loss of material
Loss of material -wear
Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the emergency diesel generator system components. * * * * *
* *
*
Bolting Integrity Buried and Underground Piping and Tanks Inspection Coating Integrity Compressed Air Monitoring Diesel Fuel Monitoring External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Oil Analysis One-Time Inspection Periodic Surveillance and Preventive Maintenance Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.8 Fire Protection -Water Materials Fire protection -water system components are constructed of the following materials. * * * * * *
Carbon steel Carbon steel with internal coating Copper alloy Copper alloy > 15% zinc or > 8% aluminum Gray cast iron Plastic (polyvinyl chloride [PVC]) Stainless steel 3.0 Aging Management Review Results Page 3.3-13 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Environments Fire protection -water system components are exposed to the following environments.
Air-indoor
Air -outdoor
Concrete
Condensation
Exhaust gas
Fuel oil
Raw water
Soil
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the fire protection .:.... water system require management. * * * *
Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Recurring internal corrosion Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the fire protection -water system components. * * * * * * *
Bolting Integrity Buried and Underground Piping and Tanks Inspection Diesel Fuel Monitoring External Surfaces Monitoring Fire Water System Internal Surfaces in Miscellaneous Piping and Ducting Components Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-14 3.3.2.1.9 Fire Protection RCP Oil Collection Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire protection RCP oil collection system components are constructed of the following materials.
Carbon steel
Glass
Stainless steel Environments Fire protection RCP oil collection system components are exposed to the following environments.
Air -indoor Lube oil Aging Effects Requiring Management The following aging effects associated with the fire protection RCP oil collection system require management.
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the fire protection RCP oil collection system components. * *
Bolting Integrity External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Periodic Surveillance and Preventive Maintenance 3.3.2.1.10 Fuel Pool Cooling and Purification Materials Fuel pool cooling and purification system components are constructed of the following materials.
Baral 3.0 Aging Management Review Results Page 3.3-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Carbon steel
Stainless steel Environments Fuel pool cooling and purification system components are exposed to the following environments.
Air -indoor
Treated borated water
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the fuel pool cooling arid purification system require management. * * * *
Change in material properties Loss of material Loss of preload Reduction in neutron absorption capacity Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the fuel pool cooling and purification system components. * * * * * * * *
Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Neutron-Absorbing Material Monitoring One-Time Inspection Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.3.2.1.11 Nitrogen Materials Nitrogen system components are constructed of the following materials. 3.0 Aging Management Review Results Page3.3-16
Aluminum
Carbon steel
Stainless steel
Environments Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nitrogen system components are exposed to the following environments.
Air -indoor
Air -outdoor
Gas
Waste water Aging Effects Requiring_Management The following aging effects associated with the nitrogen system requi.re management. * * -. Cracking Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the nitrogen system components.
Bolting Integrity
External Surfaces Monitoring .
Internal Surfaces in Miscellaneous Piping and Ducting Components 3.3.2.1.12 Miscellaneous HVAC Materials Miscellaneous HVAC systems components are constructed bf the following materials;
Carbon steel
Copper alloy
Elastomer
Glass
High strength steel
Stainless steel 3.0 Aging Management Review Results Page 3.3-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Environments Miscellaneous HVAC systems components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the miscellaneous HVAC systems require management.
Change in material properties * *Cracking
Loss of material * *
Loss of material -wear Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the miscellaneous HVAC systems components.
Bolting Integrity
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping* and Ducting Components
Water Chemistry Control -Closed Treated Water Systems *_ 3.3.2.1.13 Auxiliary Diesel Generator Materials Auxiliary diesel generator system components are constructed of the following materials.
Aluminum
Carbon steel -* Carbon steel with internal coating Aging Management Review Results Page 3.3-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Gray cast iron Stainless steel Environments Auxiliary diesel system components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Exhaust gas
Fuel oil Aging Effects Requiring Management The following aging effects associated with the auxiliary diesel generator system
require management. *
*
Cracking Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the auxiliary diesel generator system components. * * * *
Bolting Integrity Coating Integrity Diesel Fuel Monitoring External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components 3.3.2.1.14 Plant Drains Materials Plant drain components are constructed of the following materials.
Carbon steel
Copper alloy 3.0 Aging Management Review Results Page 3.3-19 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Copper alloy > 15% zinc or > 8% aluminum
Gray cast iron
Stainless steel Environments Plant drain components are exposed to the following environments.
Air-indoor
Air -outdoor
Soil
Treated water *
Waste water Aging Effects Requiring Management The following aging effects associated with the plant drains require management.
Cracking
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the plant drain components.
Bolting Integrity *
Buried and Underground Piping and Tanks Inspection
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping and Ducting Components
One-Time Inspection
Periodic Surveillance and Preventive Maintenance
Selective Leaching
Water Chemistry Control -Primary and Secondary 3.3.2.1.15 Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.3.2-15-xx tables. 3.0 Aging Management Review Results Page 3.3-20 Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-related components affecting safety-related systems are constructed of the following materials.
Aluminum
Carbon steel
Copper alloy
Copper alloy > 15% zinc or > 8% aluminum
Glass
Gray cast iron Plastic
Stainless steel Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments.
Air-indqor
Air -outdoor
Concrete
Condensation
Gas
Lube oil
Raw water
Steam
Treated borated water
Treated borated water> 140°F
Treated water
Treated water> 140°F
Waste water Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. * * * *
Cracking Cracking -fatigue Loss of material Loss of material -FAC Loss of preload 3.0 Aging Management Review Results Page 3.3-21 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs The following aging management programs manage the effects of aging on nonsafety-:related components affecting systems.
Bolting Integrity
Boric Acid Corrosion
Compressed Air Monitoring
External Surfaces Monitoring
Flow-Accelerated Corrosion
Internal Surfaces in Miscellaneous Piping and Ducting Components
Oil Analysis
One-Time Inspection
Periodic Surveillance and Preventive Mainten*ance
Selective Leaching
Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.3.2.2 of NUREG-1800. The following sections are numbered in accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further evaluation. Programs are d.escribed in Appendix B.
3.3.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management for components, the analysis of fatigue is a TLAA as defined in 10 CFR 54.3. TLAAs are evaluated in accordance with 10 CFR 54.21(c). Evaluations of these TtAAs are addressed in Sections 4.3 and 4.7. 3.3.2.2.2 Cracking due to Stress Corrosion Cracking and Cyclic Loading Cracking due to SCC and cyclic loading in stainless steel PWR non-regenerative heat exchanger components exposed to treated borated water greater than 140°F fn the chemical and volume control system is an aging effect requiring management. The Water Chemistry Control -Primary and Secondary Program manag.es cracking of stainless steel non-regenerative heat exchanger components exposed to treated borated water. The program is augmented by the One-Time lns.pection Program which will verify the absence of cracking through the use of visual and volumetric NOE techniques. Absence of cracking of the tubes and tubesheet is also verified by monitoring RCS leakage and radiation levels in the component cooling water system. Temperature monitoring is a much less sensitive technique and is not used. 3.0 Aging Management Review Results Page 3.3-22 3.3.2.2.3 Cracking due to Stress Corrosion Cracking Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Cracking due to stress corrosion cracking could occur for stainless steel piping, piping components, piping elements and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is
located near other industrial fc:icilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with NUREG-1801, cracking of stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.3.2.2.4 Loss of Material due to Cladding Breach This paragraph in NUREG-1800 pertains to steel charging pump casings with stainless steel cladding. Loss of material could occur for the steel casing material if exposed to treated borated water due to a cladding breach. The WF3 charging pumps have solid stainless steel casings. 3.3.2.2.5 loss of Material due to Pitting and Crevice Corrosion Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping piping elements, and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents'. WF3 .is l_ocated hear other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with NUREG-1801, loss of material for stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External . Surfaces Monitoring Program. 3.3.2.2.6 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.3.2.2. 7 Ongoing Review of Operating Experience See Appendix B Section 8.0.4 for discussion of WF3 operating experience review programs. 3.3.2.2.8 Loss of Material due to Recurring Internal Corrosion A review ,af 10 years of plant_operating experience identified recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in carbon steel piping exposed to raw water due to multiple corrosion mechanisms. The Fire Water System 3.0 Aging Management Review Results Page 3.3-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Program will manage loss of material for these piping components by monitoring degradation and replacing pipe where necessary. The Fire Water System Program will conduct augmented flow tests or flushing, and wall thickness measurements for fire water piping experiencing recurring internal corrosion prior to the period of extended operation and at least once every refueling cycle during the period of extended operation. Wall thickness measurements at selected locations will provide a representative sample of the type of piping and environment where the recurring corrosion is occurring. The selected locations may change based the relevance and usefulness of the wall thickness measurements. 3.3.2.3 Time-Limited Aging Analysis The only time-limited aging analysis identified for auxiliary systems components is metal fatigue. This is evaluated'in Section 4.3. 3.3.3 Conclusion The auxiliary system components that are subject to aging management review have been identified in accordance with the requirements of 10 CFR 54.21. The aging management programs selected to manage the effects of aging on auxiliary system components are identified in Section 3.3.2.1 and in the following tables. A description of these aging management programs is provided in Appendix 8, along with the demonstration that the identified aging effects wHI be managed for the period of extended operation. Therefore, based on the demonstrati.ons provided in Appendix B, the effects of aging associated with the auxiliary system components will _be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results
Page 3.3-24 Table 3.3.1 Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-180.1 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Aging Management Further Evaluation Number *Mechanism Programs Rec.ommended Discussion 3.3.1-1
Steel cranes -structural Cumulative fatigue Fatigue is a time-limited aging Yes, TLAA Fatigue is a TLAA. Steel cranes girders exposed to air-damage due to
analysis (TLAA) to be are evaluated as structural indoor uncontrolled fatigue* evaluated for t)le period of components in Section 3.5. (external) extended operation for structural girders of cranes See Section 3.3.2.2.1. that fall within the scope of 10 CFR 54 (Standard Review *Plan, Section.4.7, "Other' -Plant-Specific Time-Limited Aging for generic guidance for meeting the requirements' of 10 CFR -54.21 (c)(1)) 3.3.1-2 .Stainless steel, steel Cumulative fatigue .*. Fatigue is atir:ne-limited aging Yes, TLAA* Fatigue:is a TLAA. heat exchanger damage due to analysis (TLAA) to be components and tubes, fatigue evaluated for the period of See Section 3.3.2.2.1. piping, piping extended operation. See-the components, and SRP, Section 4.3 "Metal piping elements
Fatigue," for acceptable . exposed t<;> treated methods for meeting the borated water, air -requirements of 10 CFR indoor, uncontrolled, 54.21 (c)(1 ) .. ' treated water 3.0 Aging Management Review Results Page 3.3-25 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-3 Stainless steel heat Cracking due to Chapter Xl.M2, "Water exchanger stress corrosion Chem!stry" The AMP is to be componentS, non-cracking; cyclic augmented by verifying the regenerative exposed loading absence of cracking due to to treated borated water stress corrosion cracking and >60°C (>140°F) cyclic loading. An acceptable verification program is to include temperature and radioactivity monitoring of the shell side'water, and eddy current testing of tubes. 3.3.1-4 Stainless steel piping, Cracking due to Chapter Xl.M36, "External piping components, stress corrosion Surfaces Monitoring of and piping elements; cracking Mechanical Components" tanks exposed to air -outdoor 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific The Water Chemistry Control -Primary and Secondary Program manages cracking of stainless steel non-regenerative heat exchanger components exposed to treated borated water. The program is augmented by the One-Time Inspection Program which will verify the absence of cracking. Absence of cracking of the tubes and tubesheet is also verified by additional monitoring. See Section 3.3.2.2.2. Yes, environmental Consistent-with NUREG-1801 .. conditions need to be Cracking in stainless steel evaluated components exposed to outdoor air is managed by the External Surfaces Monitoring Program. See Section 3.3.2.2.3. Page 3.3-26 Table 3.3.1: Auxiliary Systems. Item Aging Effect/ Number Component Mechanism 3.3.1-5 Steel (with stainless Loss of material due steel or nickel-alloy to cladding breach cladding) pump casings exposed to treated borated water 3.3.1-6 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements; corrosion tanks exposed to air -outdoor 3.3.1-7 Stainless steel high-Cracking due to pressure pump, casing cyclic loading exposed to treated borated water 3.3.1-8 Stainless steel heat Cracking due to exchanger components cyclic loading and tubes exposed to
treated borated water >60°C (>140°F) 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated. Reference NRG Information Notice 94-63, "Boric Acid Corrosion of Charging Pump Casings Caused by Cladding Cracks." Chapter Xl.M36, "External Surfaces Monitoring of l\llechanical Components" Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" Ghapter Xl.M1, "ASME Section XI lnservice lns.pection, Subsections IWB, IWC, and IWD" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, verify that plant-The WF3 charging pump specific program casings are solid stainless steel. addresses clad cracking See Section 3.3.2:2.4. Yes, environmental Consistent with NUREG-1801. conditions need to be Loss of material in stainless evaluated steel components exposed to outdoor air is managed by the External Surfaces Monitoring Program.
See Section 3.3.2.2.5. No Consistent with NUREG-1801. Cracking of the stainless steel charging pump casings* due to cyclic loading is managed by the lnservice Inspection Program. No Consistent with NUREG-1801. Cracking of stainless steel heat exchanger components exposed to treated borated water >60°C (>140°F) is managed by the lnservice Inspection Program. Page 3.3-27 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-9 Steel, aluminum, Loss of material due copper alloy (>15% Zn to boric acid or >8% Al) external corrosion surfaces, piping, piping components, and piping elements, bolting exposed to air with borated water leakage 3.3.1-10 Steel, high-strength Cracking due to steel closure bolting stress corrosion exposed to air with cracking; cyclic steam or water loading leakage. 3.3.1-11 Steel, high-strength Cracking due to high-pressure pump, stress corrosion closure bolting exposed cracking; cyclic to air with steam or loading water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to boric acid corrosion of steel external surfaces is managed by the Boric Acid Corrosion Program. There are no aluminum or copper alloy (>15% Zn or >8% Al) auxiliary system components exposed to air with borated water leakage within the scope of license renewal. No Consistent with NUREG-1801. Cracking of high strength steel closure bolting is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Cracking of high strength steel, pump closure bolting is managed by the Bolting Integrity Program. Page 3.3-28 Table 3*.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-12 Steel; stainless steel Loss of material due closure bolting, bolting to general (steel exposed to only), pitting, and condensation, air -crevice corrosion indoor, uncontrolled (external), air-outdoor * (external) 3.3.1-13 Steel closure bolting Loss of material due exposed to air with to general corrosion steam or water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" .. ' Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel and stainless steel bolting is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, the Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. No As stated in Item 3.3.1-12, loss of material of steel bolting exposed to air in the auxiliary systems is managed by the Bolting Integrity Program. However, steam or water leakage is not considered as a *separate aspect of the indoor air environment. Page 3.3-29 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-14 Steel, stainless steel Loss of preload bolting exposed to soil 3.3.1-15 Steel; stainless steel, Loss of preload due copper alloy, nickel to thermal effects, alloy, stainless steel gasket creep, and closure bolting, bolting self-loosening exposed to air-indoor, uncontrolled (external), any environment, air -outdoor (external), raw water, treated borated water, fuel oil, treated water 3.3.1-16 BWR only 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of preload for steel bolting exposed to soil is managed by the Bolting Integrity Program. There is no stainless steel bolting exposed to soil in the auxiliary systems in scope for license renewal. No Consistent with NUREG-1801. Loss of preload for steel and stainless steel bolting exposed to relevant (indoor and outdoor air) environments is managed by the Bolting Integrity Program. There is no copper alloy or nickel alloy bolting in the auxiliary systems in scope for license renewal. Page 3.3-30 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-17 Stainless steel heat Reduction of heat exchanger tubes transfer due to exposed to treated fouling water, treated water (borated) 3.3.1-18 Stainless steel high-Cracking due to pressure pump, casing, stress corrosion piping, piping cracking components, and piping elements exposed to treated borated water >60°C (>140°F), sodium pentaborate solution >60°C (>140°F) 3.3.1-19 Stainless steel Cracking due to regenerative heat stress corrosion exchanger components cracking exposed to treated water >60°C (>140°F) 3.0 Aging Management Review Results ( Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No The operating temperature of the centrifugal charging pumps of the chemical and volume control system is below the 140°F threshold for cracking in stainless steel. No steel regenerative heat exchanger components are exposed to treated borated water >60°C (>140°F), and are addressed in Item 3.3.1-20. Page 3.3-31 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-20 Stainless steel, steel Cracking due to with stainless steel stress corrosion cladding heat cracking exchanger components exposed to treated borated water >60°C (>140°f), treated w:ater >60°C (>140°F) ' 3.3.1-21 BWRonly 3.3.1-22 BWRonly 3.3.1-23 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to treated water .3.3.1-24 BWR o'nly 3.3.1-25 BWRonly 3.3.1-26 Steel with stainless .Loss of material .due .steel cladding'piping; to pitting and crevice piping components, corrosion (only after and piping elements . cladding . exposed to treated degradation)
water 3.3.1-27 BWRonly 3.0 Aging Management Review Results Aging Management Programs
Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" / Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. . Cracking of stainless steel components exposed to treated borated water >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. No There are no aluminum auxiliary systems components exposed to treated water within the scope of license renewal. No There are no steel piping components in the WF3 fuel pool cooling system exposed to tre_ated water within the scope of license renewal. Page 3.3-32 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number . Component Mechanism 3.3.1-28 Stainless steel pipir:ig, Cracking due to piping components, stress corrosion and piping elements; cracking : tanks, exposed to treated borated water (pri.mary oxygen lev_els controlled) >60°C (>140°F) .. .. Steel (with stainless Loss of material due steel cladding); to pitting and crevice stainless steel piping, corrosion piping components, and piping elements exposed to treated borated water (primary oxygen levels controlled) .. " 3.0 Aging Management Re!view Results Aging Management Programs Chapter Xl.M2, "Water Chemistry" Chapter Xl.M2, "Water Chemistry". ' -Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No *Consistent with NUREG-1801 for stainless steel. components exposed to treated borated . water >60°C (>140°F). Cracking for these components is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify .the effectiveness of the water chemistry control program to manage cracking. No Consistent with NUREG-1801. Loss of material for stainless : steel components exposed to treated borated water is managed by the Water Chemistry Control -Primary and Se.condarY Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. Page 3.3-33 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-30 Concrete; cementitious Changes to material material piping, piping properties due to components, and aggressive chemical piping elements attack exposed to raw water -3.3.1-30.5 Fiberglass, HOPE Cracking, blistering, piping, piping change in color due components, and to water absorption piping elements exposed to raw water (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with l9w permeability. The pipe is exposed to raw water (river water) that is not aggressive. Consequently, changes in material properties is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no fiberglass or HOPE components exposed to raw water in the auxiliary systems in the scope of license renewal. Page 3.3-34

. Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-31 Concrete; cementitious Cracking due to Chapter Xl.M20, "Open-Cycle material piping, piping settling Cooling Water System" components, and piping elements exposed to raw water .. ,. 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping is included in scope for a rare tornado event. Bedding under this piping conforms to Class A .. or Class C as specified by the . American Concrete Pipe

Association which provides a densely compacted backfill limiting the potential for settlement leading to cracking of the concrete piping. Consequently, cracking of the piping due to settling is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. Page 3.3-35 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Co_mponent Mechanism '3.3.1-32 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, .and Changes in material piping elements properties due to exppsed to raw water aggressive chemical attack 3.3.1-32.5 Elastomer seals and Hardening and loss components exposed of strength due to to raw water elastomer degradation; loss of material due to erosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" .. Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with low permeability. The pipe is exposed to raw water (river water) that is r:iot aggressive. Consequently, cracking and changes in material properties are not significant aging effects for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no elastomer components exposed to raw water in the auxiliary systems in the scope of license renewal. Page 3.3-36 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-33 Concrete; cementitious Loss of material due material piping, piping to abrasion, components, and cavitation, piping elements aggressive chemical exposed to raw water attack, and leaching 3.3.1-34 Nickel alloy, copper Loss of material due . alloy piping, piping to general, pitting, components, and and crevice corrosion piping elements exposed to raw water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with low permeability. The pipe is exposed to raw water (river water) that is not aggressive. Consequently, loss of material is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no nickel alloy or copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other than the copper alloy heat exchanger components compared to Item 3.3.1-38 below. Page 3.3-37 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-35 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements crevice, and exposed to raw water microbiologically influenced corrosion 3.3.1-36 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements crevice, and exposed to raw water microbiologically influenced corrosion; fouling that leads to corrosion 3.3.1-37 Steel piping, piping Loss of material due components, and to general, pitting, piping elements crevice, and exposed to raw water microbiologically influenced corrosion; fouling that leads to corrosion 3.3.1-38 Copper alloy, steel heat Loss of material due exchanger components to general, pitting, exposed to raw water crevice,* galvanic, and microbiologic*ally influenced corrosion; fouling tha_t leads to corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle . Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open'-Cycle Cooling Water System" . Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other than the heat exchanger components compared to Item 3.3.1-38 below. No There are no copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other the heat exchanger components compared to Item 3.3.1-38 below. No Consistent with NUREG-1801. Loss of material for steel components exposed to raw water is managed by the Service
Water Integrity Program. No Consistent with NUREG-1801 . Loss of material for copper alloy and steel heat exchanger exposed to raw water is managed by the Service Water Integrity Program. Page 3.3-38 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-39 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to raw water 3.3.1-40 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion; fouling exposed to raw water that leads to corrosion 3.3.1-41 Stainless steel piping, Loss of material due piping components, to pitting, crevice, and piping elements and microbiologically exposed to raw water influenced corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Stainless steel piping components exposed to raw water are addressed in Item 3.3.1-40. No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to raw water is managed by the Service Water Integrity Program. No Stainless steel piping components exposed to raw water are addressed in Item 3.3.1-40. Page 3.3-39 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-42 Copper alloy, titanium, Reduction of heat Chapter Xl.M20, "Open-Cycle stainless steel heat transfer due to Cooling Water System" exchanger tubes fouling exposed to raw water 3.3.1-43 Stainless steel piping, Cracking due to Chapter Xl.M21A, "Closed piping components, stress corrosion Treated Water Systems" and piping elements cracking exposed to closed-cycle cooling water >60°C (>140°F) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to raw water is managed by the Service Water Integrity Program. For the fire pump diesel cooler, reduction of heat transfer for the copper alloy heat exchanger tubes exposed to raw water is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. There are no titanium heat exchanger tubes exposed to raw water with a heat transfer intended function in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Cracking of stainless steel components exposed to closed-cycle cooling water >60°C (>140°F) is managed by the Water Chemistry Control -Closed Treated Water Systems Program. Page 3.3-40 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-44 Stainless steel; steel Cracking due to with stainless steel stress corrosion cladding heat cracking exchanger components exposed to closed-cycle cooling water >60°C {>140°F) 3.3.1-45 Steel piping, piping Loss of material due components, and to general, pitting, piping elements; tanks and crevice corrosion exposed to closed-cycle cooling water 3.3.1-46 Steel, copper alloy heat Loss of material due exchanger to general, pitting, components, piping, and crevice, and piping components, galvanic corrosion and piping elements exposed to closed-cycle cooling water 3.3.1-47 BWRonly 3.3.1-48 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to closed-cycle cooling water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless steel heat exchanger components exposed to closed-cycle cooling water >60°C {>140°F) is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material for steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material for steel and copper alloy components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No There are no aluminum components exposed to closed-cycle cooling water in the auxiliary systems in the scope of license renewal. Page 3.3-41 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-49 Stainless steel piping, Loss of material due piping components,. to pitting and crevice and piping elements corrosion exposed to closed-cycle cooling water .. 3.3.1-50 Stainless steel, copper Reduction of heat alloy, steel heat transfer due to exchanger tubes fouling exposed to closed-cycle cooling water 3.3.1-51 Boraflex spent fuel Reduction of storage racks: neutron-neutron-absorbing absorbing sheets capacity due to (PWR), spent fuel boraflex degradation storage racks: neutron-absorbing sheets (BWR) exposed to treated borated water, treated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M22, "Boraflex Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control :.... Closed Treated Water Systems Program. No Consistent with NUREG-1801. Reduction of heat transfer for steel, stainless steel and copper alloy heat exchanger tubes exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Boraflex is n.ot used in the WF3 spent fuel storage racks. Page 3.3-42 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-52 Steel cranes: rails and Loss of material due structural girders to general corrosion exposed to air-indoor, uncontrolled (external) 3.3.1-53 Steel cranes -rails Loss of material due exposed to air-indoor, to wear uncontrolled (external) 3.3.1-54 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements and crevice corrosion exposed to condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems" Chapter Xl.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems" ' Chapter Xl.M24, "Compressed Air Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel crane rails and structural girders exposed to indoor air is managed by the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems {Inspection of OVHLL) Program. This item applies to aging management review results presented in Tables 3.5.2-X. No Visual inspections under the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program manage loss of material. No Consistent with* NUREG-1801. Loss of material for copper alloy components exposed to condensation is managed by the Compressed Air Monitoring Program. Page 3.3-43 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-55 Steel piping, piping Loss of material due components, and to general and pitting piping elements: corrosion compressed air system exposed to condensation (internal) 3.3.1-56 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to condensation (internal) 3.3.1-57 Elastomers fire barrier Increased hardness; penetration seals shrinkage; loss of exposed to air -indoor, strength due to uncontrolled, air -weathering outdoor 3.3.1-58 Steel Halon/carbon Loss of material due dioxide fire suppression to general, pitting, system piping, piping and crevice corrosion components, and piping elements exposed to air -indoor, uncontrolled (external) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M24, "Compressed Air Monitoring" Chapter Xl.M24, "*Comp*ressed Air Monitoring" Chapter Xl.M26, "Fire Protection" Chapter Xl.M26, "Fire Protection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation -Recommended Discussion No Consistent with Loss of material for steel components exposed to condensation is managed by the Compressed Air Monitoring Program.
No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to condensation is managed by the Compressed Air Monitoring Program. No Consistent with NUREG-1801. Increased hardness, shrinkage and loss of strength of elastomer fire barrier seals exposed to indoor air are managed by the Fire Protection Program. This item applies to aging review results presented in Table 3.5.2-4. No Consistent with NUREG-1801.
Loss of material for steel fire protection components exposed '. to indoor air is managed by the Fire Protection Program. This item applies to aging management review results presented in Table 3.5.2-3. Page 3.3-44 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-59 Steel fire rated doors Loss of material due exposed to air -indoor, to wear uncontrolled, air-outdoor 3.3.1-60 Reinforced concrete Concrete cracking structural fire barriers: and spalling due to walls, ceilings and aggressive chemical floors exposed to air -attack, and reaction indoor, uncontrolled with aggregates 3.3.1-61 Reinforced concrete Cracking, loss of strliCtural fire barriers: material due to walls, ceilings and freeze-thaw, floors exposed to air -aggressive chemical outdoor attack, and reaction with aggregates 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M26, "Fire Protection" Chapter Xl.M26, "Fire Protection," and Chapter Xl.S6, "Structures Monitoring" Chapter Xl.M26, "Fire Protection," and Chapter Xl.S6, "Structures Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of steel fire doors is managed by the Fire Protection Program. This item applies to aging management review results presented in Table 3.5.2-X. No Consistent with NUREG-1801. Cracking of concrete fire barriers exposed to indoor air is managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. No Consistent with NUREG-1801. Cracking and loss of material of concrete fire barriers exposed to outdoor air are managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. Page 3.3-45 Table 3.3: 1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-62 Reinforced concrete Loss of material due structural fire barriers: to corrosion of walls, ceilings and embedded steel floors exposed to air -indoor, uncontrolled, air -outdoor 3.3.1-63 Steel fire hydrants Loss of material due exposed to air -to general, pitting, outdoor and crevice corrosion 3.3.1-64 Steel, copper alloy Loss of material due piping, piping to general, pitting, components, and crevice, and piping elements microbiologically exposed to raw water influenced corrosion; fouling that leads to corrosion; flow blockage due to fouling 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M26, "Fire Protection," and Chapter XI.SS, "Structures Monitoring" Chapter Xl.M27, "Fire Water System" Chapter Xl.M27, "Fire Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of concrete fire barriers exposed to indoor or outdoor air is managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. No Consistent with NUREG-1801. Loss of material for steel fire hydrants exposed to outdoor air is managed by the Fire Water System Program. No Consistent with NUREG-1801. Loss of material for steel and copper alloy fire protection system components exposed to raw water is managed by the Fire Water System Program. Page 3.3-46 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-65 Aluminum piping, piping Loss of.material due components, and to pitting and crevice piping elements corrosion, fouling exposed to raw water
that leads to corrosion; flow blockage due to fouling 3.3.1-66 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements . corrosion; fouling exposed to raw water that leads to corrosion; flow blockage due to fouling 3.3.1-67 Steel tanks exposed to Loss of material due air -outdoor to general, pitting, and crevice corrosion I 3.3.1-68 Steel piping, piping Loss of material due components, and to general, pitting, piping elements and crevice corrosion exposed to fuel oil 3.0. Aging Management Review Results Aging Management Programs Chapter Xl.M27, "Fire Water System" ) Chapter Xl.M27, "Fire Water System" Chapter Xl.M29, "Ahqveground MetalliG Tanks" Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32 *. "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical *Further Evaluation Recommended Discussion No There are no aluminum auxiliary system components exposed to raw water in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for stainless steel fire protection system components exposed to raw water is managed by the Fire Water System Program. No The only steel tank exposed to outdoor air in the scope of license renewal is the fire water
storage tank. Loss of material for the fire water storage tank is addressed in Item 3.3.1-136. No Consistent with NUREG-1801. Loss of material for steel components exposed *to fuel oil is managed by the Diesel Fuel Monitoring Program. The One-Time Inspection Program will verify the effediveness of the Diesef Fuel Monitoring Program to manage loss of material. Page 3.3-47 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-69 Copper piping, Loss of material _due piping compon.ents, to general, pitting, and piping elements crevice, and exposed to fuel oil microbiologically influenced corrosion 3.3.1-70 Steel piping, piping Loss of material due components, ar:id to general, pitting, piping. elements; tanks crevice, and exposed to fuel oil microbiologically influenced corrosion; fouling that leads to corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to fuel oil is managed by the Diesel Fuel Monitoring Program. The One-Time Inspection Program will, verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for steel components exposed to fuel oil is managed by the Diesel Fuel Monitoring The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. Page 3.3-48 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number* Component Mechanism 3.3.1-71 Stainless steel, Loss of material due aluminum piping, piping to pitting, crevice, components, and and microbiologically piping elements influenced corrosion exposed to fuel oil 3.3.1-72
Gray cast iron, copper Loss of material due alloy (>15% Zn or >8% to selective leaching Al) piping, piping components, and piping elements, heat exchanger components exposed to.treated water, closed-cycle cooling water, soil, raw water, waste water 3.3.1-73 Concrete; cementitious Changes in material material piping, piping properties due to components, and aggressive chemical piping elements attack exposed to air -outdoor 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" . Chapter Xl.M33; "Selective Leaching" Chapter Xl.M36, "External Surfaces Monitoring of
Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to fuel oil is managed by the Diesel Fuel M.onitoring Program. The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. There are no aluminum components exposed to fuel oil in the scope of license renewal. No Consistent with. NUREG-1801. Loss of material due to selective leaching for gray cast iron and copper alloy (>15% Zn or >8% Al) components is managed by the Selective Leaching Program. -No There are no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. Page 3.3-49 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-74 Concrete; cementitious Cracking due to material piping, piping settling components, and piping elements exposed 'to air -outdoor 3.3.1-75 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, and Changes in material piping elements properties due to exposed to air -aggressive chemical outdoor attack 3.3.1-76 Elastomers elastomer: Hardening and loss seals and components of strength due to exposed to air-indoor, elastomer uncontrolled (internal/ degradation external) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No There are no reinforced concrete or asbestos cement components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801 for most components. Cracking and change in material properties of elastomer components exposed to indoor air are managed by the External Surfaces Monitoring Program. The Periodic Surveillance and Preventive Maintenance Program manages these aging effects for the portable flexible duct that can be used with the portable smoke exhaust fan in the control room HVAC system. Page 3.3-50 Table 3.3.1: Auxiliary Systems Item Number Component 3.3.1-77 Concrete; cemerititious material piping, piping components, and , piping elements exposed to air -outdoor 3.3.1-78 Steel piping and components (external surfaces), ducting and components (external surfaces), ducting; closure bolting exposed to air -indoor, uncontrolled (external), air -indoor, uncontrolled (external), air-outdoor (external), condensation (external) 3.3.1-79 Copper alloy piping, piping components, and piping elements exposed to condensation (external) 3.0 Aging Management Review Results Aging Effect/ Aging Management Mechanism Programs Loss of material due Chapter Xl.M36, "External to abrasion, Surfaces Monitoring of cavitation, Mechanical Components" aggressjve chemical attack, and leaching Loss of material due Chapter Xl.M36, "External to general corrosion Surfaces Monitoring of Mechanical Components" Loss of material due . Chapter XLM36, "External to general, pitting, Surfaces Monitoring of and crevice corrosion Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Eva I uation Recommended Discussion No There are .no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801 for most components. *Loss of material for most steel components exposed to indoor air, outdoor air or condensation is managed by the External Surfaces Monitoring Program. The Periodic Surveillance and Preventive Maintenance Program manages loss of material for the portable steel smoke exhaust fan. No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to condensation is managed by the External Surfaces Monitoring Program. Page 3.3-51 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component *Mechanism 3.3.1-80 Steel heat exchanger Loss of material due components, piping, to general, pitting, piping components, and crevice corrosion and piping elements exposed to air -indoor, uncontrolled (external), air-outdoor (external) 3.3.1-81 Copper alloy, aluminum Loss of material due piping, piping to pitting and crevice components, and corrosion piping elements exposed to air -outdoor (external), air-outdoor 3.3.1-82 Elastomers elastomer: Loss of material due seals and components to wear exposed to air -indoor, uncontrolled (external) 3.3.1-83 Stainless steel diesel Cracking due to engine exhaust piping, stress corrosion piping components, cracking and piping elements exposed to diesel exhaust 3.3.1-84 [There is no 3.3.1-84 in NUREG-1800] 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel components exposed to indoor or outdoor air is managed by the External Surfaces Monitoring Program. No Consistent with NUREG-1801. Loss of material for copper alloy and aluminum components exposed to outdoor air is managed by the External Surfaces Monitoring Program. No Consistent with NUREG-1801. Wear of external surfaces of elastomer components exposed to indoor air is managed by the External Surfaces Monitoring Program. No Cracking of stainless steel diesel engine exhaust components is managed by the Periodic Surveillance and Preventive Maintenance Program. Page 3.3-52 Table 3.3.1: Auxiliary Systems Item .. Aging Effect/ Number Component Mechanism 3.3.1-85 Elastomers elastomer Hardening and loss . seals and components of strength due to exposed to Closed-elastomer cycle cooling water degradation 3.3.1-86 Elastomers elastomers, Hardening and loss linings, elastomer: of strength due to seals and components elastomer exposed to treated degradation borated water, treated water, raw water 3.3.1-87 [There is no 3.3.1-87 in NUREG-1800.] 3.3.1-88 Steel; stainless steel Loss of material due piping, piping to general (steel components, only), pitting, and piping elements, piping, crevice corrosion piping components, and piping elements, diesel engine exhaust exposed to raw water i (potable), diesel exhaust 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in . Miscellaneous Piping arid Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no elastomer components exposed to closed-cycle cooling water in the auxiliary systems in the scope of license renewal. No There are no elastomer components exposed to treated
borated water, treated water or raw water in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for steel and stainless steel components exposed to diesel exhaust or raw water (potable) is managed by
the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-53 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-89 Steel, copper alloy Loss of material due piping, piping to general, pitting, components, and and crevice corrosion piping elements exposed to moist air or condensation (internal) 3.3.1-90 Steel ducting and Loss of material due components (internal to general, pitting, surfaces) exposed to crevice, and (for drip condensation (internal) pans and drain lines) microbiologically influenced corrosion 3.0 Aging Management Review Results Aging Management Programs For fire water system components: Chapter Xl.M27, "Fire Water System," or for other components: Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" -Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel and copper alloy components exposed to condensation is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Steel and copper alloy fire water system piping components exposed to condensation are addressed in Item 3.3.1-131. No There are no steel duct components internally exposed to condensation in the auxiliary systems in the scope of license renewal. Page 3.3-54 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-91 Steel piping, piping Loss of material due components, and to general, pitting, piping elements; tanks crevice, and exposed to waste water microbiologically influenced corrosion 3.3.1-92 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to condensation (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl'.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most steel components exposed to waste water. For these components, loss of material is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. The Periodic Surveillance and Preventive Maintenance Program uses periodic visual inspections or other NOE techniquesto manage loss of material for steel components abandoned in place. No Aluminum components within scope of license renewal that are -exposed to internal condensation, are associated with compressed air systems. Loss* of material for these aluminum components is by the Compressed Air Monitoring Program. Page 3.3-55 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-93 Copper alloy piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to raw water (potable) 3.3.1-94 Stainless steel ducting Loss of material due and components to pitting and crevice exposed to corrosion condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to raw water (potable) is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. No Consistent with NUREG-1801. Loss of material for stainless steel components internally exposed to condensation is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-56 i Table 3.3.1: Auxiliary Systems Item Aging Effect/ ; Number Component Mechanism 3.3.1-95 Copper alloy, stainless Loss of material due steel, nickel alloy, steel to pitting, crevice, piping, piping and microbiologically components, and
influenced corrosion piping elements, heat ' exchanger i components, piping, piping components, and piping elements; tanks exposed to waste. water, condensation (internal) " .. 3.0 Aging Management Review Results Aging Management Programs Chapter XLM38, "Inspection of Internal Surfaces in Miscellaneous Piping and pucting Components" ' Waterford Steam .Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation *Discussion No Consistent with NUREG-1801 for most copper alloy and stainless components exposed to waste water or condensation. For these components, 1.oss of material is managed by the Internal Surfaces. in Miscellaneous Piping and Ducting Components Program. The Periodic Surveillance and Preventive Maintenance Program uses periodic visual inspections or other NDE techniques to manage ioss of material for components abandoned in place. There. are no nickel alloy. components exposed to waste water in the auxiliary systems in the scope of license renewal. Steel .. components internally exposed to condensation are addressed in Items 3.3.1-55, 3.3.1-89, 3.3.1-131*and 3.3.1-136 . Page 3:3-!?7 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-96 Elastomers elastomer: Loss of material due seals and components to wear exposed to air-indoor, uncontrolled (internal) 3.3.1-97 Steel piping, piping Loss of material due components, and to general, pitting, piping elements, and crevice corrosion reactor coolant pump oil collection system: tanks, reactor coolant pump oil collection system: piping, tubing, valve bodies exposed to lubricating oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most components. Wear of internal surfaces of elastomer components exposed to indoor air is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Wear of the portable duct used with the portable smoke exhaust fan is managed by the Periodic Surveillance and Preventive Maintenance Program. No Consistent with NUREG-1801
for most components. Loss of material for most steel components exposed to lube oil is managed bY the Oil Analysis Program. The One-Time 1.nspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. The Periodic Surveillance and Preventive Maintenance Programs uses periodic visual inspections to. manage loss of material for steel reactor co.olant pump oil collection system components exposed to lube oil. Page 3.3-58 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-98 Steel heat exchanger Loss of material due* components exposed to general, pitting .. to lubricating oil* crevice, and microbiologically influenced corrosion;
fouling that leads to corrosion 3.3.1-99 Copper alloy, aluminum Loss of material due piping, piping to pitting and crevice components, and corrosion piping elements exposed to lubricating oil 3.0 Aging .Management Review Results ( \. Aging Management Programs Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel heat exchanger components exposed
to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will
verify the effectiveness of the Oil Analysis Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for copper alloy and aluminum components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. Page 3.3-59 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-100 Stainless steel piping, Loss of material due piping components,
to pitting, crevice, and piping elements and microbiologically exposed to lubricating influenced corrosion oil -3.3.1-101 Aluminum heat Reduction of heat exchanger tubes transfer due to exposed to lubricating fouling oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most components. Loss of material for stainless steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis to manage loss of material. For stainless steel components in the RCP oil collection subsystem of the fire protection equipment, the Periodic Surveillance and Preventive Maintenance and External Surfaces Monitoring Programs manage loss of material. No There are no aluminum heat exchanger tubes exposed to lube oil with an intended function of heat transfer in systems in the scope of license renewal. Page 3.3-60 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-102 Boral; boron steel, Reduction of and other materials neutron-absorbing (excluding Boraflex) capacity; change in spent fuel storage dimensions and loss racks: neutron-of material due to absorbing sheets effects of SFP (PWR), spent fuel environment storage racks: neutron-absorbing sheets (BWR) exposed to treated borated water, treated water 3.3.1-103 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, and Cl]anges in material piping elements properties due to exposed to soil or aggressive chemical concrete attack 3.3.1-104 HOPE, fiberglass Cracking, blistering, piping, piping change in color due components, and to water absorption piping elements exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M40, "Monitoring of Neutron-Absorbing Materials other than Boraflex" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction in neutron absorption capacity, change in material properties and loss of material for Baral is managed by the Neutron-Absorbing Material Monitoring Program. The Water Chemistry Control -Primary and Secondary Program supplements management of loss of material. No The nonsafety-related concrete circulating water intake piping is addressed in Item 3.3.1-105. -No There are no fiberglass or HOPE components exposed to soil or concrete in the systems in the scope of license renewal. Page 3.3-61 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-105 Concrete cylinder Cracking, spalling, piping, asbestos corrosion of rebar cement pipe piping, due to exposure of piping components, rebar and piping elements exposed to soil or concrete 3.3.1-106 Steel (with coating or Loss of material due wrapping) piping, piping to general, pitting,
components, and crevice, and piping elements microbiologically exposed to soil or influenced corrosion concrete 3.3.1-107 Stainless steel, nickel Loss of material due alloy piping, piping to pitting and crevice components, and corrosion piping elements exposed to soil or concrete 3.3.1-108 Titanium, sµper Loss of material due austenitic, aluminum, to pitting and crevice copper alloy, stainless corrosion steel, nickel alloy piping, piping components, and piping elements, bolting exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Burieq and Underground Piping and Tanks" Chapter Xl.M4t, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter XLM41, "Buried and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking and loss of material for concrete piping exposed to soil .is managed by the Buried and Underground Piping and Tanks Inspection Program. No Consistent with NUREG-1801. Loss of materiar for steel components exposed to soil is managed by the Buried and Underground Piping and Tanks Inspection Program. No There are no stainless steel or nickel alloy components exposed to soil or concrete in the auxiliary systems in the scope of license renewal. No None of the component type, material and environment combinations represented by . this item apply to components in . systems included in the scope of license renewal. Page 3.3-62 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-1.09 Steel bolting exposed . Loss of material due to soil or concrete to general, pitting and crevice corrosion 3.3.1-109.5 Underground . Loss of material due aluminum; copper alloy, to general (steel stainless steel, nickel only), pitting and alloy, steel piping, crevice corrosion
piping components, and piping elements 3.3.1-110 BWRonly 3.3.1-111 Steel structural steel Loss of material due exposed to air-indoor, to general, pitting, uncontrolled (external) and crevice corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Buried and Underground Piping and Tanks" *. .. Chapter XI. M41, "Buried and Underground Piping and Tanks" Chapter Xl.S_6, "Structures Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation
Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel bolting exposed to soil is managed.by* the Buried and Underground Piping and Tanks Inspection Program. There is no steel bolting embedded in concrete in systems in the.scope of license renewal. No There are no underground components in auxiliary systems in the of license renewal. No Aging management review results for structural steel components are presented in and compared to NUREG-1801 items in Section 3.5. Page 3.3-63 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-112 Steel piping, piping None components, and piping elements exposed to concrete 3.3.1-113 Aluminum piping, piping None components, and piping exposed to air -dry (internal/external), air -indoor, uncontrolled (internal/eXternal), air -indoor, controlled (external), gas 3.3.1'-114 Copper alloy piping, . None piping components, and piping elements exposed to air -indoor, uncontrolled (internal/ external), air-dry, gas 3.0 Aging Management Review Results Aging Management Programs None, provided 1) attributes of the concrete are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and
adequate air entrainment) as cited in NUREG-1557, and 2) plant OE indicates no degradation of the concrete None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No, if conditions are Consistent with NUREG-1801. met. Embedded steel components are in concrete that meets the guidelines of ACI 318 for safety-related concrete structures. Operating experience indicates n6 aging-related degradation of this concrete. NA-NoAEM or* Consistent with NUREG-1801 AMP for relevant (indoor air and gas) environments. NA-NoAEM or Consistent with NUREG-1801 AMP . for relevant (indoor air and gas) environments. Page 3.3-64 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-115 . Copper alloy (S15% Zn None and S8% Al) piping, piping components, and piping elements *. exposed to air with . borated water leakage 3.3.1-116
Galvanized steel piping,. None piping components, and piping elements exposed to air -indoor, uncontrolled 3.3.1-117 Glass piping elements None exposed to air -indoor, uncontrolled (external), lubricating oil, closed-cycle cooling water, air -outdoor, fuel oil, raw water, treated water, treated borated water, air with borated water leakage, condensation (internal/external) gas 3.3.1-118 Nickel alloy piping, None 'piping components, and piping elements exposed to air-indoor, .** uncontrolled (external) ' 3.0 Aging Management Review Results Aging Management Programs None None
None None .,. .. Waterford Steam Electric Station, Unit 3 License Renewal Application Tech 11 ical .. 1 nformation Further.Evaluation Recommended Discussion NA -No AEM or AMP There are no cepper alloy (S15% Zn or S8% Al) components exposed to air with borated water leakage in the auxiliary systems in the scope of license renewal. NA-NoAEM or Galvanized (zinc) coating AMP applied to some steel components is not credited for corrosion protection for license. renewal. or Consistent with NUREG-1801 'AMP
for relevant (indoor air, air with borated water leakage, closed-cycle* cooling water,.
condensatioil, lube oil, raw water, treated borated water.and treated water) environments. NA-NoAEM or There are no nickel alloy AMP components in the auxiliary systems in the scope of license * renewal. Page 3.3-65 Table 3.3.1: Auxil_iary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-119 Nickel alloy, PVC, glass None piping, piping components, and piping elements exposed to air with borated water leakage, air -indoor, uncontrolled, condensation (internal), wastewater 3.3.1-120 Stainless steel piping, None piping components, and piping elements .' exposed to air-indoor, uncontrolled (internal/ external), air -indoor, uncontrolled (external), air with borated water leakage, concrete, air-dry, gas 3.3.1-121 Steel piping, piping None
components, and
piping elements exposed to air -indoor, controlled (external), air -dry, g.as 3.0 Aging Management Review Results Aging Management Programs None .. None ' None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion NA-NoAEM or Consistent with NUREG-1801 AMP for glass components exposed to waste water. Other material environment combinations represented by this item are not applicable to auxiliary system components in the scope of license. renewal. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air, air with borated water leakage, and gas) environments. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (gas) environment. .. Page 3.3-66 Table 3.;t 1: Auxiliary Systems Item Number Component 3.3.1-122 Titanium !:teat exchanger components, piping, piping components, and piping elements exposed to air-indoor, uncontrolled or air -* outdoor 3.3.1-123 Titanium (ASTM Grades 1,2, 7, 11, or 12 that contains > 5% aluminum or mo.re than 0.20% oxygen or any amount of tin) heat exchanger components other than tubes, piping, piping .. comporents, and piping *elements exposed to raw water 3.0 Aging Management Review Results Aging Effect/ Aging Management Mechanism *Programs* .. None None . None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation
Recommended * .Discussion NA-NoAEM or There are no titanium AMP , components included in systems in the scope of license renewal. NA.:...NoAEM or There are no titanium AMP components included in systems in the scope of license renewal. Page 3.3-67 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-124 Stainless steel, steel Cracking due to (with stainless steel.or stress corrosion nickel-alloy cladding) cracking spent fuel storage racks (BWR), spent fuel storage racks (PWR), piping, piping components, and piping elements; exposed to treated water >60°C (>140°F), treated borated water >60°C (>140°F) 3.3.1-125 Steel (with stainless Loss of material due steel cladding); to pitting and crevice stainless steel spent corrosion fuel storage racks (BWR), spent fuel storage racks (PWR), piping, piping components, and piping elements exposed to treated water, treated borated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Wate( Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking for stainless steel components exposed to treated borated water (primary) >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. The spent fuel pool is normally maintained at a temperature below 140°F, consequently, cracking is not a significant aging effect for the stainless steel spent fuel pool components. No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to treated borated water is managed by the Water Chemistry* Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.3-68 Table 3.3.1: Auxiliary Systems Item Aging Effect/ ,
Number Component Mechanism 3.3.1-126 Any material, piping, Wall thinning due to piping components, erosion and piping elements exposed to treated water, treated water . (borated), raw water 3.3.1-127 Metallic piping, piping Loss of material.due components, and .tanks to recurring internal exposed to raw water or Corrosion waste water 3.3.1-128 Steel, stainless steel, or Loss of material due aluminumtanks (within to general (steel the scope. of Chapter only), pitting, or Xl.M29, "Aboveground crevice corrosion; Metallic Tanks") cracking due to exposed to soil or stress corrosion concrete, orthe cracking (stainless following external steel and aluminum environments only) outdoor, air-indoor uncontrolled, moist air, condensation 3.0 Aging Management Review Results Aging Management . Programs Chapter Xl.M17, "Flow-Accelerated Corrosion" A aging management program is to be evaluated to address recurring internal corrosion *Chapter Xl.M29, "Aboveground Metallic Tanks" .. Waterford Steam Electric Station, Unit 3 Renewal Application Technical Information Further Evaluation Recommended Discussion No Consist,ent with NUREG-1801. Loss of material due to erosion for steel components exposed to raw water is managed by the Flow.,Accelerated Corrosion Program . Yes, For carbon steel piping of: the fire plant-specific protection system, loss of material due to recurring internal corrosion is managed by the Fire Water System Program. See Se".tion 3 .. 3.2.2.8. No At WF3, there are no tanks within the scope of Chapter XLM29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capaCity greater than 100,000 gallons. Page 3.3-69 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-129 Steel tanks exposed to Loss of material due soil or concrete; air-to general, pitting, indoor uncontrolled, and crevice corrosion raw water, treated water, waste water, condensation 3.3.1-130 Metallic sprinklers Loss of material due exposed to air-indoor to general (where controlled, air-indoor applicable}, pitting, uncontrolled, air-crevice, and outdoor, moist air, microbiologically-condensation, raw influenced corrosion, water, treated water fouling that leads to corrosion; flow blockage due to fouling 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, "Aboveground Metallic Tanks" Chapter Xl.M27, ."Fire Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Loss of material for the steel fire water storage tank constructed on soil and concrete is managed by the Fire Water System Program. No Consistent with NUREG-1801. Loss of material for sprinklers exposed to condensation or raw water is managed by the Fire Water System Program. Page 3.3-70 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-131 Steel, stainless steel, Loss of material due
copper alloy, or to general (steel, and aluminum fire water copper alloy only), system piping, piping pitting, crevice, and components and piping microbiologically-elements exposed to influenced corrosion, air-indoor uncontrolled fouling that leads to (internal), air-outdoor corrosion; flow (internal), or blockage due to condensation (internal) fouling 3.3.1-132 Insulated steel, Loss of material due stainless steel, copper to general (steel, and alloy, aluminum, or copper alloy only), copper alloy(> 15% Zn) pitting, and crevice piping, piping corrosion; cracking components, and tanks due to stress exposed to corrosion cracking condensation, air-(aluminum, stainless outdoor steel and copper alloy (>15% Zn) only) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M27, "Fire Water System" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, .Aboveground Metallic Tanks" (for tanks only) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for* most components. Loss of material for steel, copper alloy and stainless steel fire water system components internally exposed to condensation is managed by the Fire Water System Program. For the fire water system piping and flame arrestor exposed internally to outdoor air, the Internal Surfaces in Miscellaneous Piping and Ducting Components Program manages loss of material. No with NUREG-1801 for insulated carbon steel, copper alloy and stainless steel components exposed to condensation or outdoor air. Loss of material and cracking (stainless steel only) is managed by the External Surfaces Monitoring Program. There are no insulated a.luminum or copper alloy > 15% Zn or > 8% Al piping components in auxiliary systems in the scope of license renewal. Page 3.3-71 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-133 Underground HOPE Cracking, blistering, piping, piping change in color due components, and piping to water absorption elements in an air-indoor uncontrolled or condensation (external) environment 3.3.1-134 Steel, stainless steel, or Loss of material due copper alloy piping, to general (steel and piping components, and copper alloy only), piping elements, and pitting, crevice, and heat exchanger microbiologically components exposed to influenced corrosion, a raw water fouling that leads to environment (for corrosion nonsafety-related components not covered by NRC GL 89-13) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.Ml.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no underground components in auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for nonsafety-related steel, stainless steel and copper alloy components exposed to raw water (not covered by NRC GL 89-13) is. managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-72 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-135 Steel or stainless steel Loss of material due pump casings to general (steel submerged in a waste only), pitting, crevice, water (internal and and microbiologically external) environment influenced corrosion 3.3.1-136 Steel, stainless steel or Loss of. material due aluminum fire water to general (steel storage tanks exposed only), pitting, crevice, to air-indoor and uncontrolled, air* microbiologically-outdoor, condensation, influenced corrosion,
moist air, raw water, fouling that leads fo treated water corrosion; cracking due to stress corrosion cracking (stainless steel and aluminum only) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.Ml.M36, "External Surfaces Monitoring of Mechan'ical Components" Chapter Xl.M27, "Fire Water System" .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with for some components. Loss of material for external steel surfaces exposed to waste water is managed by the External Surfaces Monitoring Program. Loss of material for internal steel surfaces exposed to waste water is managed by the Periodic
Surveillance and Preventive Maintenance Program using periodic visual inspections. No Consistent with NUREG-1801. Loss of material for steel and stainless steel components exposed to outdoor air, condensation or raw water is managed by the Fire Water System Program. Page 3.3-73 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-137 Steel, stainless steel or Loss of material due aluminum tanks (within to general (steel the scope of Chapter only) pitting and Xl.M29, "Aboveground crevice corrosion Metallic Tanks") exposed to treated water, treated borated water 3.3.1-138 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-delamination, ** cycle cooling water, raw. rusting, or physical water, treated water, damage, and spalling treated borated water, for cementitious waste water, lubricating coatings/linings oil, or fuel oil 3.3.1-139 Metallic piping, piping Loss of material due: components, heat to general, pitting, exchangers, tanks with crevice, and internal*coatings/linings microbiologically exposed to closed-influenced corrosion; cycle cooling water, raw fouling that leads to . water, treated water, corrosion treated borated water, or lubricating oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, "Aboveground Metallic Tanks" Chapter Xl.M42, "Internal Coatings/Linings for h-Scope Piping, Piping Components, Heat Exchangers, and Tanks" Chapter Xl.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks" ' Waterford Steam Electric Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater,than 100,000 gallons. No Consistent with NUREG-1801. Loss of coating or lining integrity for metallic components with internal coating or linings is managed by the Coating Integrity Program. No Consistent with NUREG-1801. Loss of material for metallic components with internal coating or linings is managed by the Coating Integrity Program. '.* Page 3.3-74 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Mechanism 3.3.1-140 Gray cast iron piping Loss of material due *components with to selective leaching internal coatings/linings exposed to closed-cycle cooling water, raw water,_ or treated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M42, "Internal Coatings/Linings for In-Scope* Piping, Piping Components, Heat Exchangers, and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to selective leaching for gray cast iron components with internal coating or linings.is managed by the Coating Integrity Program. Page 3.3-75 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Notes for Tables 3.3.2-1 through 3.3.2-15-36 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neitherthe component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 301. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 302. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 303. The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program. 304. This tank is located indoors and is seated on (not embedded in) concrete. 305. These components have openings that expose the internal surfaces to outdoor air. Because the internal and external surfaces are exposed to the same environments, aging effects of the internal surfaces can be inferred from external surface conditions. 3.0 Aging Management Review Results Page 3.3-76 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 306. The (int) and (ext) environment designations refer to the nominal internal and external surfaces of the component and may not be consistent with the internal and external environment designations used in NUREG:-1801. Consequently, an air or condensation (ext) environment for a component contained within a duct or other enclosure can correspond directly to a NUREG-1801 air or condensation (internal) environment. 307. This treated water is equivalent to the NUREG-1801 closed-cycle cooling water environment. 308. The aging mechanism for loss of material in this line is selective leaching. 3.0 Aging Management Review Results Page 3.3-77 Table 3.3.2-1 Chemical and Volume Control System Summary of Aging Management Evaluation Table 3.3.2-1: Chemical and Volume Control System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Programs Accumulator Pressure Stainless ste*e1 Air-indoor None None boundary (ext). Accumulator Pressure* Stainless steel Treated borated Loss of material Chemistry boundary water (int) Control -Primary and Secondary Bolting Press we Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of preload Bolting .integrity boundary steel (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary (ext) Demineralizer Pressure Stainless steel Air-indoor None None boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-Table 1 1801 Item Notes Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.l.AP-125 3.3.1-12 B Vll.l.A-102 3.3.1-9 A Vll.l.AP-124 3.3.1-15 B Vll.E1.AP-122 3.3.1-11 B Vll.1.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15. B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-18 3.3.1-120 A Page 3.3-78 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Demineralizer Pressure Stainless steel Treated borated Loss of material boundary water (int) Filter housing Pressure Stainless steel Air-indoor None boundary (ext) Filter housing Pressure Stainless steel Treated borated Loss of material boundary water (int) Flow element Pressure Stainless steel Air-indoor None boundary (ext) Flow element Pressure Stainless steel Treated borated Loss of material boundary water (int) Gear box Pressure Carbon steel Air-indoor Loss of material housing boundary (ext) Gear box Pressure Carbon steel Air-indoor Loss of material housing boundary (ext) Gear box Pressure Carbon steel Lube oil (int) Loss .of material housing boundary Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated borated Cracking (channel head) boundary water> 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Oil Analysis None lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-127 3.3.1-97 A, 302 Vll.J.AP-123 3.3.1-120 c Vll.E1.AP-119 3.3.1-8 A Vll.E1.AP-118 3.3.1-20 A, 301 Page 3.3-79 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Stainless steel Treated borated Cracking -fatigue (channel head) boundary water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated Loss of material (channel head) boundary water > 140°F (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) letdown boundary (ext) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) letdown boundary (ext) Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) letdown boundary (int) Heat exchanger Pressure Stainless steel Air-indoor None (shell) boundary (ext) regenerative Heat exchanger Pressure Stainless steel Treated borated Cracking (shell) boundary water> 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated Cracking -fatigue (shell) boundary water> 140°F regenerative (int) 3.0 Aging Management Review Results Aging Management Programs TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Water Chemistry Control -Closed Treated Water Systems None lnservice Inspection Water Chemistry Control -Closed Treated Water Systems TLAA-metal fatigue Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-189 3.3.1-46 A Vll.J.AP-123 3.3.1-120 c Vll.E1.AP-119 3.3.1-8 A Vll.E1.AP-118 3.3.1-20 A, 301 Vll.E1 .A-100 3.3.1-2 A Page 3.3-80 Table 3.3.2-1: Chemical and Volume Control System ' Component* Intended Type Function Material Environment
Heat exchanger Pressure Stainless steel Treated borated (shell) boundary water > 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F * (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F .letdown (ext) Heat exchanger Pressure Stainless steel Treated water (tube sheet) boundary (int) letdown Heat exchanger *Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F regenerative ' (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative* (int) . 3.0 Aging Management Review Results Aging Effect Aging 'Requiring Management Management Programs Loss of material Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Chemistry Control -Primary and Secondc;iry Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Cracking Water Chemistry Gontrol -Primary and SecondatY Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .A-88 3.3.1-29 A Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-69 3.3.1-3 E Vll.C2.A-52 3.3.1-49 c Vll.E1 .AP-118 3.3.1-20 A, 301 Vll.E1 .AP-118 3.3.1-20 A, 301 Page 3.3-81 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Environment Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative (int) Heat exchanger Heat transfer Stainless steel. Treated borated (tubes) water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated (tubes) boundary water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated (tubes) boundary water> 140°F (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) letdowri (ext) Heat exchanger Pressure Stainless steel Treated borated (tubes) letdown boundary vyater > 140°F. (int) Heat exchanger Pressure Stainless steel Treated water (tubes) letdown boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1so1* Item Item Notes Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-101 3.3.1-17 A, 301 Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.C2.AP-188 3.3.1-50 c Vll.E1.A-69 3.3.1-3 E Vll.C2.A-52 3.3.1-49 c Page 3.3-82 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Heat exchanger Heat transfer Stainless steel (tubes) regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Orifice Pressure Stainless steel boundary Flow control Orifice Pressure Stainless steel boundary Flow control Piping Pressure Stainless steel boundary Piping Pressure Stainless steel boundary 3.0 Aging Management Review Results ( I \.,_ Environment Treated borated water> 140°F (ext) Treated borated water> 140°F (ext) Treated borated water > 140°F (ext) Treated borated water> 140°F (ext) Treated borated water> 140°F (int) Air-indoor (ext) Treated borated water (int) Air-indoor (ext) Gas (int) Aging Effect Aging Requiring Management Management Programs Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-101 3.3.1-17 A, 301 Vll.E1.AP-118 3.3.1-20 A, 301 Vll.E1.A-100 3.3.1-2 A Vll.E1 .A-88' 3.3.1-29 . A Vll.E1.AP-118 3.3.1-20 A, 301 Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Page 3.3-83 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Lube oil (int) Loss of material boundary Piping Pressure Stainless steel Treated borated Loss of material boundary water (int) Piping Pressure Stainless steel Treated borated Cracking boundary water> 140°F (int) Piping Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Piping Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Piping Pressure Stainless steel Treated water Loss of material boundary (int) Pump casing Pressure CASS Air-indoor None boundary (ext) Pump casing Pressure CASS Treated borated Loss of material boundary water (int) Pump casing Pressure Stainless steel Air-indoor None boundary (ext) 3.0 Aging Management Review Results Aging Management Programs Oil Analysis Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-138 3.3.1-100 A, 302 Vll.E1 .A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1 .AP-82 3.3.1-28 A Vll.E1 .A-103 3.3.1-124 A, 301 Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 VI I. C2 .A-52 3.3.1-49 c Vll.J.AP-18 3.3.1-120 A Vll.E1 .A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Page 3.3-84 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Environment Pump casing Pressure Stainless steel Treated borated boundary water (int) Pump casing Pressure Stainless steel Treated borated boundary water (int) Strainer Filtration Stainless steel Treated borated water (ext) Strainer housing Pressure Stainless steel Air-indoor boundary (ext) Strainer housing Pressure Stainless steel Treated borated boundary water (int) Tank Pressure Stainless steel Air-indoor boundary (ext) Tank Pressure Stainless steel Treated borated boundary water (int) Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated borated boundary water (int) Thermowell Pressure Stainless steel Treated borated boundary water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-115 3.3.1-7 A Vll.E1.A-88 3.3.1-29 A Vll.E1.AP-79 3.3.1-125 A, 301 Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 ' 3.3.1-29 A Vll.J.AP-18 3.3.1-120 c Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.J.AP-18 3.3.1-120 A VI I .E 1.A-88 3.3.1-29 A Vll.E1.AP-79 3.3.1-125 A, 301 VII. E 1.AP-82 3.3.1-28 A Vll.E1.A-103 3.3.1-124 A, 301 Page 3.3-85 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Thermowell Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Treated borated Loss of material boundary water (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Gas (int) None boundary Valve body Pressure Stainless steel Treated borated Loss of material boundary -. water (int) 3.0 Aging Management Review Results Aging Management Programs TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Oil Analysis Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Oil Analysis None None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.J.AP-18 3.3.1-120 A Vll.E1.AP-138 3.3.1-100 A, 302 Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-127 3.3.1-97 A, 302 Vll.J.AP-18 . 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A. Vll.E1.AP-79 3.3.1-125 A, 301 Page 3.3-86 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material* Environment Management Valve body Pressure Stainless steel Treated borated Cracking boundary water> 140°F (int) Valve body Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Valve body Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-82 3.3.1-28 A Vll.E1.A-103 3.3.1-124 A, 301 Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.C2.A-52 3.3.1-49 c Page 3.3-87 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Blower housing Pressure Carbon steel boundary Blower housing Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Flow element Pressure Stainless steel boundary 3.0 Aging Management Review Results Table 3.3.2-2 Chilled Water System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Environment Management Programs Air-indoor Loss of material External Surfaces (ext) Monitoring Gas (int) None None Air-Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Condensation Loss of material Bolting Integrity (ext) Condensation Loss of preload Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Condensation Loss of material Bolting Integrity (ext) Con9ensation Loss of preload Bolting Integrity (ext) Condensation Loss of material External Surfaces (ext) Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.D.AP-121 3.3.1-12 D ----H Vll.l.AP-124 3.3.1-15 B Vll.D.AP-121 3.3.1-12 D ----H ----G Page 3.3-88 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Flow element Pressure Stainless steel Treated water boundary (int) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) Heat exchanger Pressure Carbon steel Treated water (channel head) boundary (int) ' Heat exchanger Pressure Stainless steel Air-indoor (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water (channel head) poundary (int) Heat exchanger Pressure Carbon steel Air-indoor (shell) boundary (ext) Heat exchanger Pressure Carbon steeL Gas (int) (shell) boundary Heat exchanger Pressure Stainless steel Air-indoor (shell) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (int) .; (shell) boundary Heat exchanger Pressure Carbon steel Gas (int) (tube sheet) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Closed
Treated Water Systems Los.s of material External Surfaces
Monitoring Loss of material Water Chemistry Control -Closed ... Treated Water Systems None None Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring None None None None Loss of material Oil Analysis None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information '* NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 3.3.1-78 A . . ' Vll.C2.AP-189 3.3.1-46 A Vll.J.AP-1.23 3.3.1-*120 c Vll.C2.A-52 3.3.1-49 c Vll.l.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 c Vll.J.AP-123 3.3.1-120 c Vll.C2.AP-138 3.3.1-100 C,302 Vll.J.AP-6 3.3.1-121 c Page 3.3-89 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Carbon steel Treated water Loss of material (tube sheet) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (int) Loss of material (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water Loss of material (tube sheet) boundary (ext) Heat exchanger Pressure Copper alloy Gas (ext) None (tubes) boundary Heat exchanger Heat transfer Copper alloy Treated water Reduction of heat (tubes) (int) transfer Heat exchanger Pressure Copper alloy Treated water Loss of material (tubes) boundary (int) Heat exchanger Heat transfer Stainless steel Lube oil (ext) Reduction of heat (tubes) transfer Heat exchanger Pressure Stainless steel Lube oil (ext) Loss of material (tubes) boundary 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Oil Analysis Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Oil Analysis Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-189 3.3.1-46 A Vll.C2.AP-138 3.3.1-100 C,302 Vll.C2.A-52 3.3.1-49 c Vll.J.AP-9 3.3.1-114 c Vll.C2.AP-205 3.3.1-50 A Vll.C2.AP-199 3.3.1-46 c V.01.EP-79 3.2.1-51 C, 302 Vll.C2.AP-138 3.3.1-100 C,302 Page 3.3-90 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Heat exchanger Pressure steel Treated water (tubes) boundary (int) Insulated piping Pressure Carbon steel Condensation components boundary (ext) Insulated piping Pressure Copper .alloy' Condensation components boundary (ext) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Gas (int) boundary Flow control Piping Pressure Carbon steel Air-indoor boundary . (ext) Piping Pressure Carbon steel Condensation boundary (ext) Piping Pressure Carbon steel Treated water boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of he"'t transfer Los.s of material Loss of material Loss of material None None Loss of material Loss of material Loss of material Aging Management .*Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item .Item Notes Water Chemistry . Vll.C2.AP-188 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems External Surfaces Vll.C2.A-405 3.3.1-132 A Monitoring External Surfaces Vll.C2.A-405 3.3.1-132 A Monitoring None Vll.J.AP-123 3.3.1-120 A None
Vll.J.AP-22 '3.3.1-120 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-81 .3.3.1-78 A Mon'itoring Water Chemistry Vll.C2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems Page 3.3-91 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Piping Pressure Copper alloy Air-indoor boundary (ext) Piping Pressure Copper alloy Condensation boundary (ext) Piping Pressure Copper alloy
Gas (int) boundary Piping Pressure Copper alloy Treated water boundary (int) Pump casing Pressure Carbon steel Air-indoor boundary (ext) Pump casing Pressure Carbon steel Gas (int) boundary Pump casing Pressure Carbon steel Lube oil (int) boundary Pump casing Pressure Stainless steel Condensation boundary Pump casing Pressure Stainless steel Treated water boundary (int) Sight glass Pressure Copper alloy > Condensation boundary 15% Zn or> 8% (ext) Al 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material External Surfaces Monitoring None None Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring None None Loss of material Oil Analysis Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-144 3.3.1-114 A Vll.F1 .AP-109 3.3.1-79 c Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-199 3.3.1-46 A Vll.1.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.G2.AP-127 3.3.1-97 A, 302 ----G Vll.C2.A-52 3.3.1-49 A Vll.F1.AP-109 3.3.1-79 c Page 3.3-92 Table 3.3.2-2: Chilled Water System Compom;mt Intended Type Function Material Environment Sight glass Pressure Copper alloy > Condensation boundary 15% Zn or> 8% (ext) Al Sight glass Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Sight glass Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Sight glass Pressure Glass Condensation boundary (ext) Sight glass Pressure Glass Treated water boundary (int) Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Condensation boundary (ext) Tank Pressure Carbon steel Gas (int) boundary Tank Pressure Carbon steel with Treated water boundary internal coating (int) Tank Pressure Carbon steel with Treated water boundary internal coating (int) Thermowell Pressure Stainless steel Condensation boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material None None Loss of material Loss of material None Loss of coating integrity Loss of material Loss of material Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Selective Leaching ----H Selective Leaching Vll.C2.AP-43 3.3.1-72 A Water Chemistry Vll.C2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-97 3.3.1-117 A None Vll.J.AP-166 3.3.1-117 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.1.A-77 3.3.1-78 A Monitoring None Vll.J.AP-6 3.3.1-121 c Coating Integrity Vll.C2.A-416 3.3.1-138 B, 307 Coating Integrity Vll.C2.A-414 3.3.1-139 B, 307 External Surfaces ----G Monitoring Page 3.3-93 Table 3.3.2-2: Chilled Water System Aging Effect *Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel _ Treated water Loss of material boundary (int) Tubing_ Pressure Copper. alloy Air-indoor None boundary (ext) Tubing Pressure Copper alloy Condensation Loss of material boundary (ext) Tubing Pressure Copper alloy Gas (int) -None boundary Tubing Pressure Copper alloy Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Co.ndensation Loss of material boundary (ext) Tubing Pressure Stainless steel Gas:(int) *
None bouridary Tubing Pressure Stainless steel Lube oil (int) Loss *of material boundary 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems None External Surfaces Monitoring None _Oil Analysis Water Chemistry Control -Closed Treated Water Systems* None External Surfaces Monitoring None Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.J.AP-144 A Vll.F1.AP-109 3.3.1-79 c Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-133 3.3.1-99 A, 302 Vll.C2.AP-199 3.3.1-46 A V!l.J.AP-123 3.3.1-120 A ----G Vll.J.AP-22 3.3.1.-120 A Vll.C2.AP-138 3.3.1-100 A, 302 Page 3.3-94 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel
Treated water Loss of material boundary (int) Valve body Pressure Carbon.steel. Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Condensation Loss of material boundary (ext) Valve body Pressure Carbon steel Gas (int) None boundary Valve body Pressure Carbon steel Lube oil (int) ' Loss of material boundary Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Copper alloy > Air-indoor None boundary 15% Zn or> 8% (ext) Al Valve body Pressure . Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (ext) Al Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (ext) Al 3.0 Aging Management Review Results ( '* Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Exterr:ial Surfaces Monitoring External Surfaces Monitoring None Oil Analysis Water Chemistry Control -Closed Treated Water Systems None External Surfaces Monitoring . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information '* *NUREG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 . 3.3.1-78 A Vll.l.A-81 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.C2.AP-127 3.3.1-97 A, 302 Vll.C2.AP-202 3.3.1-45 A . Vll.J.AP-144 3.3.1-114 A Vll.F1.AP-109 3.3.1-79 c Selective Leaching ----H Page 3.3-95 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Copper alloy > Gas (int) None boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Lube oil (int)
Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Treated water Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Treated water Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Condensation Loss of material boundary (ext) Valve body Pressure Stainless steel Gas (int) None boundary Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs None Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-133 3.3.1-99 A, 302 Selective Leaching Vll.C2.AP-43 3.3.1-72 A Water Chemistry Vll.C2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-123 3.3.1-120 A External Surfaces ----G Monitoring None Vll.J.AP-22 3.3.1-120 A Water Chemistry Vll.C2.A-52 3.3.1-49 A Control -Closed Treated Water Systems Page 3.3-96 Table 3.3.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling and Auxiliary Component Cooling Water System Summary of Aging Management Evaluation Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Blower housing* Pressure . Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Mo11itoring . Blower housing . Carbon steel Air -outdoor Loss of material External S-urfaces ----G, 305 boundary (int) Monitoring Bolting Pressure Carbon.steel Air -indoor . Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel
Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity 3.3.1-12 B boundary (ext)* Bolting Pressure steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP7263 3.3.1-15 B boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity Vll:l.A-04 3.3.1-10 B boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 .B . boundary steel (ext) Bolting Pressure High strength Air-* indoor . Loss of preload Bolting Integrity VILl.AP.:124 3.3.1-15 B boundary steel (ext) .. Bolting Pressure High strength Air -outdoor Cracking Bolting ,Integrity Vll.l.A-04 3.3.1-10 B boundary steel (ext) Bolting Pressure High strength Air -outdoor Loss ofmaterial Bolting 'Integrity Vll.1.AP-126 3.3.1-12 B boundary steel (ext) 3.0 Aging Management Review Results Page Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Bolting Pressure High strength Air -outdoor Loss of preload Bolting Integrity boundary steel (ext) Coil Pressure Copper alloy Lube oil (int) Loss of material Oil Analysis boundary Coil Pressure Copper alloy Raw water (ext) Loss of material Service Water boundary Integrity Expansion joint Pressure Stainless steel Air-indoor None None boundary (ext) Expansion joint Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Fan housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Fan housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (int) Monitoring Flow element Pressure Stainless steel Air-indoor None None boundary (ext) Flow element Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (channel head) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (channel head) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.AP-263 3.3.1-15 B Vll.C1.AP-133 3.3.1-99 C,302 Vll.C1.AP-179 3.3.1-38 A Vll.J.AP-123 3.3.1-120 A Vll.C2.A-52 3.3.1-49 A Vll.l.A-78 3.3.1-78 A ----G, 305 Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.l.A-77 3.3.1-78 A Vll.C2.AP-189 3.3.1-46 A Page 3.3-98 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Heat exchanger Pressure Stainless steel Air-indoor None None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (channel head) boundary (int) Control -Closed Treated Water Systems Heat exchanger Heat transfer Aluminum Condensation . Cracking External Surfaces (fins) (ext) Monitoring Heat exchanger Heat transfer Aluminum Condensation Loss of material External Surfaces (fins) (ext) Monitoring Heat exchanger Heat transfer Aluminum Condensation Reduction of heat Periodic (fins) (ext) transfer Surveillance and Preventive Maintenance Heat exchanger Pressure Carbon steel Air-indoor Loss of material. External Surfaces (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel . Raw water (int) Loss of material Service Water (shell) boundary Integrity Heat exchanger Pressure Stainless steel Air-indoor None None (shell) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (shell) boundary (int) Control -Closed Treated Water Systems Heat exchanger Pressure Carbon steel Raw water (int) Loss of material Service Water (tube sheet) boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-123 3.3.1-120 c Vll.C2.A-52 3.3.1-49 c ----G ----G ----G Vll.l.A-77 3.3.1-78 A Vll.C1.AP-183 3.3.1-38 A Vll.J.AP-123 3.3.1-120 c Vll.C2.A-52 3.3. 1-49 c Vll.C1 .AP-183 3.3. 1-38 A Page 3.3-99 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (tube sheet) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (tube sheet) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (tube sheet) boundary (int) Control -Closed Treated Water Systems Heat exchanger Heat transfer Carbon steel Condensation Reduction of heat Periodic (tubes) (ext) transfer Surveillance and Preventive Maintenance Heat exchanger Pressure Carbon steel Condensation Loss of material External Surfaces (tubes) boundary (ext) Monitoring Heat exchanger Heat transfer Carbon steel Treated water Reduction of heat Water Chemistry (tubes) (int) transfer Control -Closed Treated Water Systems Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (tubes) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-189 3.3.1-46 A Vll.C2.A-52 3.3.1-49 c Vll.C2.A-52 3.3.1-49 c ----G Vll.l.A-81 3.3.1-78 A Vll.F1 .AP-204 3.3.1-50 c Vll.C2.AP-189 3.3.1-46 A Page 3.3-100 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect
Aging Component Intended Requiring Management Type Function
Material Environment Management Programs Heat exchanger Pressure Copper alloy Condensation Loss of material External Surfaces (tubes) boundary (ext) Mo_nitoring Heat exchanger Pressure Copper.alloy Treated water Loss of material Water Chemistry (tubes) boundary (int) Control -Closed Treated Water .. Systems Heat exchanger Heat transfer Stainless steel Raw water (ext) Reduction of heat Service Water (tubes) transfer Integrity Heat exchanger Pressure Stainless steel Raw water (ext) Loss of material
Service Water (tubes) boundary Integrity Heat exchanger Pressure Stainless steel Treated water Loss' of material Water Chemistry (tubes) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Heat transfer Stainless steel. Treated water Reduction of heat Water Chemistry (tubes) (int) transfer Control -Closed Treated Water . Systems Heat exchanger . Pressure Stainless steel Treated water Loss of material Water Chemistry (tubes). boundary (int) Control -Closed ; Treated Water Systems Insulated piping Pressure Carbon steel Air -outdoor Loss of material* External Surfaces components boundary (ext) Monitoring Insulated piping. Pressure Carbon steel Condensation Loss of material External Surfaces components boundary .. (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.F1.AP-109 3.3.1-79 c Vll.C2.AP-199 3.3.1-46 c Vll.C1.AP-187 3.3.1-42 A Vll.C1.A-54 3.3.1-40 c Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-188 3.3.1-50 A 3.3.1-49 c VILC1 .A-405 3.3.1-132 A Vll.C1 .A-405 3.3.1-132 A Page 3.3-101 Waterford Steam Electric Station, Unit 3 License Renewal Technical Information Table 3.3.2-3: Component Cooling and Auxiliary Compo,nent CooHng Water System
Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Nozzle Pressure Stainless steel . Air -outdoor Cracking External Surfaces Vll.C1 .AP-209 3.3.1-4 A boundary (ext) Monitoring Nozzle Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vll.C1 .AP-221 3.3.1-6 A bOundary (ext) Monitoring Nozzle Pressure . Stainless steel Raw water (int) Loss of material *
Service Water VILC1.A-54 3.3.1-40 A bounda.ry Integrity Orifice Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary *(ext) Orifice Pressure Stainless steel Raw water (int) Loss of material Service Water Vll.C1.A-54 3.3.1-40 A boundary Integrity Flow control Orifice Pressure Stainless stee! *Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Flow control Treated Water Systems Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary * (ext) Monitoring Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A *boundary (ext) Monitoring Piping Pressure Carbon steel Raw water.(int) Loss of Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Piping Pressure Carbon steel Soil (ext) Loss of material Buried and VILC1.AP-198 3.3.1-106 A boundary Underground* Piping and Tanks . Inspection 3.0 Aging Management Review Results Page 3.3-102 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Piping Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel with Raw water (int) Loss of coating Coating Integrity boundary internal coating integrity Piping Pressure Carbon steel with Raw water (int) Loss of material Coating Integrity boundary internal coating Piping Pressure Concrete Raw water (int) Change in material One-Time boundary properties Inspection Piping Pressure Concrete Raw water (int) Cracking One-Time boundary Inspection Piping Pressure Concrete Raw water (int) Loss of material One-Time boundary Inspection Piping Pressure Concrete Soil (ext) Cracking Buried and boundary Underground Piping and Tanks Inspection Piping Pressure Concrete Soil (ext) Loss of material Buried and boundary Underground Piping and Tanks Inspection Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-202 3.3.1-45 A Vll.C1 .A-416 3.3.1-138 B Vll.C1 .A-414 3.3.1-139 B Vll.C1 .AP-250 3.3.1-30 E 3.3.1-32 Vll.C1 .AP-155 Vll.C1 .AP-248 3.3.1-31 E 3.3.1-32 Vll.C1.AP-155 Vll.C1 .AP-249 3.3.1-33 E Vll.C1.AP-178 3.3.1-105 A Vll.C1.AP-178 3.3.1-105 A Vll.l.A-77 3.3.1-78 A Page 3.3-103 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Pump casing Pressure Carbon steel Air -indoor (int) Loss of material Periodic boundary Surveillance and Preventive Maintenance Pump casing Pressure Stainless steel Air-indoor None None boundary (ext) Pump casing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None boundary (ext) Sight glass Pressure Glass Treated water None None boundary (int) Strainer housing Pressure Stainless steel Air-indoor None None boundary (ext) Strainer housing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.E-29 3.2.1-44 E Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 3.3.1-78 A Vll.C2.AP-202 3.3.1-45 A Vll.J.AP-14 3.3.1-117 A Vll.J.AP-166 3.3.1-117 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Page 3.3-104 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Tank Pressure Carbon steel with Treated water Loss of coating Coating Integrity boundary internal coating (int) integrity Tank Pressure Carbon steel with Treated water Loss of material Coating Integrity boundary internal coating (int) Thermowell Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Thermowell Pressure Carbon steel Raw water (int) Loss of material Service Water boundary Integrity Thermowell Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Thermowell Pressure Stainless steel Air-indoor None None boundary (ext) Thermowell Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Thermowell Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Tubing Pressure Stainless steel Air-indoor None None boundary (ext) Tubing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.C2.A-414 3.3.1-138 B,307 Vll.C2.A-414 3.3.1-139 B,307 Vll.l.A-77 3.3.1-78 A Vll.C1.AP-194 3.3.1-37 A Vll.C2.AP-202 3.3.1-45 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.C2.A-52 3.3.1-49 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Page 3.3-105 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NUREG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure, Carbon steel Air'-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Raw water (int) Loss of material Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Valve body Pressure Carbon steel Raw water (int) Loss of material -Flow-Accelerated Vll.C1 .A-409 3.3.1-126 A boundary erosion Corrosion Valve body Pressure Carbon steel Treated water
Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Gray cast iron Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring 0 Valve body Pressure Gray cast iron Raw water (int) Loss of material Selective Leaching Vll.C1.A-51 3.3.1-72 A boundary Valve body Pressure G.ray cast iron. Raw water (int) Loss of material Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary * (ext) Valve body Pressure Stainless steel Raw water (int) Loss of material Service Water Vll.C1.A-54 3.3.1-40 A boundary Integrity 3.0 Aging Management Review Results Page 3.3-106 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging* Component Intended Requiring Management Type Function Material Environment Management Programs Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results *
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Page 3.3-107
Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Accumulator Pressure Carbon steel boundary Accumulator Pressure Carbon steel boundary Accumulator Pressure Carbon steel boundary* Accumulator Pressure Stainless steel boundary Accumulator Pressure Stainless steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure
Carbon steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure* Plastic boundary 3.0 Aging Management Review Results Table 3.3.2-4 Compressed Air System Summary of Aging Management Evaluation Aging Effect Aging ' Requiring Management Environment MC1nagement Programs Air-indoor Loss of material External Surfaces (ext) Monitoring Air -outdoor Loss of material External Surfaces (ext) Monitoring Condensation Loss of material Compressed Air (int) Monitoring Air-indoor None None (ext) Condensation Loss of material Compressed Air (int) Monitoring Air-indoor Loss of material Bolting Integrity (ext) Air -indoor* Loss of preload Bolting Integrity (ext) Air -outdoor loss of material External Surfaces (ext) Monitoring Condensation Loss of material Compressed Air (int) Monitoring Air-indoor None None (ext) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A ----F Page 3.3-108 Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Environment Filter housing Pressure Plastic Condensation boundary (int) Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Condensation boundary (int) Flex hose Pressure Elastomer Air-indoor boundary (ext) Flex hose Pressure Elastomer Condensation boundary (int) Flex hose Pressure Stainless steel Air-indoor boundary (ext) Flex hose Pressure Stainless steel Condensation boundary (int) Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Condensation boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Air -outdoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None None None Loss of material Compressed Air Monitoring Loss of material -External Surfaces wear Monitoring None None None None Loss of material Compressed Air Monitoring Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Cracking External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----F Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.F1 .AP-113 3.3.1-82 c ----G Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A Page 3.3-109 Table 3.3.2-4: Compressed Air System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure* Stainless steel Air -outdoor Loss of material .. boundary (ext) Piping Pressure Stainless steel Condensation
Loss of material boundary (int) Regulator body Pressure Aluminum Air-indoor None boundary (ext) Regulator body Pressure Aluminum Condensation Loss of material boundary (int) Regulator body Pressure Copper alloy
Air -indoor None boundary (ext) .Regulator body Pressure Copper alloy Condensation Loss of material bdundar-Y (int) Regulator body Pressure Plastic Air-indoor None boundary (ext) Regulator body Pressure Plastic Condensation None ' boundary (int) Tubing Pressure Copper alloy Air-indoor None boundary (ext) Tubing* Pressure Copper alloy Condensation Loss of material boundary {int) Tubing Pressure Stainles.s steel Air=-indoor None bounda_ry (ext) Tubing Pressure Stainless steel
Air -outdoor Cracking boundary (ext) 3.0 Aging Management Review Results Aging Management Programs. External Surfaces Monitoring Compressed Air Monitoring None Compressed Air Monitoring None Compressed Air Monitoring None None None Compressed Air fl.llonitoring. *None External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-221 3.3.1-6 A Vll.D.AP-81 3.3.1-56 0 A VILJ.AP-135 3.3.1.-113 A Vll.F2.AP-142 3.3.1-92 E ' Vll.J.AP-144 3.3.1-114 A
Vll.D.AP-240 3.3.1-54 A ----F ----F Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A .. *P.age 3.3-110 Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Environment Tubing Pressure Stainless steel Air -outdoor boundary (ext) Tubing Pressure Stainless steel Condensation boundary (int) Valve body Pressure Aluminum Air-indoor boundary (ext) Valve body Pressure Aluminum Condensation boundary (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Condensation boundary (int) Valve body Pressure Copper alloy Air-indoor boundary (ext) Valve body Pressure Copper alloy Condensation boundary (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) Valve body Pressure Stainless steel Air -outdoor boundary (ext) Valve body Pressure Stainless steel Air -outdoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Loss of material Compressed Air Monitoring Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Loss of material Compressed Air Monitoring None None Cracking External Surfaces Monitoring Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-221 3.3.1-6 A Vll.D.AP-81 3.3.1-56 A Vll.J.AP-135 3.3.1-113 A Vll.F2.AP-142 3.3.1-92 E Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A Vll.D.AP-221 3.3.1-6 A Page 3.3-111 Table 3.3.2-4: Compressed Air System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs Compressed Air Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-Table 1 1801 Item Item Notes Vll.D.AP-81 3.3.1-56 A Page 3.3-112 Table 3.3.2-5 . Containment Cooling HVAC System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-5: Containment Cooling 'HVAC System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor
Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.AP-41 3.3.1-80 A boundary (ext) Monitoring Cooler housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E bo_undary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of r:naterial External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E: boundary Monitoring Fan housing . Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-113 Table 3.3.2-5: Containment Cooling HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Flex connection Pressure Elastomer Air-indoor Change in material boundary (ext) properties Flex connection Pressure Elastomer Air-indoor Cracking boundary (ext) Flex connection Pressure Elastomer Air-indoor Loss of material -boundary (ext) wear Flex connection Pressure Elastomer Air -indoor (int) Change in material boundary properties Flex connection Pressure Elastomer Air -indoor (int) Cracking boundary Flex connection Pressure Elastomer Air -indoor (int) Loss of material -boundary wear Heat exchanger Heat transfer Copper alloy Condensation Loss of material (fins) (ext) Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (fins) (ext) transfer 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring *External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F3.AP-113 3.3.1-82 A Monitoring External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring Internal Surfaces in Vll.F3.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Page 3.3-114 Table 3.3.2-5: Containment Cooling HVAC System Component Intended Type Function Material Environment Heat exchanger Pressure Carbon steel Air-indoor (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) (housing) boundary Heat exchanger Heat transfer Copper alloy Condensation (tubes) (ext) Heat exchanger Pressure Copper alloy Condensation (tubes) boundary (ext) Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Reduction of heat transfer Loss of material. Reduction of heat transfer Loss of material None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.F3.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Water Chemistry Vll.F3.AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F3.AP-203 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-123 3.3.1-120 A Page 3.3-115 Table 3.3.2-5: Containment Cooling HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Waste water Loss of material boundary (int) Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary 3.0 Aging Management Review Results Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Internal Surfaces in Vll.ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Page 3.3-116 Table Control Room HVAC System Component Intended Type Function Material Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Stainless steel boundary Damper Pressure Carbon steel boundary Damper housing Pressure Carbon steel boundary Damper housing Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary 3.0 Aging Management Review Results ( Table 3.3.2-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Control Room HVAC System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NU REG-Table 1 Environment Management Programs. 1801 Item Item Notes Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B (ext) Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B (ext) Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B (ext) Air-indoor Loss of material External Surfaces Vll.F1.A-10 3.3.1-78 A (ext) Monitoring Air-indoor.(i.nt) Loss of material External Surfaces V.A.E-29 3.2.1-44 E Monitoring Air -outdoor Loss of material Internal Surfaces in Vlll.B1 .SP-59 3.4.1-36 c (int) Miscellaneous Piping and Ducting Components Air-indoor Loss of material External Surfaces Vll.F1.A-10 3.3.1-78 A (ext) Monitoring Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E Monitoring Air -outdoor Loss of material Internal Surfaces in Vlll.B1 .SP-59 3.4.1-36 c (int) Miscellaneous Piping and Ducting Components Page \ )

Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Ducting Pressure Elastomer Air-indoor Change in material boundary (ext) properties Ducting Pressure Elastomer Air-indoor Cracking boundary (ext) Ducting Pressure Elastomer Air -indoor (int) Loss of material -boundary wear Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary 3.0 Aging Management Review Results Aging Management Programs Periodic Surveillance and Preventive Maintenance Periodic Surveillance and Preventive Maintenance Periodic Surveillance and Preventive Maintenance External Surfaces Monitoring Periodic Surveillance and Preventive Maintenance External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.F1.AP-102 3.3.1-76 E Vll.F1.AP-102 3.3.1-76 E Vll.F1 .AP-103 3.3.1-96 E Vll.F1.A-10 3.3.1-78 A Vll.F1 .A-10 3.3.1-78 E V.A.E-29 3.2.1-44 E Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Page 3.3-118 Table 3.3.2-6: Control Room HVAC System Component Intended Type Function Material Environment Fan housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Carbon steel Air-indoor boundary (ext) Filter housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Air -indoor (int) boundary Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air -indoor (int) boundary 3.0 Aging Management Review Results ( \ Aging Effect Requiring Management Loss of material Loss of material Loss of material None None Change in material properties Cracking Loss of material -wear Loss of material -wear Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Periodic V.A.E-29 3.2.1-44 E Surveillance and Preventive Maintenance External Surfaces Vll.F1.A-10 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.F1.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F1.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F1.AP-113 3.3.1-82 A Monitoring Internal Surfaces in Vll.F1.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components Page 3.3-119 Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Heat transfer Copper alloy Condensation Loss of material (fins) (ext) ' Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (fins) (ext) transfer Heat exchanger Pressure Carbon steel Air-indoor Loss of material (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material (housing) boundary Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material (housing) boundary Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (tubes) (ext) transfer Heat exchanger Pressure Copper alloy Condensation Loss of material (tubes) boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information .Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Internal Surfaces in Vll.G.AP-143 3.3.1-89 C, 306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components External Surfaces Vll.F1.AP-41 3.3.1-80 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Page 3.3-120 Table 3.3.2-6: Control Room HVAC System Component Intended Type Function Material Environment Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Heater housing Pressure Carbon steel Air-indoor boundary (ext) Heater housing Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Waste water boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of heat transfer Loss of material Loss of material Loss of material Loss of material Loss of material None Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Water Chemistry Vll.F1 .AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F1 .AP-203 3.3.1-46 A Control -Closed Treated Water Systems External Surfaces Vll.F1.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F1.A-10 3.3.1-78 c Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-121 Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) Loss of material boundary Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Stainless steel Waste water Loss of material boundary (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.F1 .A-10 3.3.1-78 c Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-122 Table 3.3.2-7 Emergency Diesel Generator System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program* 1801 Item Item Notes Blower Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Blower Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components Blower Pressure Carbon steel Exhaust gas Loss of material Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A boundary (int) Miscellaneous Piping and Ducting Components Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.1.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Expansion joint Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results

Page 3.3-123 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Expansion joint Pressure Stainless steel Air -indoor (int) Cracking -fatigue boundary Expansion joint Pressure Stainless steel Exhaust gas Cracking boundary (int) Expansion joint Pressure Stainless steel gas Cracking -fatigue boundary (int) Expansion joint Pressure Stainless steel Exhaust gas Loss of material boundary (int) Expansion joint Pressure Stainless steel Lube oil (int) Loss of material boundary Expansion joint Pressure Stainless steel Treated water Loss of material boundary (int) Expansion joint Pressure Stainless steel Treated water Cracking boundary > 1.40°F (int) Expansion joint Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program TLAA-metal fatigue Periodic Surveillance and Preventive Maintenance TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----H Vll.H2.AP-128 3.3.1-83 E ----H Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Oil Analysis Vll.H2.AP-138 3.3.1-100 A, 302 Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Water Chemistry VI I. C2.AP-186 3.3.1-43 c Control -Closed Treated Water Systems Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Page 3.3-124 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environ.ment Management Filter housing Pressure Aluminum Air-indoor None boundary (ext) Filter housing Pressure Aluminum Condensation Loss of material boundary (int) Filter housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Filter housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Filter housing Pressure Carbon steel Fuel oil (int) Loss of material boundary Filter housing Pressure Carbon steel Lube oil (int) Loss of material boundary Flame arrestor Pressure Carbon steel . Air -outdoor
Loss of material
boundary (ext) Flame arrestor Pressure Carbon steel Air -outdoor Loss of material boundary (int) Flow element Pressure Stainless steel Air-indoor None boundary (ext) Flow element Pressure Stainless steel Fuel oil (int) Loss of material boundary Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) 3.0 Aging Management Review Results Aging Management *Program None Compressed Air Monitoring External Surfaces
Monitoring Waterford Steam Electric Station, *unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-135 3.3.1-113 A Vll.F2.AP-142 3.3.1-92 E Vll.l.A-77 3.3.1-78 A Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Diesel Fuel
Vll.H1.AP-105 3.3.1-70 A,303 Monitoring " Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring External Surfaces ----G, 305 Monitoring None Vll.J.AP-17 3.3.1-120 A Diesel Fuel Vll.H1 .AP-136 3.3.1-71 A, 303 Monitoring None Vll.J.AP-123 3.3.1-120 c Page 3.3-125 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Stainless steel Treated water Loss of material (channel head) boundary (int) Heat exchanger Heat transfer Aluminum Air-indoor Reduction of heat (fins) * (ext) transfer Heat exchanger Pressure Carbon steel Air-indoor Loss of material (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material. (housing) boundary Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) HeC!t exchanger Pressure Carbon steel with Fuel oil (int) Loss of coating (shell) boundary internal coating integrity Heat exchanger Pressure Carbon steel with Fuel oil (int) Loss of material (shell) ' boundary
internal coating Heat exchanger Pressure Carbon steel with Lube oil (int) Loss of coating (shell boundary internal coating integrity Heat exchanger Pressure Carbon steel with Lube oil (int) Loss of material (shell) boundary internal coating Heat exchanger Pressure Carbon steel with Treated water Loss of coating (shell) boundary internal coating (int) integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Internal Surfaces in ----G Miscellaneous Piping and Ducting Components External Surfaces Vll.H2.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.H2.AP-41 3.3.1-80 A Monitoring Coating Integrity Vll.H2.A-416 3.3.1-138 B Coating Integrity --G Coating Integrity Vll.H1 .A-416 3.3.1-138 B Coating Integrity Vll.H1 .A-414 3.3.1-139 B Coating Integrity Vll.H1 .A-416 3.3.1-138 B Page 3.3-126 Table 3.3.2-7: Diesel Generator System " Component Intended Type Function
Material Environment Heat exchanger Pressure Carbon steelwith Treated water (shell) boundary internal coating (int) Heat exchanger Pressure Stainless steel Fuel oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Lul;>e oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water *(tube sheet) boundary : (ext) Heat exchanger Pressure steel Treated water (tube sheet) boundary > 140°F (int) Heat exchanger . .Pressure Stainless steel Treated water (tube sheet) boundary > 140°F (int) ** Heat exchanger Heat transfer Copper alloy > Air""" indoor (tubes) 15% zinc-(ext) (inhibited) Heat exchanger Pressure Copper alloy > Air-indoor (tubes) boundary 15%iinc . (ext) (inhibited) 3.0 Aging. Management Review Results Aging Effect Requiring M;magement Loss qf material .Loss of material Loss of material Loss of material Cracking Loss of material Reduction of heat transfer .. None Aging Management Program Coating Integrity Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item* Notes Vll.H1 .A-414 3.3.1-139 B Vll.H2.AP-136 3.3.1-71 C,303 Vll.H2.AP-138 3.3.1-100 C,302 Vll.C2.A-52 3.3.1-49 c i Vll.E3.AP-192 3.3.1-44 c Vll.C2.A-52 3.3.1-49 c Internal Surfaces in --*--G Miscellaneous Piping al')d Ducting Components -None Vll.J.AP-144 3.3.1-114 A Page 3.3-127 r Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management < Heat exchanger Heat transfer Copper alloy > Treated water Reduction of heat (tubes) 15% zinc (int) transfer (inhibited) Heat exchanger Pressure Copper alloy > Treated water Loss of material (tubes) boundary 15% zinc : (int) (inhibited) Heat exchanger Heat transfer Stainless steel Fuel oil (ext) Reduction of heat (tubes) transfer Heat exchanger Pressure Stainless steel Fuel oil (ext) Loss of material (tubes) boundary Heat exchanger Pressure Stainless steel Fuel oil (ext)* Loss of material -(tubes) boundary wear Heat exchanger Heat transfer Stainless steel Lube oil (ext) Reduction of heat (tubes) . transfer Heat exchanger Pressure Stainless steel Lube oil (ext) Loss of material (tubes) boundary Heat exchanger Flressure Stainless steel Lube oil (ext) Loss of material -(tubes) boundary wear 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Diesel Fuel . Monitoring Diesel Fuel Monitoring Periodic Surveillance and Preventive Maintenance Oil Analysis Oil Analysis Periodic Surveillance and Preventive Maintenance Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-205 3.3.1-50 c Vll.E1 .AP-203 3.3.1-46 c ----G Vll.H2.AP-136 3.3.1-71 C,303 ----G V.D1.EP-79 3.2.1-51 C, 302 Vll.H2.AP-138 3.3.1-100 C, 302 --. --H Page 3.3-128 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Heat exchanger Heat transfer Stainless steel Treated water (tubes) (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (int) Heater housing Pressure Stainless steel Air-indoor boundary (ext) Heater housing Pressure Stainless steel Lube oil (int) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material -Periodic wear Surveillance and Preventive Maintenance Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Closed Treated Water Systems None None Loss of material Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c ----H Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c Vll.J.AP-123 3.3.1-120 c Vll.H2.AP-138 3.3.1-100 C, 302 Page 3.3-129 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Heater housing Pressure Stainless steel Treated water boundary > 140°F (int} Heater housing Pressure Stainless steel Treated water boundary > 140°F (int) Level indicator Pressure Copper alloy > Air-indoor boundary 15% Zn or> 8% (ext) Al Level indicator Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Level indicator Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Level indicator Pressure Glass Air-indoor boundary (ext) Level indicator Press lire Glass Treated water boundary (int) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control 3.0 Aging Management Review Results Aging Effect Requiring Management Cracking Loss of material None Loss of material Loss of material None None None Aging Management Program Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-186 3.3.1-43 c Vll.C2.A-52 3.3.1-49 c Vll.J.AP-144 3.3.1-114 A Selective Leaching Vll.H2.AP-43 3.3.1-72 A Water Chemistry VI I. H2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-166 3.3.1-117 A None Vll.J.AP-166 3.3.1-117 A None Vll.J.AP-17 3.3.1-120 A Page 3.3-130 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function
Material. Environment Management Orifice
Pressure Stainless steel Condensation Loss of material boundary (int) Flow control Piping Pressure Carbon steel
Air-indoor Loss of material . boundary (ext) Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary Piping Pressure Carbon steel Air -outdoor . Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure Carbon steel Condensation
Loss of material ,. boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue boundary (int) Piping Pressure Carbon steel Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (ext) Loss of material boundary 3.0 Aging Management Review Results ( \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Compressed Air . Vll.D.AP-81 3.3.1-56 c Monitoring External Surfaces VILl.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Piping and Ducting Components External.Surfaces 3.3.1-78 A Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous 'Piping and Ducting Components Compressed Air Vll.D.A-26 3.3.1-55 c Monitoring TLAA-metal ----H fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Page 3.3-131 \

Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Jlllanagement Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Piping Pressure Carbon steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Soil (ext) Loss of material .. boundary Piping Pressure Carbon steel Treated water . Loss of material boundary (int) Pump casing Pressure . Carbon steel Air-indoor Loss of material boundary (ext) Pump casing Pressure Carbon steel Fuel oil (int) Loss of material boundary Pump casing Pressure Carbon steel Lube qil (int) Loss of material boundary Pump casing Pressure Carbon steel Treated water Loss of material boundary (int) Silencer Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Aging Management Program Diesel Fuel Monitoring Oil Analysis Buried ;:ind Underground . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.H1.AP-105 3.3.1-70 A, 303 Vll.H2.AP-127 3.3.1-97 A, 302

Vll.H1.AP-198 3.3.1-106 A Piping and Tanks' *. Inspection Water Chemistry Vll.H2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303* Monitoring Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 Water Chemistry Vll,H2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-132 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Silencer Pressure Carbon steel Air -indoor (int) boundary Silencer Pressure Carbon steel boundary (int) Strainer Filtration Carbon steel Fuel oil (ext) Strainer Filtration Carbon steel Lube oil (ext) Strainer housing Pressure Carbon steel Air-indoor boundary (ext) Strainer housing Pressure Carbon steel Fuel oil (int) boundary Strainer housing Pressure Carbon steel Lube oil (int) boundary Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Concrete (ext) boundary Tank Pressure Carbon steel Condensation boundary (int) Tank Pressure Carbon steel with Fuel oil (int) boundary internal coating 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material None Loss of material Loss of coating integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Oil Analysis Vll.H2.AP-127 3.3.:1-97 A, 302 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring None ----G, 304 Compressed Air Vll.D.A-26 3.3.1-55 c Monitoring Coating Integrity Vll.H2.A-416 3.3.1-138 B Page 3.3-133 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Tank Pressure Carbon steel with Fuel oil (int) Loss of material boundary internal coating Tank Pressure Carbon steel with Treated water Loss of coating boundary internal coating (int) integrity Tank Pressure Carbon steel with Treated water Loss of material boundary internal coating (int) Thermowell Pressure Carbon steel Air-indoor Loss of material boundary (ext) Thermowell Pressure Carbon steel Lube oil (int) Loss of material boundary Thermowell Pressure Carbon steel Treated water Loss of material boundary (int) Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Air-indoor None boundary (ext) Tubing Pressure Copper alloy Air -indoor (int) None boundary Tubing Pressure Copper alloy Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program Coating Integrity Coating Integrity Coating Integrity External Surfaces Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None Oil Analysis None None Compressed Air Monitoring Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----G Vll.H1 .A-416 3.3.1-138 B Vll.H1.A-414 *. 3.3.1-139 B Vll.l.A-77 3.3.1-78 A Vll.H2.AP-127 3.3.1-97 A,302 Vll.H2.AP-202 3.3.1-45 A Vll.J.AP-17 3.3.1-120 A Vll.H2.AP-138 3.3.1-100 A, 302 VI l.J .AP-144 3.3.1-114 A . Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 c Page 3.3-134 Table 3.3.2-7: E.mergency Diesel Generator System Aging Effect Component Intended Requiring. Type Function Material Environment Management Tubing Pressure Copper alloy Fuel*oil (int) . Loss of material boundary p Tubing Pressure Copper alloy Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Condensation Loss of material boundary (int) Tubing Pressure Stainless steel Fuel oil (int) Loss of material boundary Tubing Pressure Stainless steel Lube oil* (int) Loss of material boundary lubing Pressure Stainless steel Treated water Loss of material boundary (int) '. Tubing Pressure
Stainless steel Treated water Cracking boundary > 140°F (int) 3.0 Aging Management Review Res,ults Aging 'Management Program Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None None Compressed Air Monitoring D.iesel Fuel Monitoring Oil Analysis . Water Chemistry Control -Closed . Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information NU REG-Table 1 1801 Item Item Notes Vll.H1 3.3.1-69 A,.303 Vll.H2.AP-133 . 3.3.1-99 A, 302 Vll.H2.AP-199. 3.3.1-46 A VILJ.AP-17 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A . Vll.D.AP-81 3.3.1-56 c VILH1.AP-136 3.3.1-71 A, 303 Vll.H2.AP-138 3.3.1-100 A, 302 Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-186 3.3.1-43 c Page 3.3-135

) Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring . Type Function Material Environment Management Tubing Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -indoor (irit) Loss of material boundary Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (eXt) Valve body Pressure Carbon steel Condensation Loss of material boundary* (int) Valve body Pressure Carbon steel Fuel oil (int) Loss of material boundary Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Copper alloy > Air-indoor None boundary 15% ?:nor> 8% (ext) Al Valve body Pressure Copper alloy > -indoor (int) None boundary 15% Zn or> 8% Al 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Closed Treated Water Systems External Surfaces Mol')itoring External Surfaces Monitoring External Surfaces Monitoring Compressed Air Monitoring Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 c Vll.l.A-77 3.3.1-78 A V.A.E-29 3.2.1-44 E Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 c Vll.H1.AP-105 3.3.1-70 A, 303 Vll.H2.AP-127 3.3.1-97 A, 302 Vll.H2.AP-202 3.3.1-45 A Vll.J.AP-144 3.3.1-114 A Vll.J.AP-144 3.3.1-114 A Page 3.3-136 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Fuel oil (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Condensation Loss of material boundary (int) Valve body Pressure Stainless steel Fuel oil (int) Loss of material boundary Valve body Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Treated water Loss of material boundary (int) Valve body Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program Compressed Air Monitoring Diesel Fuel Monitoring None Compressed Air Monitoring Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-240 3.3.1-54 c Vll.H1 .AP-132 3.3.1-69 A, 303 Vll.J.AP-17 3.3.1-120 A Vll.D.AP-81 3.3.1-56 c Vll.H1 .AP-136 3.3.1-71 A, 303 Vll.H2.AP-138 3.3.1-100 A, 302 Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-186 3.3.1-43 c Vll.C2.A-52 3.3.1-49 c Page 3.3-137 Table 3.3.2-8 Fire Protection -Water System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-8: Fire Protection -Water System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary Bolting Pressure Carbon steel Air-indoor (ext) Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Soil (ext) Loss of material Buried and Vll.l.AP-241 3.3.1-109 A boundary Underground Piping and Tanks Inspection Bolting Pressure Carbon steel Soil (ext) Loss of preload Bolting Integrity Vll.l.AP-242 3.3.1-14 B boundary Expansion joint Pressure Carbon steel Air-indoor (ext) Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary Monitoring Expansion joint Pressure Carbon steel Exhaust gas Loss of material Internal Surfaces in Vll.H2.AP-104 3.3.1-88 c boundary (int) Miscellaneous Piping and Ducting Components Flame arrestor Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-138 3.3.2-8: Fire Protection -Watel'.' System I Component Intended* Type* Function Material* Environment Flame arrestor Pressure

Carbon steel Air --outdoor boundary (int) Flex hose Pressure Copper alloy > Air-indoor (ext) boundary 15% Zn or> 8% Al flex hose Pressure Copper alloy > Fuel oil (int) boundary 15% Zn or> 8% Al Heat exchanger Pressure. Carbon steel Air-indoor (ext) (housing) boundary Heat exchanger Pre.ssure Carbon steel Treated water (housing) boundary (int) .. Heat exchanger Heat transfer
Copper alloy
Raw water (irit) (tubes) .. Heat exchanger Pressure Copper alloy
Raw water (int) (tubes) boundary Heat exchanger Heat transfer Copper alloy neated water (tubes) (ext) 3.0 Aging Management Review Results .* Aging Effect Requiring Management Loss of material None Loss of material Loss of material Loss of material Reduction of heat transfer Loss of material Reduction ofheat transfer Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information .,, Aging Management NU REG-Table 1 'Program
1801 Item Item. Notes
Internal Surfaces in Vll.G.A-404 3.3.1-131 E Miscellaneous
Piping anti Due.ting Components None , Vll.J.AP-144 3.3.1-114 A Diesel Fuel Vll.G.AP-132 3.3.1-69 I A, 303 Monitoring External Surfaces Vll.G.AP-41 3.3.1-:80 A Monjtoring . Water Chemistry Vll.C2.AP-189 3.3.1-46 c Control -Closed Treated Water $ystems Internal Surfaces in Vll.C1.A-72 3.3.1-42 E 'Miscellaneous Piping and Ducting Components Fire Water System Vll.G.AP-197 3.3.1-64 D Water Chemistry 3.3.1-50 c Control -Closed Treated Water Systems Page 3.3-139 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Copper alloy Treated water Loss of material (tubes) boundary (ext) Hydrant Pressure Gray cast iron Air -outdoor Loss of material boundary (ext) Hydrant Pressure Gray cast iron Raw water (int) Loss of coating boundary with internal integrity coating Hydrant Pressure Gray cast iron Raw water (int) Loss of material boundary with internal coating Hydrant Pressure Gray cast iron Raw water (int) Loss of material boundary with internal coating Hydrant Pressure Gray cast iron Soil (ext) Loss of material boundary Hydrant Pressure Gray cast iron Soil (ext) Loss of material boundary Insulated piping Pressure Carbon steel Air -outdoor Loss of material components boundary (ext) Piping Pressure Carbon steel Air-indoor (ext) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Water Chemistry Vll.E1 .AP-203 3.3.1-46 c Control -Closed Treated Water Systems Fire Water System Vll.G.AP-149 3.3.1-63 B Coating Integrity Vll.G.A-416 3.3.1-138 B Coating Integrity Vll.G.A-414 3.3.1-139 B Coating Integrity Vll.G.A-415 3.3.1-140 B,308 Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Selective Leaching Vll.G.A-02 3.3.1-72 A External Surfaces
Vll.G.A-405 3.3.1-132 A Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-140 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure Carbon steel Condensation Loss of material boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue -boundary (int) Piping Pressure Carbon steel Exhaust gas Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Piping Pressure Carbon steel Raw water (int) Loss of material boundary Piping Pressure Carbon steel Raw water (int) Recurring internal boundary corrosion Piping Pressure Carbon steel Soil (ext) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vll.G.A-404 3.3.1-131 E Miscellaneous Piping and Ducting Components Fire Water System Vll.G.A-404 3.3.1-131 B TLAA-metal ----G fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 c Miscellaneous Piping and Ducting Components Diesel Fuel Vll.G.AP-234 3.3.1-68 A, 303 Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B Fire Water System Vll.G.A-400 3.3.1-127 E Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Page 3.3-141 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Waste water Loss of material boundary (int) Piping Pressure Gray cast iron Raw water (int) Loss of material boundary Piping Pressure Gray cast iron Raw water (int) Loss of material boundary Piping Pressure Gray cast iron Soil (ext) Loss of material boundary Piping Pressure Gray cast iron Soil (ext) Loss of material boundary Piping Pressure Plastic (PVC) Raw water (int) None boundary Piping Pressure Plastic (PVC) Soil (ext) None boundary Pump casing Pressure Carbon steel Air -indoor (ext) Loss of material boundary Pump casing Pressure Carbon steel Raw water (int) Loss of material boundary Silencer Pressure Carbon steel Air -outdoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components Fire Water System Vll.G.A-33 3.3.1-64 B Selective Leaching Vll.G.A-51 3.3.1-72 A Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Selective Leaching Vll.G.A-02 3.3.1-72 A None ----G None ----G External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Page 3.3-142 Table 3.3.2-8: Fire Protection -Water System Component Intended Type. Function Material Silencer Pressure Carbon steel boundary Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow contror Al Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al ' Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al Strainer Filtration Stainless steel Strainer Filtration Stainless steel Strainer housing Pressure Carbon steel boundary Strainer housing Pressure Carbon steel boundary 3.0 Aging Management Review Results Aging Effect Requiring Environment Management Exhaust gas . Loss of material (int) Air-indoor (ext) None Condensation Loss of material (int) Raw water (int) Loss of material Raw water (int) Loss of material Condensation Loss of material (ext) Raw water (ext) Loss of material Air-indoor (ext) Loss of material Raw water (int) Loss of material Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in 3.3.1-88 c Miscellaneous Piping and Ducting Components None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.A-403 3.3.1-130 8 Fire Water System Vll.G.A-403 3.3.1-130 8 Selective Leaching Vll.G.A-47 3.3.1-72 A Fire Water System Vll.G.A-412 3.3.1-136 D Fire Water System Vll.G.A-55 3.3.1-66 8 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-33 3.3.1-64 8 Page 3.3-143 Table 3.3.2*8: Fire Protection -Water System i Component Intended* Function Material Environment Strainer housing Pressure Copper alloy > Air-indoor (ext) boundary or> 8% .. Al Strainer housing Pressure Copper alloy > Raw water (int) boundary 15%Zn or> 8% Al Strainer housing Pressure Copper alloy > Raw water (int)
I boundary 15% Zn or> 8% Al Tank Pressure Carbon steel Air-indoor (ext) boundary Tank Pressure Carbon steel Air -outdoor boundary (ext) Tank Pressure Carbon steel Concrete (ext) boundary Tank Pressure Carbon steel Condensation boundary (int) Tank Pressure Carbon steel Fuel oil (int) boundary Tank . Pressure Carbon steel Raw water (int) boundary with*internal . . coating Tank Pressure Carbon steel Raw water (int) boundary with internal 3.0 Aging Management Review Results Aging Effect Requiring MaF!agement None Loss of material Loss of material Loss of material Loss of material Loss of material Loss o_f material Loss of material Loss of coating Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.AP-197 3.3.1-64 B .Selective Leaching. Vll.G.A-47 3.3.1-72 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-412 3.3.1-136 B Fire Water System Vll.G.A-402 3.3.1-129 E Fire Water System Vll.G.A-412 3.3.1-136 B Diesel Fuel Vll.H1.AP-105 3.3.1-70 C,303 Monitoring Fire Water System ----H Fire Water System Vll.G.A-412 3.3.1-136 B Page 3.3-144 Table 3.3.2-8: Fire Protection -Water System Component Intended Type Function Material Environment Tank Pressure Carbon steel Soil (ext) boundary Trap Pressure Gray cast iron Air-indoor (ext) boundary Trap Pressure Gray cast iron Condensation boundary (int) Tubing Pressure Copper alloy Air-indoor (ext) boundary Tubing Pressure Copper alloy Condensation boundary (int) Tubing Pressure Copper alloy Fuel oil (int) boundary Tubing Pressure Copper alloy Raw water (int) boundary Tubing Pressure Stainless steel Air -indoor (ext) boundary Tubing Pressure Stainless steel Raw water (int) boundary Valve body Pressure Carbon steel Air-indoor (ext) boundary Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Condensation boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material None Loss of material Loss of material Loss of material None Loss of material Loss of material Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Fire Water System Vll.G.A-402 3.3.1-129 E External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.A-404 3.3.1-131 B Diesel Fuel Vll.G.AP-132 3.3.1-69 A,303 Monitoring Fire Water System Vll.G.AP-197 3.3.1-64 B None Vll.J.AP-123 3.3.1-120 A Fire Water System Vll.G.A-55 3.3.1-66 B External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Page 3.3-145 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Carbon steel Fuel oil (int) Loss of material boundary Valve body Pressure Carbon steel Raw water (int) Loss of material boundary Valve body Pressure Carbon steel Soil (ext) Loss of material boundary Valve body Pressure Copper alloy > Air -indoor (ext) None boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Air -outdoor Loss of material boundary 15% Zn or> 8% (ext) Al Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Fuel oil (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Raw water (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Raw water (int) Loss of material boundary 15% Zn or> 8% Al 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Diesel Fuel Vll.G.AP-234 3.3.1-68 A, 303 Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection None Vll.J.AP-144 3.3.1-114 A External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Diesel Fuel Vll.G.AP-132 3.3.1-69 A, 303 Monitoring Fire Water System Vll.G.AP-197 3.3.1-64 B Selective Leaching Vll.G.A-47 3.3.1-72 A Page 3.3-146 Table 3.3.2-8: Fire Protection -Water System Component lntende.d Type Function Material Environment Valve body Pressure Gray cast iron Air-indoor (ext) boundary Valve body Pressure Gray cast iron Condensation boundary (int) Valve body Pressure Gray cast iron Raw water (int) boundary Valve body Pressure Gray cast iron Raw water (int) boundary Valve body Pressure Stainless steel Air-indoor (ext) boundary Valve body Pressure Stainless steel Condensation boundary (int) Valve body Pressure Stainless steel Raw water (int) boundary
Vortex breaker Flow control Carbon steel Raw water (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss qf material Loss of material Loss of material Loss of material None Loss of material Los!S of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Fire Water System Vll.G.A-33 3.3.1-64 B Selective Leaching Vll.G.A-51 3.3.1-72 A None Vll.J.AP-123 3.3.1-120 A Fire Water System Vll.G.A-404 3.3.1-131 B Fire Water System Vll.G.A-55 3.3.1-66 B Fire Water System Vll.G.A-412 3.3.1-136 D Page 3.3-147 Table 3.3.2-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire Protection RCP Oil Collection System Summary of Aging Management Evaluation Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Aging Component . Intended Requiring_ Management NU REG-Table 1 Type Function Material
Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material .Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Drip pan-Pressure Carbon steel Air-'-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Drip pan Pressure Carbon steel Lube oil (int) Loss of material Periodic Vll.G.AP-117 3.3.1-97 E boundary Surveillance and .. Preventive Maintenance *Drip pan Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A *boundary (ext) Drip pan Pressure Stainless steel Lube oil (int) Loss of material Periodic Vll.G.AP-138 3.3.1-100 E boundary . Surveillance and Preventive .. Maintenance Enclosure Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-148 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Enclosure Pressure Carbon steel Lube oil (int) Loss of material boundary Enclosure Pressure Stainless steel Air-indoor None boundary (ext) Enclosure Pressure Stainless steel Lube oil (int) Loss of material boundary Flame arrestor Pressure Carbon steel Air-indoor Loss of material boundary (ext) Flame arrestor Pressure Carbon steel Air -indoor (int) Loss of material boundary Flex hose Pressure Stainless steel indoor None boundary (ext) Flex hose Pressure Stainless steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program* 1801 Item Item Notes Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-149 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary -Piping Pressure Carbon steel oil (int) Loss of material boundary Piping Pressure Stainless steel Air-indoor None boundary (ext) Piping Pressure Stainless steel Lube oil (int) Loss of material boundary . Sight glass Pressure Carbon steel Air-indoor Loss of material boundary (ext) Sight glass Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Lube oil (int) None boundary Strainer Filtration Stainless steel Lube oil (ext) Loss of material 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-14 3.3;1-117 A None Vll.J.AP-15 3.3.1-117 A External Surfaces Vll.G.AP-138 3.3.1-100 E Monitoring Page 3.3-150 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Strainer Filtration Stainless steel Lube oil (int) Loss of material Tank Pressure Carbon steel Air-indoor Loss of material boundary (ext) Tank Pressure Carbon steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary 3.0 Aging Management Review Results Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes External Surfaces Vll.G.AP-138 3.3.1-100 E Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance Page 3.3-151

\ Table 3.3.2-1 O Fuel Pool Cooling and Purification System Summary of Aging Management Evaluation Table 3.3.2-10: Fuel Pool Cooling and Purification System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Heat exchanger Pressure Stainless steel Air-indoor None None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated borated Loss of material Water Chemistry (channel head) boundary water (int) Control -Primary and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material Boric Acid (shell) boundary (ext) Corrosion Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (shell) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.AP-125 3.3.1-12 B Vll.l.A-102 3.3.1-9 A Vll.l.AP-124 3.3.1-15 B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-123 3.3.1-120 c , Vll.A3.AP-79 3.3.1-125 C, 301 Vll.A3.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.A3.AP-189 3.3.1-46 A Page 3.3-152 Table 3.3.2-10: Fuel Pool Cooling and Purification System Component Intended Type . Function Material Environment . Heat exchanger Pressure Stainless steel Treated borated (tube sheet)* boundary water (ext) Heat exchanger. Pressure Stainless steel . Treated water (tube sheet) *boundary (int) Heat exchanger Heat transfer Stainless steel Treated borated (tubes) water (int) Heat exchanger Pressure

Stainless steel Treated borated (tubes) boundary water (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Neutron Neutron Bora I Treated borated Absorber absorption water (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Reduction of heat transfer Loss of material Reduction of heat transfer
Loss of material Change in material properties Aging Management Program Water Chemistry Control -Primary and Secondary Water Chemistry Control.-Closed Treated Water Systems Water. Chemistry Control -Primary and Secondary Water Chemistry Control -Primary Secondary Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Neutron-Absorbing Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.A3.AP-79 3.3.1-125 C, 301 Vll.C2.A-52 3.3.1-49 c Vll.A3.A-10.1 3.3.1-17 A, 301 Vll.A3.AP-79 3.3.1-125 C, 301 Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c Vll.A2.AP-235 3.3.1-102 A Material Monitoring Page 3.3-153 Table 3.3.2-10: Fuel Pool Cooling and Purification System I Component Intended Type Function Material Environment Neutron Neutron Bora I Treated borated Absorber absorption water (ext) Neutron Neutron Bora I Treated borated Absorber absorption water (ext) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Treated borated boundary water (ext) Piping Pressure Stainless steel Treated borated boundary water (int) Piping Pressure Stainless steel Waste water boundary (int) Pump casing Pressure Stainless steel Air-indoor boundary (ext) Pump casing Pressure Stainless steel Treated borated boundary water (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Reduction in neutron absorption capacity None Loss of material Loss of material Loss of material None Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Neutron-Absorbing Vll.A2.AP-235 3.3.1-102 A Material Monitoring Water Chemistry Control -Primary and Secondary Neutron-Absorbing VI I .A2.AP-235 3.3.1-102 A Material Monitoring None Vll.J.AP-17 3.3.1-120 A Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None Vll.J.AP-17 3.3.1-120 A Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Page 3.3-154 Table 3.3.2-10: Fuel Pool Cooling and Purification System Component Intended Type Function Material Environment Rack Support for Stainless steel Treated borated criterion (a)(1) water (ext) equipment Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated borated boundary water (int) Tubing Pressure Stainless steel Air-indoor boundary (ext) Tubing Pressure Stainless steel Treated borated boundary water (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) Valve body Pressure Stainless steel Treated borated boundary water (int) Valve body Pressure Stainless steel Waste water boundary (int) 3.0 Aging Management Review Results ( Aging Effect Requiring Management Loss of material None Loss of material None Loss of material None Loss of material Loss of material Aging Management Program Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.A3.AP-79 3.3.1-125 C, 301 Vll.J.AP-17 3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Vll.J.AP-17 3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Vll.J.AP-17-3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-155 Table 3.3.2-11 Nitrogen System Summary of Aging Management Evaluation Table 3.3.2-11: Nitrogen System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Accumulator Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Accumulator Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Accumulator Pressure Carbon steel Gas (int) None None boundary Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity boundary (ext) Flex hose Pressure Stainless steel Air-indoor None None boundary (ext) Flex hose Pressure Stainless steel Gas (int) None None boundary Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces components boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.AP-126 3.3.1-12 B Vll.l.AP-263 3.3.1-15 B Vll.J.AP-17 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Vll.l.A-405 3.3.1-132 A Page 3.3-156 Table 3.3.2-11: Nitrogen System Component Intended Type Function Material Environment Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Gas (int) boundary Flow control Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -indoor. (int) boundary Piping Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Gas (int) boundary Piping Pressure Carbon steel Waste water boundary (int) Regulator body Pressure Aluminum Air-indoor boundary (ext) Regulator body Pressure Aluminum Gas (int) boundary Tubing Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging _Management Review Results Aging Effect Requiring Management None None Loss of material Loss of material Loss of material None Loss of material None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes None Vll.J.AP-17 3.3.1-120 A None Vll.J.AP-22 3.3.1-120 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring None Vll.J.AP-6 3.3.1-121 A Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-135 3.3.1-113 A None Vll.J.AP-37 3.3.1-113 A None Vll.J.AP-17 3.3.1-120 A Page 3.3-157 Table 3.3.2-11: Nitrogen System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss*ofmaterial boundary (ext)
Tubing Pressure Stainless steel Gas (int) -None boundary Valve body Pressure Carbon steel Air..., indoor Loss of material boundary (ext)* Valve body Pressure Carbon steel Air..:. outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Gas (int) None boundary Valve body Pressure Carbon steel Wastewater Loss of material boundary (int) Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Gas (int) None. boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring External Surfaces Monitoring None External Surfaces Monitoring External Surfaces Monitoring None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.D.AP-209 3.3.1-4 ' c Vll.D.AP-221 3.3.1-6 c Vll.J.AP-22 3.3.1-120 A Vll.l.A-77 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Internal Surfaces in V11.E5.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-1.7 3.3.1-120 A INone Vll.J.AP-22 3.3.1-120 A Page 3.3-158 Table 3.3.2-12 Miscellaneous HVAC Systems Summary of Aging Management Evaluation Table 3.3.2-12: Miscellaneous HVAC Systems ., Aging Effect Aging Component Intended Requiring Management . Type Function Material Environment Management Program aolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Halting Integrity boundary (ext) Bolting Pressure High strength. Air-*indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-*indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss .of preload Bolting Integrity ,. boundary steel (ext) Bolting Pressure Stainless steel Air :-indoor " Loss of preload Bolting 'Integrity boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces boundary Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item *.Notes Vll.l.AP-125 3.3.1-12 B 3.3.1-15 B
Vll.l.AP-126 3.3 .. 1-12 B Vll.l.AP.,.263 3.3.1-15 B Vll.l.A-04 3.3.1-10 D ViLl.AP-125 3.3.1-12 B Vll.l.AP-1.24 3.3.1-15 B Vll.l.AP-124 B Vll.F2.A-10 3.3.1-78 A V.A.E-29 3.2.1-44 E ' Page 3.3-159 Table 3.3.2-12: Miscellaneous HVAC Systems Aging Effect Component Intended Requiring Type Function Material Environment Management Damper housing Pressure Carbon steel Air -outdoor Loss of material boundary (int) Ducting Pressure Carbon steel Air-indoor Loss of material boundary (ext) Ducting Pressure Carbon steel Air -indoor (int) Loss of material boundary Ducting Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Ducting Pressure Carbon steel Air -outdoor Loss of material boundary (int) Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel, Air -indoor (int) Loss of material boundary Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Filter housing Pressure Carbon steel Air-indoor Loss of material boundary (ext), Filter housing Pressure Carbon steel Air -indoor (int) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components External Surfaces Vll.F3.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Page 3.3-160 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Filter housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Carbon steel Air -outdoor boundary (int) Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Air -indoor (int) boundary Filter housing Pressure Stainless steel Condensation boundary (int) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material None None Loss of material Change in material properties Cracking Loss of material -wear Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.F2.AP-99 3.3.1-94 A Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F2.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F2.AP-113 3.3.1-82 A Monitoring Page 3.3-161 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Flex connection Pressure Elastomer Air -indoor (int) boundary Flex hose Pressure Stainless steel Air-indoor boundary (ext) Flex hose . Pressure Stainless steel Air -indoor (int) boundary Heat exchanger Heat transfer Copper alloy Condensation (fins) (ext) Heat exchanger Heat transfer Copper alloy Condensation (fins) (ext) Heat exchanger Pressure Carbon steel Air-indoor (housing) boundary (ext)
Heat exchanger Pressure Carbon steel Air-indoor (int) (housing) boundary Heat exchanger Pressure Carbon Air -indoor (int) (housing) boundary 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material -wear .. None None Loss of material Reduction of heat transfer Loss of materiaJ Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vll.F2.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A -None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in 3.3.1-89 C, 306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----G Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.AP-41 3.3.1-80 A . Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components Page 3.3-162 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Heat exchanger Heat transfer Copper alloy Condensation (tubes) (ext) Heat exchanger Pressure Copper alloy Condensc;ition (tubes) boundary (ext) Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Heater housing Pressure Carbon steel Air-indoor boundary (ext) Heater housing Pressure Carbon steel Air -indoor (int) boundary Heater housing Pressure Carbon steel Air -outdoor boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of heat transfer Loss of material Reduction of heat transfer Loss of material Loss of material Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in ----G* Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Water Chemistry Vll.F2.AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F3.AP-203 3.3.1-46 A Control Closed Treated Water Systems External Surfaces Vll.F2.AP-41 3.3.1-80 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components Page 3.3-163 Table 3.3.2-12: Miscellaneous HVAC Systems Aging Effect Component Intended Requiring Type Function Material Environment Management Nozzle Pressure Stainless steel Air-indoor None boundary (ext) Flow control Nozzle Pressure Stainless steel Air -indoor (int) None boundary Flow control Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary Pump casing Pressure Stainless steel Air-indoor None boundary (ext) Pump casing Pressure Stainless steel Air -indoor (int) None boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Air -indoor (int) None boundary Sight glass Stainless steel Air-indoor None boundary (ext) Sight glass Pressure Stainless steel Air -indoor (int) None boundary 3.0 Aging Management Review Results Aging Management Program None None External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.l.A-77 3.3.1-78 A Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-14 3.3.1-117 A None Vll.J.AP-48 3.3.1-117 A None VI l.J .AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Page 3.3-164 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) boundary Tubing Pressure Stainless steel Air-indoor boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) boundary Tubing Pressure Stainless steel Air -outdoor boundary (ext) Tubing Pressure Stainless steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Air-indoor . boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) boundary Valve body Pressure Carbon steel Air -indoor (int) boundary Valve body Pressure Carbon steel Waste water boundary (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management None None None None Cracking Loss of material Loss of material Loss of material Loss of material Loss of material None Aging Management Program None None None None External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.F2.AP-209 3.3.1-4 A Vll.F2.AP-221 3.3.1-6 A Vll.l.A-77 3.3.1-78 A V.A.E-29 3.2.1-44 E Internal Surfaces in V.A.E-29 3.2.1-44 A
Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Page 3.3-165 Table 3.3.2-12: Miscellaneous HVAC Systems I c Aging Effect Component Intended 'Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Stainless steel Wastewater Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-166 Table 3.3.2-13 Auxiliary Diesel Generator System Summary of Aging Management Evaluation Table 3.3.2-13:Auxiliary Diesel Generator System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Expansion joint Pressure Stainless steel Air-indoor None None boundary (ext) Flame arrestor Pressure Aluminum Air -outdoor Cracking External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Aluminum Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Aluminum Air -outdoor Cracking External Surfaces boundary (int) Monitoring Flame arrestor Pressure Gray cast iron Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Gray cast iron Air -outdoor Loss of material External Surfaces boundary (int) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-123 3.3.1-120 A ----H Vll.l.AP-256 3.3.1-81 A ----H Vll.H1.A-24 3.3.1-80 A ----G, 305 Vll.l.A-77 3.3.1-78 A Page 3.3-167 Table 3.3.2-13:Auxiliary Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure* Carbon steel Condensation Loss of material boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue boundary (int) Piping Pressure Carbon steel Exhaust gas Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Silencer. Pressure Carbon steel Air-*indoor Loss of material boundary (ext) Silencer Pressure Carbon steel Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes External Surfaces Vll.H1.A-24 3.3.1-80 A Monitoring Internal Surfaces in Vlll.B1.SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.H2.A-23 3.3.1-89 A Miscellaneous Piping and Ducting Components TLAA-metal ----H fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in Vll.H2.A-23 3.3.1-89 A Miscellaneous Piping and Ducting Components Page 3.3-168 Table 3.3.2-13:Auxiliary Diesel Generator System Component Intended Type Function Material Environment Silencer Pressure Carbon steel Exhaust gas boundary (int) Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Fuel oil (int) boundary . Tubing Pressure Carbon steel Air-indoor boundary (ext) Tubing Pressure Carbon steel Fuel oil (int) boundary Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Fuel oil (int) boundary 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1 .AP-105 3.3.1-70 A, 303 .Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel VJl.H1.AP-105 3.3.1-70 A, 303 Monitoring Page 3.3-169 Table 3.3.2-14:Plant Drains Intended Component Type Function Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary. Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary Piping Pressure boundary Piping Pressure boundary Piping Pressure boundary 3.0 Aging Management Review Results Table 3.3.2-14 Plant Drains Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NUREG-1801 Table 1 M;;iterial Environment Management Program Item Item Notes Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B (ext) Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B (ext) Carbon steel Waste water Loss of material Bolting Integrity ----G (ext) Carbon steel Waste water Loss of preload Bolting Integrity ----G (eXt) .. Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B steel (ext) Stainless Air-*outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B steel (ext) Stainless Air -outdoor _Loss of preload Bolting Integrity Vl,l.l.AP-263 3.3.1-15 B steel (ext) Carbon steel . Air-indoor .Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A (ext) Monitoring Carbon steel Air -o*utdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A (ext) Monitoring . Carbon steel Air -outdoor Loss of material Internal Surfaces in VllLB1.SP-59 3.4.1-36 c (int) Miscellaneous
Piping and Ducting Components Page 3.3-170 Table 3.3.2-14:Plant Drains Aging Effect Intended -Requiring Component Type Function Material Environment Management Piping Pressure Carbon steel _ Soil (ext)' ' 'Loss of material boundary '* Piping Pressure .Carbon steel Wastewater Loss of material boundary (int) \ \ Piping Pressure Stainless Air -indqor None boundary steel (ext) Piping Pressure Stainless Air-in.door (int) None boundary steel Piping Pre.ssure Stainless Treated water . Loss qf material boundary steel (int) Piping Pressure Stainless Wastewater .of mate.rial boundary steel (int) Pump casing Pressure Carbon steel Wastewater Loss of material boundary (ext) Pi.Imp casing Pressure. Carbon steel W(3ste water Loss of material boundary (int) 3.0 Aging Manageme11t Review Results Aging Management Program Buried and Underground Piping and Tanks Inspection Waterford Steam Electric Station, Unit 3 License Renewal Application , Technical Information NUREG-1801 Table 1 Item Item Notes* VILC1.AP-;198 3.3.1-106 c Internal Surfaces in VI I. E5 .. AP-28.1 3.3.1-91 A Miscellaneous Piping and Ducting
Components Npne* VILJ.AP-123 . 3.3.1-120 A None. Vll.J.AP-123 3.3.1-120 A ' Water Chemistry Vlll.81.SP-87 3.4.1-16 C, 301 Control -Primary and Secondary Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A . Mi.scellaneous Piping and Ducting ' Components Surfaces VILE5.A-410 3.3.1-135 A Monitoring Periodic Vll.E5.A-410 3 .. 3.1-135 E Surveillance and Preventive Maintenance Page 3.3-171 Table 3.3.2-14:Plant Drains* Aging Effect -Intended Requiring Component Type Function Material Environment Management Pump casing Pressure Gray cast iron Air -outdoor Loss of material boundary (ext) Pump casing Pressure Gray cast iron Waste water Loss of material boundary (int) Pump casing Pressure Gray cast iron Waste water Loss of material boundary (int) Strainer Filtration Stainless Waste water Loss of material steel (ext) Strainer housing Pressure Stainless Air-indoor None boundary steel (ext) Strainer housing Pressure Stainless Air -outdoor Cracking boundary steel (ext) Strainer housing Pressure Stainless Air -outdoor Loss of material boundary steel (ext) Strainer housing Pressure Stainless Treated water Loss of material boundary steel (int) Strainer housing Pressure Stainless Waste water Loss of material boundary steel (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Periodic Vll.E5.A-410 3.3.1-135 E Surveillance and Preventive Maintenance Selective Leaching Vll.E5.A-407 3.3.1-72 A Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.C1 .AP-209 3.3.1-4 c Monitoring External Surfaces Vll.C1 .AP-221 3.3.1-6 c Monitoring Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 Control -Primary and Secondary Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Page 3.3-172 Table 3.3.2-14:Plant Drains Aging Effect Intended Requiring Component Type Function Material Environment Management Tubing Pressure Stainless Air-indoor None boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material boundary steel (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Waste water Loss of material boundary (int) Valve body Pressure Copper alloy Air -outdoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes. None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vll.E5.AP-281 3.3.1-91 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring Page 3.3-173 Table 3.3.2-14: Plant Drains Aging Effect Intended Requiring Component Type Function Material Environment Management Valve body Pressure Copper alloy Waste water Loss of material boundary (int) Valve body Pressure Copper alloy Air -outdoor Loss of material boundary > 15% Zn or (ext) >8%AI Valve body Pressure Copper alloy Wastewater Loss of material boundary > 15% Zn or (int) >8%AI Valve body Pressure Copper alloy Wastewater Loss of material boundary > 15% Zn or (int) -.. >8%AI Valve body Pressure Gray cast iron Wastewater Loss of material boundary (ext) Flow control Valve body Pressure Gray cast iron Wastewater Loss of material boundary (ext) ' Flow control Valve body Pressure Gray cast iron Wastewater . Loss of material boundary (int) Flow control 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vll.E5.AP-272 3.3.1-95 A Miscellaneous Piping and Ducting . Components External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring . Internal Surfaces in VII. E5.AP-272 3.3.1-95 A Miscellaneous Piping and Ducting Components Selective Leaching Vll.E5.A-407 3.3.1-72 A External Surfaces Vll.E5.A-410 3.3.1-135 c Monitoring Selective Leaching Vll.E5.A-407 3.3.1-72 A Internal Surfaces in VI I. E5.AP-281 3.3.1-91 A Miscell*ineous Piping and Ducting Components Page 3.3-174 Table 3.3.2-14:Plant Drains Intended Component Type Function Valve body Pressure boundary Flow control Valve body Pressure boundary Valve body Pressure boundary Valve body Pressure boundary Valve body Pressure boundary Valve body . Pressure boundary Valve body* Pressure boundary 3.0 Aging Man.agement Review Results ( \ Material Environment Gray cast iron Wastewater (int) Stainless f.ir -indoor steel* (ext) Stainless Air -in.door (int) stainless Air -outdoo'r steel (ext) Stainless Air -outdoor . steel (ext) Stainless Treated water steel (int) Stainless Wastewater steel (int) Aging Effect Requiring Management Loss of material None None Cracking Loss of material Loss of material Loss of material Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes SeleCtive Leaching VI I. E5.A-407 3.3.1-72 A None Vll.J.AP..:123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120' A External Surfaces Vll.C1 .AP-209 3.3.1-4 c Monitoring . External Surfaces VllC1 .AP-221 3.3.1-6 c Monitoring Water Chemistry Vlll.B1.SP-87 '3.4.1-16 C, 301 Control -Primary and.Secondary Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Page 3.3-175 Table 3.3.2-15-1 Air Evacuation System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-1 :Air Evacuation System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous* Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-176 Table 3.3.2-15-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-2:Airborne Radioactivity Removal System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-177 Table 3.3.2-15-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Annulus Negative Pressure System Nonsafety-Related Components. Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-3:Annulus Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect . Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment r Management Program Item Item Notes Blower housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in 3.2.1-44 A boundary Miscellaneous Piping and Ducting Components Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Bolting Pressure steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon.steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 A boundary Miscellaneous Piping and Ducting Components Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-178 Waterford Steam Electric Station, Unit 3 License Renewal Application *Technical Information Table Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems . ' Aging Effect Aging* Component Intended Requiring ' Management NUREG-1801 -Table 1 Type Function Material Environment Management Progral'!" Item Item Notes Ducting Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 A boundary Miscellaneoas Piping and Ducting Components 3.0 Aging Mahagement Review Results Page 3.3-179 ( \

Table 3.3.2-15*4

Auxiliary Steam System Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation _Table 3.3.2-15-4:Auxiliary Steam. System, Nonsafety-Related Components Affecting Safety-Re.lated Systems Aging Effect Aging Component Intended Requiring Management . NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-1,25 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of.preload Bolting Integrity Vll.l.AP-1.24 3.3.1-15 B boundary (ext) Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary Control ._ Primary and Secondary
Flow element Pressure Stainless steel Steam (int) Cracking -fatigue TLAA-metal ----H boundary fatigue Flow element Pressure Stainless steel Steam (int) Loss of material Water Chemistry 3.4.1-16 C, 301 boundary Control -Primary ... and Secondary Flow element Pressure Stainless steel Waste water Loss of material .Periodic VI I. E5.AP-278 3.3.1-95 E (int) Surveillance and .. Preventive Maintenance Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-180 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-4:Auxiliary Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Piping Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAG Corrosion Piping Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Waste water Loss of material Periodic VII. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-181 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary fatigue Trap Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Trap Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Trap Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary fatigue Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Valve body Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-182 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-1,5-4:Auxiliary Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management .. 'NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve.body Pressure Stainless steel Steam (int) Cracking Water Chemistry . Vlll.A.SP-98 3.4.1-11 C, 301 boundary Control -Primary and Secondary Valve body Pressure Stainless steel steam (int)
Cracking -fatigue TLAA.,..,metal ---H boundary
body Pressure Stainless steel Steam (int) Loss of material .Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundar"Y Control -Primary . and Secondary , 3.0 Aging Management Review Results Page 3.3-183 Table 3.3.2-15-5 Boric Acid Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-5: Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item* Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C,301 boundary water (int) Control -Primary and Secondary Sight glass Pressure Glass Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated borated None None Vll.J.AP-52 3.3.1-117 A boundary water (int) Sight glass Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Sight glass Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-184 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-5: Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended *Requiring Management NUREG-1801 Table 1 Type Function Material E.nvironment Management Program Item Item Notes Strainer housing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Strainer housing Pressure Stainless steel
Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel indoor None None Vll.J.AP.:18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 C,.301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry VI l.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-185 Table 3.3.2-15-6 Boron Management System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-6:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting. Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Condenser Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c (Shell) boundary (ext) Condenser Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 (Shell) boundary water (int) Control -Primary and Secondary Cooler housing Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary (ext) Cooler housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Demineralizer Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Demineralizer Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-186 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-G:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Evaporator Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary (ext) Evaporator Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Filter housing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Filter housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Insulated piping Pressure Stainless steel Condensation Cracking External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Insulated piping Pressure Stainless steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Orifice Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Orifice Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 *boundary water Control -Primary and Secondary Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-187 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems : Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Piping Pressure Stainless ste.el Waste water Loss of material . Internal Surfaces.in Vll.ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting ' Components Piping Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Pump casing Pressure Stainless steel Air-indoor None None 3.3.1-120 A boundary (ext) -Pump casing Pressure Stainless steel Treated borated Loss of material
Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Pump casing Pressure Stainless steel Waste water Lqss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary (int) Surveillance and P'reventive Maintenance Sight glass Pressure Glass Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary * (ext) Sight glass Pressure Glass* Treated !;>orated None* None Vll.J.AP-52 3.3.1-117 A .. water (int) Sight glass P*ressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A bouridar}t* (ext) 3.0 Aging Management Review Results Page 3.3-188 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management
Program Item Item Notes Sight glass Pressure Stainless steel Treated borated Loss of material Water-Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Strainer housing Pressure Stainless steel Air-indoor None None . Vll.J.AP-17 3.3.1-120 A boundary (ext) Strainer housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material . Water Chemistry Vll.E1.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Trap Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Trap Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive* Maintenance Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary 3.0 Aging Management Review Results Page 3.3-189 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 *Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-190 Table 3.3.2-15-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Chemical and Volume Control System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.1.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Demineralizer Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Demineralizer Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Flex hose Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Flex hose Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1.AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-191 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended .. .Requiring Management NUREG-1801 Table 1 Type Function Material
Environment Management Program Item Item Notes Piping.* Pressure Stainlesl) steel Treatec! water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301. boundary (int) Control -Primary and Secondary Piping Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) ' . Pump casing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125. *A, 301 boundary water (int) -Primary and Secondary Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81.SP-87 3.4.1-16 C, 301 boundary (int) Control Primary and Secondary Sight glass Pressure Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary .. (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A bound?ry (int) " Sight glass Pressure Stainless steel Air -indoor . None None Vll.J.AP-18 3.3.1-120 A boundary .. (ext> Sight glass Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81.SP-87 3.4.1-16 C,301 boundary (int) Control -Primary and Secondary Strainer housing Pressure Stainless steel Air-indoor None Norie Vll.J.AP-18 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-192 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.B1.SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor No11e None Vll.J.AP-18 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-193 Waterford Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-194
Table 3.3.2-15-8 Chemical Feed System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cylinder Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Cylinder Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless steel* Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting -Components Piping Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-195 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging .component Intended Requiring Management NUREG-1801 Table 1 Type Function Material
Environment Management Program Item Item Notes Pump casing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Pump casing Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c b<;)undary (int) Miscellaneous I Piping and Ducting Components Sight glass Pressure Carbon steel Air-indoor Loss of material. External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary -(ext) Tank Pressure Stainless steel Wastewater Loss of material Internal Surfaces ii'! VI I. E5.AP-278 3.3.1-95 c boundary (int) . Miscellaneous ., Piping and Ducting Component!;l. Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) '. 3.0 Aging Management Review Results Page 3.3-196 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive ' Maintenance Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water
Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-197 Table 3.3.2-15-9 Chilled Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment
Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H bouhdar}t (ext) Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A \ boundary (int) Control -Closed Treated Water Systems Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A . boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-198 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting* Components Piping Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None Vll.J.AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-199 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System; Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated.Water Systems Tank Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous*
Piping and Ducting
Components . Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ex.t). Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 c (int) I Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Waste water
Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int)
Surveillance and Preventive Maintenance Valve body Pressure Copper alloy >
Air -indoor None None Vll.J.AP-144 3.3.1-114 A boundary 15% Zn or>8% (ext)* Al 3.0 Aging Management Review Results Page. 3.3-200 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related ComponentS Affecting Safety-Related Systems Aging Effect Aging Component Intended Requirjng Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Copper .alloy > Condensation Loss of material External Surfaces Vll.F1.AP-109 3.3.1-79 c boundary 15% Zn or> 8% (ext) Monitoring Al -Valve body Pressure Copper alloy > Treated water Loss of material Selective Leaching Vll.C2.AP-43 3.3.1-72 A boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Treated water I,.oss of material Water Chemistry Vll.C2.AP-199 3.3.1-46 A boundary 15% Zn or> 8% (int) Control -Closed Al Treated Water Systems 3.0 Aging Management Review Results Page 3.3-201 Table 3.3.2-15-1 O Circulating Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes -Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H boundary_ (ext) Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Sight glass Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Sight glass Pressure Glass Condensation None None Vlll.l.SP-68 3.4.1-55 c boundary (ext) 3.0 Aging Management Review Results Page 3.3-202 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Sight glass Pressure Glass Raw water (int) None None Vll.J.AP-50 3.3.1-117 A boundary Strainer housing Pressure Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Strainer housing Pressure Stainless steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-409 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous ' Piping and Ducting Components Valve body Pressure Copper alloy > Condensation Loss of material External Surfaces Vll.F1.AP-109 3.3.1-79 c boundary 15% Zn or> 8% (ext) Monitoring Al Valve body Pressure Copper alloy > Raw water (int) Loss of material Internal Surfaces in VI I. C 1.A-408 3.3.1-134 c boundary 15% Zn or> 8% Miscellaneous Al Piping and Ducting Components Valve body Pressure Copper alloy > Raw water (int) Loss of material Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary 15% Zn or > 8.% Al Valve body Pressure Gray cast iron Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-203 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Gray cast iron Raw water (int) Loss of material Internal Surfaces in VI I. C 1.A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Gray cast iron Raw water (int) Loss of material Selective Leaching Vll.C1 .A-51 3.3.1-72 c boundary 3.0 Aging Management Review Results Page 3.3-204 Table 3.3.2-15-11
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management .Evaluation Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H boundary (ext) Filter housing Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Filter housing Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Flow element Pressure . Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-205 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.H1 .A-24 3.3.1-80 c boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Plastic Condensation None None --F boundary (ext) Piping Pressure Plastic Treated water None None --F boundary (int) Sight glass Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Condensation None None Vll.J.AP-97 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) 3.0 Aging Management Review Results Page 3.3-206 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless steel Condensation Loss of material External Surfaces ---G boundary (ext) Monitoring Strainer housing. Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A-boundary (int) Control -Closed Treated Water Systems Tank Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Treated water Loss of material Water Chemistry VI I. C2.AP-202 3.3.1-45 A boundary (int) Control -Closed *Treated Water Systems Tubing Pressure Stainless steel Condensation Loss of material External Surfaces ---G boundary (ext) Monitoring Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.1.A-81 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry VI I ,C2.AP-202 3.3.1-45 A boundary (int) Control -Closed . Treated Water Systems 3.0 Aging Management Review Results Page 3.3-207 )

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging -. Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in VIL E5.,A.P-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Valve body Pressure. Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-208 Table 3.3.2-15-12 Compressed Air System Waterford Steam Electric Station, Unit 3

License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-12:Compressed Air System, Nonsafety-RelatedComponents Affecting Safety-Related Systems Aging Effect Aging. Intended Requiring' Management *NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity VIU.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity VII .l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure. Stainless Condensation Loss of material Compressed Air 3.3.1-56 A boundary steel (int) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.D.A-80 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 A boundary (int) MonitQring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 . 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary (ext) Piping Pressure Copper alloy Condensation Loss of material Compressed Air Vll.D.AP-240 3.3.1-54 A boundary (int) Monitoring 3.0 Aging Management Review Results Page (

Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information Table 3.3.2-15-12:Compressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tubing Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A bound.ary. (ext) Tubing Pressure Copper alloy Condensation Loss of material Compressed Air Vll.D.AP-240 3.3.1-54 A boundary (int) Monitoring Tubing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 A boundary steel (int) Monitoring Valve body *Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.D.A-80 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 A boundary (int) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary > 15% Zn or (ext) >8%AI Valve body Pressure Copper alloy Waste water Loss of material Internal Surfaces in VI I. E5.AP-272 3.3.1-95 c boundary > 15% Zn or (int) Miscellaneous >8%AI Piping and Ducting Components Valve body Pressure Copper alloy Waste water Loss of material Selective Leaching Vll.E5.A-407 3.3.1-72 c boundary > 15% Zn or (int) >8%AI 3.0 Aging Management Review Results Page 3.3-210 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-12:Gompressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect *Aging* Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material EnvironmE;!nt Management Program Item Item Notes Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 1-120 A boundary steel* (eXt) Valve body Pressure Stainless Wastewater Loss of material . Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary

steel (iht) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-211 Table 3.3.2-15-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-13:Containment Atmosphere Purge System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting . Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel . Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Concrete (ext) None None Vll.J.AP-282 3.3.1-112 A boundary Heater housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.AP-41 3.3.1-80 A boundary (ext) Monitoring Heater housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-212 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-13:Containment Atmosphere Purge System *. Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Pi:ogram Item Item Notes Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-213 Table 3.3.2-15-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-14:Containment Atmosphere Release System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-214
Table* 3.3.2-15-15 Containment Building Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-15:Containment Building, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801" Table 1 Component Ty.pe Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext)' Bolting Pressure* Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Tubing Pressure Stainless Air-indoor None . None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 c boundary steel (int) Monitoring Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 c bound9_ry steel (int) Monitoring 3.0 Aging Management Review Results Page 3.3-215 (

Table 3.3.2-15-16 Decontamination Facility Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-16:Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) . Filter housing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-216 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-16:Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring NUREG-1601 Table 1 Component Type. Function Material Environment Management Program Item Item Notes Pump casing Pressure. Stainless

Waste water Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure
Stainless . Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel *
Strainer housing Pressure Stainless
Waste water
Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting
ComponE;?nts Tank Pressure Stainless* Air:-indoor None None Vll.J.AP-123 3.3.1-120 c boundary " steel (ext) Tank Pressure Stainless Waste water Loss of material Internal.Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (irit) Miscellaneous Piping and Ducting Components / Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of matE;?rial Internal Surfaces in VI I. ES.AP-278 3.3.1-95 . c boundary steel (int) Miscellaneous . }--, Piping and Ducting .. Components 3.0 Aging Management Review Results Page 3.3-217 Table 3.3.2-15-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-17:Emergency Diesel Generator System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 c boundary (int) Monitoring Piping Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 boundary Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-218 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-17:Emergency Diesel Generator System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-138 3.3.1-100 A, 302 boundary steel **. Valve body Pressure Stainless Treated water Loss of material . Water Chemistry Vll.C2.A-52 . 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systeml) Valve body Pressure Stainless ** Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous . ' Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-219 Table 3.3.2-15-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-18:Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-.1801 Table 1 Component Type Function Materi(ll Environment Management Program Item Item Notes Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Blower housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring *-Piping Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-220 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-18:Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting -Components 3.0 Aging Management Review Results
Page 3.3-221 Table 3.3.2-15-19 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-19:Fuel Pool Cooling and Purification System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry VI l.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-222 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-19:Fuel Pool Cooling and Purification System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 *Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A bc;iundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Treated borated Loss of material Water Chemistry VI I .A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-223 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-19:Fuel Pool Cooling and Purification System,* Nonsafety*Related Components Affecting Safety-Related Systems . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-224 Table 3.3.2-15-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Sumrriary of Aging Management Evaluation Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function *Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Lo_ss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Stainless . Air -indoor None None Vll.J.AP-17 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water
Syster:ris Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting : Coriponents Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Gas (int) None None* Vll.J.AP-6 3.3.1-121 A boundary 3.0 Aging Management Review Results Page 3.3-225 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry VI I. C2.AP-202 3.3.1-45 c boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Separator Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Separator Pressure Stainless Gas (int) None None Vll.J.AP-22 3.3.1-120 A boundary steel Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Sight glass Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Sight glass Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-226 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Agir:1g Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Carbon steel Air -indoor. Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Mon'itoring Trap Pressure Carbon steel Waste water of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Trap Pressure Stainless Waste water . Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Gomponents Valve body Pressure Stainless Air-indoor None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Gas (int) . None None 3.3.1-120 A boundary steel Valve body Pressure Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel . (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-227 Table 3.3.2-15-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information H.ot Macbine Shop and Decon Facility Vent System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-21:Hot Machine Shop & Decon Vent System, Nonsafety-Related Components Affecting_Safety-Related Systems Aging Effect Aging Intended . Requiring Management
NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting *Pressure Carbon steel Air --indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air --indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Riping Pressure Carbon steel . Air..: indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting pomponents Valve body Pressure Air --indoor None None Vll.J .. AP-123 3.3.1-120 A boundary steel <ext> *Valve body Pressure Stainless Waste water Loss of materii;il Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components* 3.0 Aging Management Review Results Page 3.3-228 Table 3.3.2-15-22 Leak Rate Testing System Waterford Steam*Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-22:Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item* Item Notes Bolting Pressure Carbon Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces
Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring .. Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary , (int) Miscellaneous Piping* and Ducting Components Piping Pressure Copper alloy Air -indoor (int) None None Vll.J.AP-144 3.3.1-114 A boundary 3.0 Aging Management Review Results Page 3.3-229 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-22:Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Copper alloy Air -outdoor Loss of material External Surfaces Vll.l.AP-159 3.3.1-81 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-230 Table 3.3.2-15-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Liquid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 . B boundary steel (ext) Condenser (Shell) Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Condenser (Shell) Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance
Cooler housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Demineralizer Pressure Stainless Air -indoor
None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Demineralizer Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-231 Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management Syste*m, Nonsafety-Related Components Affecting Safety-Related Systems -Aging Effect Aging Intended Requiring Management NUREG-1801 Table1 Component Type . Function* Material Environment Management Program Item Item Notes Evaporator Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Evaporator Pressure Stainless, Waste water Loss of material Periodic Vll.E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive* .. Maintenance Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary . steel (int) Miscellaneous Piping and Ducting ** Components Orifice Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel. (ext) Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Garbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281. 3.3.1-91 A ** boundi!iry (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None VILJ.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-232 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Systems Aging Effect Aging Intended* Requiring Management NUREG-1801 . Table 1 Component Type Function Material Environment " Management Program Item Item Notes Piping Pressure Stainless VV?Ste water Loss of material Internal Surfaces in 3.3.1-95 A boundary steel (int) Miscellaneo'us Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance .and Preventive Maintenance . Pump casing . *Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in VII. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous .. Piping and Ducting
Components Sight glass Pressure Glass Air -indoor
None None VI l.J .AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Sight glass Pressure
Stainless . Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) .. Sight glass Pressure Stainless Waste* water Loss of material Internal Surfaces in VII. 3.3.1-95 A boundary steel (int) .. Miscellaneous Pipi.ng and Ducting Components Strainer housing Pressure Stainless Air. -indoor None. None Vfl.J.AP-123 3.3.1-120 A boundary steel (ext) ' . 3.0 Aging Management Review Results Page 3.3-233 Waterford Steam Electric Station, Unit 3 .License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components. Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-234 Table 3.3.2-15-24 Nitrogen System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-24:Nitrogen System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Gas (int) None None Vll.J.AP-22 3.3.1-120 A boundary steel Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Carbon steel Air -indoor . Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and. Ducting Components 3.0 Aging Management Review Results Page 3.3-235 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type
Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78. A boundary. (ext) Monitoring Trap Pressure Carbon steel Waste water Loss of material Internal Surfaces in VII.. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of materiar External Surfaces Vll.l.A-77 3,3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary ,, Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c *boundary Miscellaneous Piping and Ducting 3.0 Aging Management Review Results Page 3.3-236 Table 3.3.2-15-25 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Chiller housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 c boundary (ext) Monitoring Chiller housing Pressure Carbon steel Waste water Loss of material Internal Surfaces in VII. E5.AP-281 3.3.1-91 c boundary . (int) Miscellaneous Piping and Ducting Components Heat exchanger Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c (shell) boundary steel (ext) Heat exchanger Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c (shell) boundary steel (int) Control -Closed Treated Water Systems Orifice Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-237 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.ES.AP-278 \ 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping . Pressure Stainless Air -indoor , None None Vll.J.AP-123 3.3.1..:120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components s.trainer housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Wastewater Loss of material lnternal*Surfaces in VILE5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainles's Air:_ indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-238 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Environment Management Program Item Item Notes Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-239 Table 3.3.2-15-26 Potable Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation Table 3.3.2-15-26:Potable Water System, Nonsafety-Related Components Affecting Safety-Related Systems ' . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel water (int) Loss of material Internal Surfaces in VI I. c boundary Miscellaneous Piping and Ducting Components Pump casing Pressure Copper alloy Air-indoor None None* VILJ.AP-144 3.3.1-114 A boundary > 15% Zn or (ext) >8%AI '. Pump casing Pressure Copper alloy Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-271 3.3.1-93 c boundary > 15% Zn or Miscellaneous ?' 8% Al Piping and Ducting Components . Pump casing Pressure Copper alloy Raw water (int) Loss Of mc:iterial Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary > 15% Zn or >8%AI 3'.0 Aging Management Review Results Page 3.3-240 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-26:Potable Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-270 3.3.1-88 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary > 15% Zri or (ext) >8%AI Valve body Pressure Copper alloy Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-271 3.3.1-93 c boundary > 15% Zn or Miscellaneous >8%AI Piping and Ducting Components Valve body Pressure Copper alloy Raw water (int) Loss of material Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary > 15% Zn or >8%AI Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-270 3.3.1-88 c boundary steel Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-241 Table 3.3.2-15-27 Primary Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-27:Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material
Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) , Insulated piping Pressure Stainless Condensation Cracking External Surfaces Vll.l.A-405 3.3.1-132 A components boundary steel (ext) Monitoring Insulated piping Pressure Stainless Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary steel (ext) Monitoring Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel (int) Control -Primary and Secondary Piping Pressure *Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-242 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-27:Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-243 Table 3.3.2-15-28 Primary Sampling System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ' ' Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Systems Aging Effect Aging Intended '* Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure *carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload
Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Flex hose Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Flex hose Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Flex hose Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water> 140°F Control -Primary (int) and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-79 3.3.1-9 A (shell) boundary (ext) Corrosion Heat exchanger . Pressure Carbon steel Air-indoor Loss of.material External Surfaces Vll.l.A-77 3.3.1-78 A (shell) boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-244
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-189 3.3.1-46 c (shell} boundary (int) Control -Closed Treated Water Systems Piping. Pressure steel Air .... indoor Loss of material Boric Acid Vll.l.A-79 3.3.1-9 A . boundary (ext) Corrosion Piping Pressure Carbon steel Air*-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) -* Monitoring Piping Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary Piping Pressure Stainless Air-indoor None* None VI l.J .AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Treated borated Cracking -fatigue TLAA-metal Vll.E1.A-57 3.3.1-2 c boundary steel water > 140°F fatigue (int) *Piping Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary* steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-245 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping anq Ducting Components Trap Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Trap Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water (int) Control -Primary and Secondary Trap Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Trap Pressure Stainless Treated borated Cracking -fatigue TLAA-metal VII. E 1.A-57 3.3.1-2 c boundary steel water > 140°F fatigue (int) Trap Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air -i'ndoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary 3.0 Aging Management Review Results Page 3.3-246 Waterford Steam Electric Station, License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Treated borated Cracking -fatigue TLAA-metal Vll.E1.A-57 3.3.1-2 c . boundary steel water > 140°F fatigue (int) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 . C, 301
boundary steel water > 140°F Control-Primary (int) and Secondary Valve body Pressure Stainless Waste water Loss of material lpternal Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Vessel Pressure Stainless Air -indoor None None Vll.J.AP-17 * . 3.3.1-120 A boundary steel (ext) Vessel Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water > 140°F Control -Primary -(int) and Secondary Vessel Pressure Stainless Treated borated Cracking -fatigue TLAA -metal Vll.E1.A-57 3.3.1-2 c boundary steel water> 140°F fatigue (int) -Vessel Pressure Stainless Treated borated Loss of material Water Chemistry. Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water> 140°F Control -Primary (int) and Secondary . 3.0 Aging Management Review Results
Page 3.3-247 Table 3.3.2-15-29 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Aluminum Air-indoor None None Vll.J.AP-135 3.3.1-113 A boundary (ext) Filter housing Pressure Aluminum Wastewater Loss of material Internal Surfaces in ----G boundary (int) Miscellaneous Piping and Ducting Components Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c r boundary steel (int) Miscellaneous Piping and Ducting Components Filter housing Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-248 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Heat exchanger Pressure Carbon steel Air -indoor . Loss of material External Surfaces Vll.l.A-77 3.3.1-78 c (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c (shell) bo1,mdary (int) . MisceUaneous Piping and Ducting Components Piping Pressure *Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary* steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and . -Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-249 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Env.ironment Management Program Item Item Notes Trap Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.:?.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) , Tubing Pressure Stainless Air....:. indoor (int) None None Vll.J.AP-123 3.3.1-120 A boundary steel Valve body Pressure Stainless Air-indoor None None : Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Air -indoor (int) None None VI l.J .AP-123 3.3.1-120 A boundary steel Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure* Stainless Waste water Loss of material Periodic 3.3.1-95 E boundary steel *(int) Surveillance and Preventive .. ' Maintenance 3.0 Aging Management Review Results Page 3.3-250 Table 3.3.2-15-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table Auxiliary Building HVAC System, Affecting Safety-Related Systems Aging Effect
Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoc;>r Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B *boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting. Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A . boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 c boundary (int) Miscellaneous Piping 1?ucting Components Valve body Pressure Garb.on steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-251 ----

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-30:Reactor Auxiliary Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous* Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-252 Table 3.3.2-15-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Ag.ing Management Evaluation Table 3.3.2-15-31 :Reactor Cavity Cooling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Blower housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 B boundary (ext) Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1'-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring 3.0 Aging Management Review Results Pa*ge 3.3-253 Table 3.3.2-15-32 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management

Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless Air -indoor
None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Pump casing Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-254 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Intended Component Type Function Pump casing Pressure boundary Sight glass Pressure . boundary Sight glass Pressure boundary Sight glass Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Strainer housing
Pressure boundary Tank Pressure . boundary Tank Pressure boundary 3.0 Aging Management Review Results *, *. Material Environment Stainless Waste water steel (int) Glass Air-indoor (ext) Glass Waste water *(int) Stainless Air-indoor steel (ext) Stainless Wastewater steel (int) I Stainless Air-indoor steel (ext) .. Stainless Waste water steel (int) Stainless Air-indoor steel (ext) Stainless Waste water steel (int) Aging Effect Aging Requiring Management NUREG-1801 Table 1 Management Program Item Item Notes
Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-48 3.3.1-117 A None None Vll.J.AP-277 3.3.1-119 A None None Vll.J.AP-17 3.3.1-120 A Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-17 3.3.1-120 A Loss of material Internal Surfaces in 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-123 3.3.1-120 c Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-255 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-256 Table 3.3.2-15-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Secondary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Treated water Cracking Water Chemistry Vlll.B1 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Orifice Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-257
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air -indoor (int) Loss of material Periodic V.A.E-29 3.2.1-44 E boundary Surveillance and Preventive .. Ma,intenance Piping Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E qoundary {Int) Surveillance arid Preventive Maintenance .. Piping Pressure Stainless Air-indoor None None VII.J.AP-17 3.3.1-'120 A ' boundary steel (ext) Piping Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary steel Control -Prin:iary and Secondary Piping Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary steel fatigue Piping Pressure Stainless Steam (int) Loss of material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundary steel Control -Primary . and Secondary Piping Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Piping Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 c;301 boundary steel > 140°F (int) Control -.Primary and Secondary 3.0 Aging Management Review Results Page 3.3-258 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Pump casing Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Pump casing Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Strainer housing Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-259 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tank Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Tank Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Prim*ary and Secondary Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary steel Control -Primary and Secondary Tubing Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary steel fatigue Tubing Pressure Stainless Steam (int) . Loss of material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 *boundary steel Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None Vll.J .. AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C,301 . boundary steel Control -Primary and Secondary Valve body Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary. steel fatigue Valve body Pressure Stainless Steam (int) Loss of. material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundary steel Control -Primary .. and Secondary 3.0 Aging Management Review Results Page 3.3-260 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management . Program Item Item Notes Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Valve body Pressure Stainless Treated water *Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 ,SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-261 Table 3.3.2-15-34 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Solid Waste Management System N9nsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-34: Solid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Accumulator Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Accumulator Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary steel (ext) Piping Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillarice and Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-262 Waterford Steam Electric Station, Unit 3 -License Renewal Application Technical Information Table 3.3.2-15-34: Solid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-263 Table 3.3.2-15-35 Surrip Pump System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summ.ary of Aging Management Evaluation Table 3.3.2-15-3S:Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect . Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -,indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (eXt) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 A boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None Vll.J.AP-'123 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless
Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure
Stainless Air-indoor None Vll.J.AP-123 3:3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-264 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-35:Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring* Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Waste water . . Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of material . External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Wastewater Loss of material* Internal Surfaces in Vll.E5.AP-281 3.3.1-91 A boundary (int) Miscellaneous Piping and Ducting Components Valve body Pres$ure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-265 Table 3.3.2-15-36 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-36:Turbine Building Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None Vll.J.AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) Sight glass Pressure Stainless Air-indoor None None VI l.J .AP-123 3.3.1-120 A boundary steel (ext) Sight glass Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary steel (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-266 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-36:Turbine Building Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item *Notes Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary . (ext) Monitoring Tank Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-267 3.4 STEAM AND POWER CONVERSION SYSTEMS 3.4.1 Introduction Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of the aging management reviews for components in the steam and power conversion systems that are subject to aging management review. The following systems are addressed in this section (the system descriptions are available in the referenced section).
Condensate Makeup and Storage (Section 2.3.4.1)
Emergency Feedwater (Section 2.3.4.2)
Main Feedwater (Section 2.3.4.3)
Main Steam (Section 2.3.4.4)
Steam and Power Conversion Systems in Scope for 1 O CFR 54.4(a)(2) (Section 2.3.4.5) Table 3.4.1, Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the steam and power conversion system component group. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.4.2 Results The following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for the condensate storage system.
Table 3.4.2-1 Condensate Makeup and Storage System-Summary of Aging Management Evaluation
Table 3.4.2-2 Emergency Feedwater System-Summary of Aging Management Evaluation
Table 3.4.2-3 Main Feedwater System-Summary of Aging Management E'valuation
Table *3.4.2-4 Main Steam System-Summary of Aging Management Evaluation *
Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) Table 3.4.2-5-1 Slowdown System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Evaluation Table 3.4.2-5-2 Condensate System, Nonsafety-Related Components Affecting Related Systems__;_Summary of Aging Management Evaluation 3.0 Aging Management Review Results Page 3.4-1 Waterford Steam Electric Station, Unit 3 Licen_se Renewal Application -Technical Information
Table 3.4.2-5-3 Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *
Table 3.4.2-5-4 Emergency Feedwater System, Nonsafety-Related Components Affecting Safety-Related Systems;_:_Summary of Aging Management Evaluation
Table 3.4.2-5-5 Feedwater System, Nonsafety-Related Components Affecting Related.Systems-Summary of Aging Management Evaluation
Table 3.4.2-5-6 Main steam System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Managem*ent Evaluation 3.4.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the steam and power conversion systems. Programs are described in Appendix B. Further details are provided in the system tables. 3.4.2.1.1 Condensate Makeup and Storage Materials Condensate makeup and storage system components are constructed of the following materials. *
Carbon steel
stainless steel Environments Condensate makeup and storage system components are exposed to the following environments. *
Air -indoor
Treated water Aging Effects Requiring Management The following aging effects associated with the condensate makeup and storage system require management.
Loss of material 3.0 Aging Management Review Results Page 3.4-2
Loss of preload Aging Management Programs Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the condensate makeup and storage system components. * * *
Bolting Integrity External Surfaces 'Monitoring One-Time Inspection . Water Chemistry Control -Primary and Secondary 3.4.2.1.2 Emergency Feedwater Materials Emergency feedwater system components are constructed of the following materi.als.
Carbon steel * *
Gray cast iron High steel Stainless steel Environments Emergency feedwater system components are exposed to the following environments. *
Air -indoor
Air -outdoor
Lube oil
Treated water Aging Effects Requiring Management The following aging effects associated with the emergency feedwater system require management. * *
Cracking J..oss of material Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results
Page 3.4-3 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
The following aging management programs man.age aging for the emergency feedwater system components. * * * *
Bolting Integrity External *Surfaces Monitoring Oil Analysis One-Time Inspection Water Chemistry Control -Primary and Secondary 3.4.2.1.3 Main Feedwater Materials Main feedwater system components are constructed of the following materials.
Carbon steel
High strength .steel
Stainless steel Environments Main feedwater system components are exposed to the following environments.
Air -indoor
Air -outdoor
Steam
Treated water
Treated water> 140°F Aging Effects Requiring Management The following aging effects associated with the main feedwater system require management. * * * *
Cracking Cracking -fatigue Loss of material Loss .of material -FAC Loss of preload 3.0 Aging Management Review Results Page 3.4-4

./ Waterford Steam Electric Station, Unit 3 Ucense Renewal Application Technical Information Aging Management Programs The following aging management programs manage the aging effects for the main feedwater system components. * * * *

Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion One-Time Inspection Water Chemistry Control -Primary and Secondary 3.4.2.1.4 Main Steam Materials Main steam system components are constructed of the following materials.
Carbon steel * *CASS
Glass
Gray cast iron
High strength steel
Stainless steel Environments Main steam system components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Lube oil
Steam
Treated water Aging Effects Requiring Management The following aging effects associated with the main steam system require management. * * *
Cracking Cracking -fatigue Loss of material Loss of material -erosion 3.0 Aging Management Review Results Page
Loss of material -FAC
Loss of preload Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information The following aging management programs manage the aging effects for the main steam system components. .* * * .. * *
Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Oil Analysis . One-Time Inspection Selective Leaching Water Chemistry Control -Primary and Secondary 3.4.2.1.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.4.2-5-x tables. *Materials Nonsafety-related components affecting safety-related systems .are constructed of the following materials.
Carbon steel
Glass
Stainless steel Environments Nonsafety-related components affecting safety-:related systems are exposed to the. following environments.
Air-indoor
Air -outdoor
Condensation
Steam
Treated water
Wastewater 3.0 Aging Management Review Results Page 3.4-6 \

Waterford Steam Electric Station, Unit 3 License Renewal Application TechnJcal Information

Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management.
Cracking
Craqking -fatigue
Loss of material
Loss of material -erosion
Loss of material -*FAG
Loss of preload Aging Programs The following aging management programs manage the effects of aging on nonsafety-related components affecting. safety-related systems. * * * * * *
Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Internal Surfaces in Miscellaneous Piping and Ducting Components One-Time Inspection . Periodic Surveillance and Preventive Maintenance Water Chemistry Control -Primary and Secondary 3.4.2.2 Further Evaluation of Aging Management as Recommended hy NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.4.2.2 of NUREG-1800. The .following sections are numbered in accordance with the discussions in NUREG 1800 and explain the approach to those areas requiring further evaluation. Programs are described in Appendix B. 3.4.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management, the analysis of fatigue is a TLAA as defined in 1 O CFR 54.3. TLAAs are evaluated in accordance with 1 O CFR' 54.21 (c). Evaluation of this TLAA is addressed in Section 4.3. 3.4.2.2.2 Cracking due to Stress Corrosion Cracking CSCC) Cracking due to stress corrosion cracking could occur for stainless steel piping, pipfng components, piping elements and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with 3.0 Aging Management Review Results Page 3.4-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801, cracking of stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.4.2.2.3 Loss of Material Due to Pitting and Crevice Corrosion Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping components, piping elements, and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may* occur. Consistent with NUREG-1801, loss of material for stainless steel components exposed to outdoor including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.4.2.2.4 Qualitv Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section_B.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.4.2.2.5 Ongoing Review of Operating Experience See Appendix B Section B.0.4 for discussion* of the WF3. operating experience review . . . programs. 3.4.2.2.6 Loss of Material due to Recurring Internal Corrosion
A review of 10 years of plant operating experience identified no conditions* of recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in the piping * ,*,components of the steam and *power conversion systems in the scope oflicerise . renewal'. 3.4.2.3 Time-Limited Aging Analysis The only time-limited aging for the steam and power conversion systems components is metal fatigue. This is evaluated in Section 4.3. 3.4.3 Conclusion The steam and power conversion system components that are subject to aging management review have been identified in accordance with the requirements of 1 O CFR 54.21. The aging management programs selected to manage the effects of aging on and power conversion system components are identified in Secti.on 3.4.2.1 and in following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects wilr be managed for the period of extended operation. . . 3.0 Aging Management Review Results Page 3.4-8 Waterford Stearn Electric Station, Unit 3 License Renewal Application Technical Information Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the steam and power conversion system components will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.4-9 Table 3.4.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801 . Table 3.4.1: Steam and Power Conversion Systems Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.4.1-1 Steel piping, piping Cumulative fatigue Fatigue is a time-limited Yes, TLAA Fatigue is a TLAA. components, and piping damage due to aging analysis (TLAA) to be elements exposed to fatigue evaluated for the period of See Section 3.4.2.2.1. steam or treated water extended operation: See the SRP, Section 4.3 "Metal Fatigue," for acceptable methods for meeting the requirements of 10 CFR 54.21(c)(1). 3.4.1-2 Stainless steel piping, Cracking.due to Chapter Xl.M36, "External Yes, Consistent with NUREG-1801. piping components, and stress corrosion Surfaces Monitoring of environmental Cracking of stainless steel piping elements; tanks cracking Mechanical Components" conditions need to components exposed to outdoor air is exposed to air -outdoor be evaluated managed .by the External Surfaces Monitoring Program. See Section 3.4.2.2.2. 3.4.1-3 Stainless steel piping, Loss of material due Chapter Xl.M36, "External Yes, Consistent with NUREG-1801. Loss of piping components, and to pitting and crevice . S.urfaces Monitoring of environmental material for stainless steel piping elements; tanks corrosion Mechanical Components" conditions need to components exposed to outdoor air is exposed to air -outdoor be evaluated managed by the External Surfaces Monitoring Program. See Section 3.4.2.2.3. 3.0 Aging Management Review Results Page 3.4-10 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-4 Steel external surfaces, Loss of material due bolting exposed to air to boric acid with borated water corrosion leakage 3.4.1-5 Steel piping, piping Wall thinning due to components, and piping flow-accelerated elements exposed to corrosion steam, treated water 3.4.1-6 Steel, stainless steel Loss of preload bolting exposed to soil 3.4.1-7 High-strength steel Cracking due to closure bolting exposed cyclic loading, stress to air with steam or corrosion cracking water leakage 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M10, "Boric No Acid Corrosion" Chapter XI.Mt?, "Flow-No Accelerated Corrosion" -Chapter Xl.M18, "Bolting No Integrity" Chapter Xl.M18, "Bolting No Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no external steel surfaces exposed to borated water in the steam and power conversion systems. Consistent with NUREG-1801. Loss of material due to flow accelerated corrosion in steel components exposed to steam or treated water is managed by the Flow-Accelerated Corrosion Program. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Cracking of high strength steel bolting exposed to air with steam or water leakage is managed by the Bolting Integrity Program. Page 3.4-11 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/_ Aging Management Number Component Mechanism Programs 3.4.1-8 Steel; stainless steel Loss of material due Chapter Xl.M18, "Bolting bolting, closure bolting to general (steel Integrity" exposed to air -outdoor only), pitting, and (external}, air-indoor, crevice corrosion uncontrolled (external) 3.4.1-9 Steel closure bolting Loss of material due Chapter Xl.M18, "Bolting exposed to air with to general corrosion Integrity" steam or water leakage .. 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel and stainless steel closure bolting exposed to indoor and outdoor air is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, t_he Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. As stated in Item 3.4.1-8, loss of material of steel bolting exposed to air in the steam and power conversion systems is managed by the Bolting
Integrity Program. However, steam or water leakage is not considered as a separate aspect of the indoor air envfronment. Page 3.4-12
Table 3.4.1 : Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-10 Copper alloy, nickel Loss of preload due alloy, steel; stainless to thermal effects, steel, steel; stainless gasket creep, and
steel bolting, closure self-loosening bolting exposed to any environment, air -outdoor (external), air -indoor, uncontrolled (external) 3.4.1-11 Stainless steel piping, Cracking due to piping components, and stress corrosion piping elements, tanks, cracking heat exchanger components exposed to steam, treated water >60°C (>140°F) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M18, "Bolting No . Integrity" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Tinie Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of preload for steel and stainless steel bolting is managed by the Bolting Integrity Program. Copper alloy and nickel alloy bolting is not included in the scope of license renewal for steam and power conversion systems. Consistent with NUREG-1801. Cracking of stainless steel components exposed to steam or treated water >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. Page 3.4-13 Table 3.4.1 : Steam and* Power Conversion Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.4.1-12 Steel; stainless steel Loss of material due Chapter Xl.M2, "Water tanks exposed to treated to general (steel Chemistry," and Chapter water only), pitting, and Xl.M32, "One-Time crevice corrosion Inspection" " .. 3.4.1-13 Steel piping, piping Loss of material due Chapter Xl.M2, "Water c.omponents, and piping to general, pitting, Ch,emistry," and Chapter elements exposed to and crevice corrosion Xl.M32, "One-Time treated water Inspection" 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel tanks exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no stainless steel tanks exposed to treated water in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Loss of material for steel components exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effeGtiveness of the water chemistry control program to manage loss of material. Page 3.4-14 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-14 Steel piping, piping Loss of material due components, and piping to general, pitting, elements, PWR heat and crevice corrosion exchanger components exposed to steam, treated water 3.4.1-15 Steel heat exchanger Loss of material due components exposed to to general, pitting, treated water crevice, and galvanic corrosion 3.4.1-16 Copper alloy, stainless Loss of material due steel, nickel alloy, to pitting and crevice aluminum piping, piping corrosion components, and piping elements, heat exchanger components and tubes, PWR heat exchanger components exposed to treated water, steam 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" -. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel components exposed to steam or treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no steel condensate system . heat exchanger components exposed to treated water in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Loss of material for stainless steel components exposed to steam or treated water is managed by the Water Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no aluminum, copper alloy or nickel alloy components in the steam and power conversion systems in the scope of license renewal. Page 3.4-15 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component* Mechanism 3.4.1-17 Copper alloy heat Reduction of heat exchanger tubes transfer due to exposed to treated water fouling 3.4.1-18 Copper alloy, stainless Reduction of heat steel heat exchanger transfer due to tubes exposed to treated fouling
water 3.4.1-19 Stainless steel, steel Loss of material due
heat exchanger to general, pitting, components exposed to crevice, galvanic, raw water and microbiologically influenced corrosion; fouling that leads to corrosion 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M2, "Water No Chemistry,'.' and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter -Xl.M32, "One-Time Inspection" .. Chapter Xl.M20, "Open-No Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the steam and power conversion systems in the scope of license renewal. There are no steel or stainless steel heat exchanger components exposed to raw water in the steam and power conversion in the scope of license renewal. Page 3.4-16 ---,/

Table 3.4.1: Steam and Power Conversion Systems Item, Aging Effect/ Number Component Mechanism 3.4.1-20 Copper alloy, stainless Loss of material due steel piping; piping to pitting, crevice, components, and piping and microbiologically elements exposed to influenced corrosion raw water* 3.4.1-21 Stainless steel heat* Loss of material due exchanger components to pitting, crevice, exposed to raw water and microbiologically-influenced corrosion; fouling that leads to corrosion 3.4.1-22 Stainless steel, copper Reduction of heat alloy, steel heat transfer due to exchanger tubes, heat fouling exchanger components exposed to raw water 3.4.1-23 Stainless steel piping, Cracking due to piping components, and stress corrosion piping elements exposed cracking to closed-cycle cooling water >60°C (>140°F) 3.4.1-24 Steel heat exchanger Loss of material due components exposed to to general, pitting, closed-cycle cooling crevice, and galvanic water corrosion 3.0 Aging Management Review Results \ ' Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Further Evaluation . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No There are no copper alloy or stainless steel components exposed to raw water in the steam and power conversion' systems in the scope of license renewal. No There are no stainless steel heat exchanger components exposed to raw water in the steam and power conversion systems in the scope of license renewal. No There are no heat exchanger tubes exposed to raw water with an intended function. of heat transfer in the steam and power conversion systems in the scope of license renewal., No There are no stainless steel components exposed to closed-cycle cooling water >60°C (>140°F) in the steam and power conversion systems in the scope of license renewal. No. There are no steel components exposed to closed-cycle cooling water in .the steam and power conversion systems in the scope of license renewal. Page 3.4-17 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component. Mechanism 3.4.1-25 Steel heat exchanger Loss of material due components exposed to to general, pitting, closed-cycle cooling crevice, and galvanic water corrosion 3.4.1-26 Stainless steel heat Loss of material due exchanger components, to pitting and crevice piping, piping corrosion components, and piping elements exposed to closed-cycle cooling water 3.4.1-27 Copper alloy piping, Loss of material due piping components, and to pitting, crevice, piping elements exposed and galvanic to closed-cycle cooling corrosion water ' 3.4.1-28 Steel, stainless steel, Reduction of heat copper alloy heat transfer due to exchanger components fouling and tubes, heat . exchanger tubes .. exposed to closed-cycle cooling water 3.4.1-29 Steel tanks exposed to Loss of material due air.-outdoor (external) to general, pitting, and crevice corrosion 3.0 Aging Management Review Results Further Aging Management Evaluation i:>rograms Recommended Chapter Xl.M21A, "Closed No. Treated Water Systems" Chapter Xl.M21A, "Closed No Treated Water Systems" Chapter Xl.M21A, "Closed No

Treated Water Systems" Chapter Xl.M21A, "Closed No Treated Water Systems" Chapter Xl.M29, No "Aboveground Metallic , Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no steel components exposed to closed-cyele cooling water in the steam and power conversion systems in the scope of license renewal. There are no stainless steel components exposed to closed-cycle . cooling water in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components exposed to closed-cycle cooling water in the steam and power conversion systems in the scope of license renewal. There are no steel, stainless steel or copper alloy components exposed to closed-cycle cooling water in the steam and power conversion systems in the scope of lice.nse renewal. There are no steel tanks exposed to outdoor air in the steam and power conversion systems in the scope of license renewal. Page 3.4-18 i :

Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-30 Steel, stainless steel, Loss of material due aluminum tanks (within to general (steel the scope of Chapter only), pitting, and Xl.M29, "Aboveground crevice corrosion; Metallic Tanks") cracking due to exposed to soil or stress corrosion concrete, or the cracking (stainless following external steel and aluminum environments air-only) outdoor, air-indoor uncontrolled, moist air, condensation 3.4.1-31 Stainless steel, Loss of material due aluminum tanks (within to pitting, and crevice the scope of Chapter corrosion; cracking Xl.M29, "Aboveground due to stress Metallic Tanks") corrosion cracking exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist air, condensation 3.4.1-32 Gray cast iron piping, Loss of material due piping components, and to selective leaching piping ele_ments exposed to soil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M33, "Selective No Leaching" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *' Discussion At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. Page 3.4-19 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-33 Gray cast iron, copper Loss of material due alloy (>15% Zn or >8% to selective leaching Al) piping, piping components, and piping elements exposed to treated water, raw water, closed-cycle cooling water 3.4.1-34 Steel external surfaces Loss of material due exposed to air -indoor, to general corrosion uncontrolled (external),

air-outdoor (external), condensation (external) 3.4.1-35 Aluminum piping, piping Loss of material due. components, and piping to pitting and crevice elements exposed to air corrosion -outdoor 3.0 Aging Management Review Results (. Further Aging Management Evaluation Programs Recommended Chapter Xl.M33, "Selective No Leaching" Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" ' Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for gray cast iron components exposed to treated water is managed by the Selective Leaching Program. Other material environment combinations represented by this item are not applicable to steam and power conversion system components in the ; scope of license renewal. Consistent with NUREG-1801. Loss of material for steel components exposed to indoor or outdoor air is managed by the External Surfaces Monitoring Program. There are no uninsulated steel components exposed to condensation in the steam and power conversion systems. in the scope of license renewal. There are no aluminum components exposed to outdoor air in the steam and power conversion systems in the scope of license renewal. Page 3.4-20 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-36 Steel piping, piping Loss of material due components, and piping to general, pitting, elements exposed to air and crevice corrosion -outdoor (internal) 3.4.1-37 Steel piping, piping Loss of material .due components, and piping to general, pitting, elements exposed to and crevice corrosion condensation (internal) 3.4.1-38 Steel piping, piping Loss of material due components, and piping to general, pitting, elements exposed to crevice, galvanic, raw water and microbiologically-influenced corrosion; fouling that leads to corrosion 3.4.1-39 Stainless steel piping, Loss of material due piping components, and to pitting and crevice piping elements exposed corrosion to condensation (internal) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for internal surfaces of steel
components exposed to outdoor air (Tables 3.3.2-X) is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. There are no steel components exposed to condensation in the steam and power conversion systems in the scope of license renewal. There are no steel components exposed to raw water in the steam and power conversion systems in the scope of license renewal. There are no stainless steel components exposed to condensation in the steam and power conversion systems in the scope of license renewal. Page 3.4-21 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-40 Steel piping, piping Loss bf material due components, and piping to general, pitting, elements exposed to and crevice corrosion lubricating oil 3.4.1-41 Steel heat exchanger Loss of material due components exposed to to general, pitting, lubricating oil crevice, and I / microbiologically-influenced corrosion 3.4.1-42 Aluminum piping, piping Loss of material due components, and piping to pitting and crevice elements exposed to corrosion lubricating oil 3.4.1-43 Copper alloy piping, Loss of material due piping components, and to pitting and crevice piping elements exposed corrosion to lubricating oil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information
Discµssion Consistent with NUREG-1801. Loss of material for steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. Consistent with NUREG-1801. Loss of material for steel heat exchanger components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. : There are no aluminum components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. Page 3.4-22 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-44 Stainless steel piping, Loss of material due piping components, and to pitting, crevice, piping elements, heat and microbiologically exchanger components influenced corrosion exposed to lubricating oil 3.4.1-45 Aluminum heat* Reduction of heat , exchanger components transfer due to and tubes exposed to fouling lubricating oil 3.4.1-46 Stainless steel, Reduction of heat copper alloy heat transfer due to exchanger tubes fouling exposed to lubricating oil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station; Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for stainless steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. There are no aluminum components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. There are no steel or copper alloy heat exchanger tubes with a heat transfer intended function in the steam and power conversion systems in the scope of license renewal. Page 3.4-23 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-47 Steel (with coating or Loss of material due wrapping), stainless to general, pitting, steel, nickel alloy piping, crevice .* and piping components, and microbiologically piping elements; tanks influencei:f corrosion exposed to soil or concrete 3.4.1-48 Stainless steel, nickel . Loss of material due alloy bolting exposed to to pitting and crevice soil corrosion 3.4.1-49 Stainless steel, nickel Loss of material due alloy piping, piping to pitting and crevice components, and piping corrosion elements exposed to soil or concrete 3.4.1-50 Steel bolting exposed to Loss of material due soil to general, pitting and crevice corrosion 3.4.1-50.5 Underground stainless Loss of material due steel, nickel alloy, steel to general (steel piping, piping only), pitting and components, and piping crevice corrosion elements 3.0 Aging Management Review Results Further Aging Management* Evaluation Programs Recommended Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and *underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no components exposed to soil or concrete in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil or concrete in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil in the.steam and power conversion systems in the scope of license renewal. There are no underground components in the steam and power conversion systems in the scope of license renewal. Page 3.4-24 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-51 .Steel piping, piping None components, and piping elements exposed to concrete 3.4.1-52 Aluminum piping, piping None components, and piping elements exposed to gas, air -indoor, uncontrolled (internal/ external) 3.4.1-53 Copper alloy (S15% Zn None and S8% Al) piping, piping components, and piping elements exposed to air with borated water leakage 3.4.1-54 Copper alloy piping, None piping components, and piping elements exposed to gas, air -indoor, , uncontrolled (external) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended None, provided 1) No, if conditions attributes of the concrete are met. are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG-1557, and 2) plant OE indicates no degradation of the concrete None NA-NoAEM or AMP None NA-NoAEM or AMP None NA-NoAEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no steel components embedded in concrete in the steam and power conversion systems in the scope of license renewal. There are no aluminum components in the steam and power conversion systems in the scope of license renewal. There are no copper alloy (S15% Zn and S8% Al) components in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components in the steam and power conversion systems in the scope of license renewal. Page 3.4-25 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-55 Glass piping elements None exposed to lubricating oil, air -outdoor, condensation (inter:nal/ external), raw water, treated water, air with. borated water leakage, gas, closed-cycle qooling water, air -indoor, uncontrolled (external) 3.4.1-56 Nickel alloy piping, None piping components, and piping elements exposed to air -indoor, uncontrolled (external) 3.4.1-57 Nickel alloy, PVC piping,* None piping components, and piping elements exposed to air with borated water leakage, air -indoor, uncontrolled, condensation (internal) '* 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended None NA-NoAEM or AMP None NA-NoAEM or AMP None NA""'"" No AEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for relevant (indoor air, condensation, lube oil and treated water) environments .. There are no nickel alloy components in the steam and power conversion systems in the scope of license renewal. There are no nickel alloy or PVC components in the steam and power conversion systems in the scope of license renewal. Page 3A-26 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-58 Stainless steel piping, None piping components, and piping elements exposed to air -indoor, uncontrolled (external), concrete, gas, air -indoor, uncontrolled (internal) 3.4.1-59 Steel piping, piping None components, and piping elements exposed to air -indoor controlled (external), gas 3.4.1-60 Any material, piping, Wall thinning due to . piping components, and erosion piping elements exposed to treated water 3.4.1-61 Metallic piping, piping Loss of material due components, and tanks to recurring internal exposed to raw water or corrosion wastewater 3.0 Aging Management Review Results Aging Management Programs None None Chapter Xl.M17, "Flow-Accelerated Corrosion" A plant-specific aging management program is to be evaluated to address recurring internal corrosion . Further Evaluation Recommended NA-NoAEM or AMP NA-NoAEM or AMP No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for relevant (indoor air) environment. There are no steel steam and power conversion system components exposed to controlled indoor air br gas in the scope of license renewal. Consistent with NUREG-1801. Loss of material due to erosion for steel components exposed to treated water is managed by the Flow-Accelerated Corrosion Program. Yes, plant-specific Recurring internal corrosion was not identified in the WF3 steam and power conversion systems in the scope of license renewal. See Section 3.4.2.2.6. Page 3.4-27 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-62 Steel, stainless steel or Loss of material due aluminum tanks (within to general (steel the scope of Chapter only), pitting, and Xl.M29, "Aboveground crevice corrosion Metallic Tanks") exposed to treated water 3.4.1-63 Insulated steel, stainless Loss of material due steel, copper alloy, to general (steel, and aluminum, or copper copper alloy), pitting, . alloy (> 15% Zn) piping, or crevice corrosion, piping components, and and cracking due to tanks exposed to stress corrosion condensation, air-cracking (aluminum, outdoor stainless steel and copper alloy (>15% Zn) only) 3.4.1-64 Jacketed calcium silicate Reduced thermal or fiberglass insulation in insulation resistance an air-indoor due to moisture uncontrolled or air-intrusion outdoor environment 3.0 Aging Management Review Results " '*. Further Aging Management Evaluation Programs Recommended Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" . or Chapter Xl.M29, "Aboveground Metallic Tanks" (for tanks only) Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal i_s the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Consistent with NUREG-1801 for insulated carbon steel and stainless steel components exposed to outdoor air. Loss of material and cracking (stainless steel only) is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy piping components in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduced thermal insulation resistance due to moisture intrusion of jacketed calcium silicate or fiberglass insulation is managed by the External Surfaces Monitoring Program. This item applies to aging management review results presented in Tab!e 3.5.2-4. Page 3.4-28 Table 3.4.1 : Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-65 Jacketed foamglas Reduced thermal (glass dust) insulation in insulation resistance an air-indoor due to moisture uncontrolled or air-intrusion outdoor environment 3.4.1-66 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-cycle delamination, rusting, cooling water, raw water, or physical damage, treated water, treated . and spalling for borated water, or cementitious lubricating oil coatings/linings 3.4.1-67 Metallic piping, piping Loss of material due components, heat to general, pitting, exchangers, tanks with crevice, and internal coatings/linings microbiologically exposed to closed-cycle influenced corrosion; cooling water, raw water, fouling that leads to treated water, treated *corrosion borated water, or lubricating oil 3.0 Aging Management Review Results Further
Aging Management Evaluation Programs Recommended Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"
Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no insulation components with an intended function of thermal insulation in the stecim and power conversion systems. There are no metallic components with internal coating or linings in the steam and power conversion systems in the scope of license renewal. There are no metallic components with internal coating or linings in the steam and power conversion systems in the scope of license renewal. Page 3.4-29 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-68 Gray cast iron piping Loss of material due components with internal to selective leaching coatings/linings exposed to closed-cycle cooling water, raw water, or treated water 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no gray cast iron components with internal coatings or linings in the steam and power conversion systems in the scope of license renewal. Page 3.4-30 Waterford Steam Electric Stat!on, Unit 3 License Renewal Application Technical Information Notes for Table 3.4.2-1 through 3.4.2-5-6 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consi_stent with component, material, environment, aging effect'and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. . , G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component*nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 401. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 402. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program .. 403. The CASS flow elements were evaluated and determined to not be susceptible to thermal aging embrittlement. 404. These components have openings that expose the internal surfaces to outdoor air. Because the internal and external surfaces are exposed to the same environments, aging effects of the internal surfaces can* be inferred from external surface conditions. 405. For the purposes of evaluating loss of coating integrity and loss of material, this environment can be considered equivalent to the NUREG-1801 environment. 3.0 Aging Management Review Results
Page 3.4-31 Table 3.4.2-1 Condensate Makeup and Storage System Summary of Aging Management Evaluation Table 3.4.2-1: Condensate Makeup and Storage System Aging Effect . Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless *steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Flow element Pressure Stainless steel Air-indoor None None boundary (ext) Flow control Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Primary Flow control and Secondary Orifice Pressure Stainless steel Air-indoor None None boundary (ext) Flow control Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Primary Flow control and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Page 3.4-32 Table 3.4.2-1: Condensate Makeup and Storage System Component Intended Type Function Material Environment Piping Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Carbon steel Treated water boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Treated water boundary (int) Pump casing Pressure Stainless steel Air-indoor boundary (ext) Pump casing Pressure Stainless steel Treated water boundary (int) Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated water boundary (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Treated water boundary* (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes V.A.E-29 3.2.1-44 E Vlll.E.SP-73 3.4.1-14 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.E.SP-73 3.4.1-14 A, 401 Page 3.4-33 Table 3.4.2-1: Condensate Makeup and Storage System Aging Effect Component Intended Requiring. Type Function Material Environment Management Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review.Results Aging
Management Program None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3:4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Page 3.4-34 Table 3.4.2-2 Emergency Feedwater System Summary of Aging Management Evaluation Table 3.4.2-2: Emergency Feedwater System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) ' Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of preload Bolting Integrity boundary steel (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Coil Heat transfer Stainless steel Lube oil (ext) Reduction of heat Oil Analysis transfer Coil Pressure Stainless steel Lube oil (ext) Loss of material Oil Analysis boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.S-03 3.4.1-7 B Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B Vlll.G.SP-102 3.4.1-46 A,402 Vlll.G.SP-79 3.4.1-44 A,402 Page 3.4-35 Table 3.4.2-2: Emergency Feedwater System Component Intended Type Function Material Environment Coil Heat transfer Stainless steel Treated water (int) Coil Pressure Stainless steel Treated water boundary (int) Heat exchanger Pressure Gray cast iron Air-indoor (housing) boundary (ext) Heat exchanger Pressure Gray cast iron Lube oil (int) (housing) boundary Insulated piping Pressure Carbon steel Air -outdoor components boundary (ext) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Treated water boundary (int) Flow control Piping Pressure Carbon steel Air-indoor boundary (ext) Piping
Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Treated water boundary (int) 3.0. Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Reduction of heat Water Chemistry transfer Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Oil Analysis Loss of material External Surfaces Monitoring None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring
Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.E.SP-96 3.4.1-18 C, 401 Vlll.G.SP-87 3.4.1-16 C, 401 Vlll.H.S-29 3.4.1-34 A Vlll.G.SP-76 3.4.1-41 A,402 Vlll.G.S-402 3.4.1-63 A Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.G.SP-74 3.4.1-13 A, 401 Page 3.4-36 Table 3.4.2-2: Emergency Feedwater System Aging Effect *component Intended Requiring Type Function Material Environment Management Pump casing Pressure Stainless steel Air-indoor None boundary (ext) Pump casing Pressure Stainless steel Treated water Loss of material boundary (int) Tubing . Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Treated water Loss of material boundary (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A,401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.G.SP-74 3.4.1-13 A, 401 Page 3.4-37 Table 3.4.2-3: Main Feedwater System Component Intended Type Function Material Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel 3.0 Aging Management Review Results Table 3.4.2-3 Main Feedwater System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Environment Management Program Air-indoor Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Air -outdoor Loss of material Bolting Integrity (ext) Air -outdoor Loss of preload Bolting Integrity (ext) Air-indoor Cracking Bolting Integrity (ext) Air-indoor Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Air -outdoor Cracking Bolting Integrity (ext) Air -outdoor Loss of material Bolting Integrity (ext) Air -outdoor Loss of preload Bolting Integrity (ext) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.S-03 3.4.1-7 B Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B ----G Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Page 3.4-38 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Bolting Pressure Stainless steel Air-indoor Loss of preload boundary (ext) Bolting Pressure Stainless steel Air -outdoor Cracking boundary (ext) Bolting Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Bolting Pressure Stainless steel Air -outdoor Loss of preload boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material components boundary (ext) Orifice Pressure Stainless steel Air -outdoor Cracking boundary (ext) Orifice Pressure Stainless steel Air -outdoor Loss of material boundary . (ext) Orifice Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Orifice Pressure Stainless steel Treated water Cracking -fatigue boundary > 140°F (int) Orifice Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Aging Management Program Bolting Integrity Bolting Integrity Bolting Integrity Bolting Integrity External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-83 3.4.1-10 B ----H Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.01 .S-402 3.4.1-63 A Vlll.01 .SP-118 3.4.1-2 A Vlll.01 .SP-127 3.4.1-3 A -Vlll.01.SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.01 .SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Page 3.4-39 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Steam (int) Cracking -fatigue boundary Piping Pressure Carbon steel Steam (int) Loss of material boundary Piping Pressure Carbon steel Treated water Cracking -fatigue boundary (int) Piping Pressure Carbon steel Treated water Loss of material boundary (int) Piping Pressure Carbon steel Treated water Loss of material -boundary (int) FAC Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Tubing Pressure Stainless steel Steam (int) Cracking boundary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring TLAA-metal fatigue Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion None External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Seconda*ry TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.S-41 3.4.1-34 A Vlll.81.S-08 3.4.1-1 c Vlll.A.SP-71 3.4.1-14 C, 401 Vlll.01.S-11 3.4.1-1 A Vlll.01 .SP-74 3.4.1-13 A, 401 Vlll.01 .S-16 3.4.1-5 A Vlll.1.SP-12 3.4.1-58 A Vlll.01 .SP-118 3.4.1-2 A Vlll.01 .SP-127 3.4.1-3 A Vlll.A.SP-98 3.4.1-11 C,401 ----H Page 3.4-40 Table 3.4.2-3: Main Feedwater System Component Intended Type Function Material Environment Tubing Pressure Stainless steel Steam (int) boundary Tubing Pressure Stainless steel Treated water boundary > 140°F (int) Tubing Pressure Stainless steel Treated water boundary > 140°F (int) Tubing Pressure Stainless steel Treated water boundary > (int) Valve body Pressure Carbon steel Air-indoor boundary (ext). Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Treated water boundary (int). Valve body Pressure Carbon steel Treated water boundary (int) Valve body Pressure Carbon steel Treated water bouridary (int) Valve body. Pressure. Stainless steel Air-indoor boundary (ext) 3.0 Aging Managemellt Review Results Aging Effect . Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemi.stry Control -Primary .. and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water ChemistT"Y Control -Primary and Seconda,.Y Loss of material External Surfaces Monitoring Loss of material. External Surfaces Monitoring Cracking -fatigue TLAA* -metal fatigue Loss of material
Water Chemistry *-* Co.ntrol -Primary and Secondary Loss of material -Flow-Accelerated FAG Corrosion* None. None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.A.SP-155 3.4.1-16 C, 401 Vlll.D1 .SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.D1 .SP-87 3.4.1-16 A,401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.D1 .S-11 3.4.1-1 A Vlll.D1 .SP-74 3.4.1-13 A, 401 Vlll.D1.S-16 . 3.4.1-5 A VllLl.SP-12 3.4.1-58 A
Page 3.4-41 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Steam (int) Cracking boundary Valve body Pressure Stainless steel Steam (int) Cracking -boundary Valve body Pressure Stainless steel Steam (int) Loss of material boundary Valve body Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Cracking -fatigue boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.A.SP-98 3.4.1-11 C, 401 ----H Vlll.A.SP-155 3.4.1-16 C, 401 Vlll.01 .SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.01 .SP-87 3.4.1-16 A, 401 Page 3.4-42 Table 3.4.2-4: Main Steam System ' Component Intended Type Function Material Bearing housing Pressure Gray cast iron boundary Bearing housing Pressure
Gray cast fron boundary Bearing housing Pressure Gray cast iron boundary Bearing housing Pressure Gray cast iron boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure
Carbon steel boundary Bolting Pressure High strength " boundary steel Bolting Pressure High strength boundary steel 3.0 Aging Management Review Results Table 3.4.2-4 Main Steam System Summary of Aging Management Evaluation l Aging_ Effect Aging Requiring Management Environment Management Program Air-indoor L:oss of material External Surfaces (ext) Monitoring Lube oil (int) Loss of material Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information I ,, NUREG-1801 Table 1 Item Item Notes Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,.402 -Treated water Loss of material Selective Leaching Vlll.A.SP-27 3.4.1-33 c (int) Treated water Loss of Water Chemistry Vlll.B1 .SP-74 3.4.1-13 A, 401 (int) Control -Primary and Secondary Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B (ext) Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B (ext) Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 3.4.1-8 B (ext) Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3.4.1-10 B (ext) Air-indoor Cracking Bolting Integrity Vlll.H.S-03 3.4.1-7 B (ext) Air -indoor. Loss of material Bolting Integrity Vlll.H.SP-84 B (ext) Page 3.4-43 Table 3.4.2-4: Main Steam System . Component Intended ; Ty.pe . Function Material* Bolting Pressure . High strength* " boundary steel Bolting Pressure High strength *boundary steel Bolting Pressure
High strength
boundary steel Bolting Pressure High strength boundary . steel " Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Bolting "Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure Carbon steel boundary Flow element Pressure ,carbon steel '. boundary Flow control 3.0 Aging Management Review Results { I Environment Air-indoor (ext) Air-outdoor (ext) ; .. outdoor * (ext) Air -outdoor (ext) Air-indoor (ext) Air -outdoor . (ext) Air -outdoor (ext) Air -outdoor (ext) Air -iridoor . Lube oil (int) Steam (int) Aging Effect Aging Requiring Management Management Program Loss of preload Bolting Integrity Cracking . Bolting Integrity Loss of material* Bolting Integrity Loss of preload Bolting Integrity Loss of preload Bolting Integrity Cracking Bolting Integrity Loss of material Bolting Integrity LO$S of preload Bolting Integrity Loss of materi9I External Surfaces Monitoring
Loss of material ()ii Analysis Cracking -fatigue TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-83 ' 3.4.1-10 B ----G Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B --* --H Vlll.H.SP-82 3.4.1-8 B VllLH.SP-151 3.4.1-10 B Vlll.H.S-29 3.4.:1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.B1.S-08 3.4.1-1 A Page 3.4-44 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Flow element Pressure Carbon steel Steam (int) Loss of material boundary Flow control Flow element Pressure Carbon steel Steam (int) Loss of material -boundary FAC Flow control Flow element Pressure CASS Steam (int) Cracking boundary Flow control Flow element Pressure CASS Steam (int) Cracking -fatigue boundary Flow control Flow element Pressure CASS Steam (int) Loss of material boundary Flow control Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material (channel head) boundary (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Lube oil (int) Loss of material (shell) boundary 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.81 .S-15 3.4.1-5 A Vlll.81.SP-98 3.4.1-11 A, 401 403 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 c Vlll.81 .SP-87 3.4.1-16 C, 401 Vlll.H.S-29 3.4.1-34 A Vlll.G.SP-76 3.4.1-41 C,402 Page 3.4-45 Table 3.4.2-4: Main Steam System Component Intended Type Function Material Environment Heat exchanger Pressure Stainless steel Lube oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water (tube sheet) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (ext) (tubes) boundary Heat exchaf!ger Heat transfer Stainless steel Lube oil (ext) (tubes) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Insulated piping Pressure Carbon steel Air -outdoor components boundary (ext) Insulated piping Pressure Stainless steel Air -outdoor components boundary (ext) Insulated piping Pressure Stainless steel Air -outdoor components boundary (ext) Nozzle Pressure Stainless steel Steam (ext) boundary Flow control 3.? Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Oil Analysis Loss of material Water Chemistry Control -Primary and Secondary Loss of material Oil Analysis Reduction of heat Oil Analysis transfer Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer
Control -Primary and Secondary Loss of material External Surfaces Monitoring Cracking External Surfaces Monitoring Loss of material External Surfaces Monitoring Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.G.SP-79 3.4.1-44 C,402 Vlll.81.SP-87 3.4.1-16 C, 401 Vlll.G.SP-79 3.4.1-44 C,402 Vlll.G.SP-102 3.4.1-46 C,402 Vlll.81.SP-87 3.4.1-16 C, 401 Vlll.E.SP-96 3.4.1-18 C, 401 Vlll.81 .S-402 3.4.1-63 A Vlll.81 .S-402 3.4.1-63 A Vlll.81 .S-402 3.4.1-63 A Vlll.81.SP-98 3.4.1-11 A, 401 Page* 3.4-46 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Nozzle Pressure Stainless steel Steam (ext) . Cracking -fatigue boundary Flow control Nozzle Pressure Stainless steel Steam (ext) Loss of material boundary Flow control Nozzle Pressure Stainless steel Steam (int) Cracking boundary Flow control Nozzle Pressure Stainless steel Steam (int) Cracking -fatigue boundary Flow control Nozzle Pressure Stainless steel Steam (int) Loss of material boundary Flow control Orifice Pressure Carbon steel Air-indoor Loss of material boundary (ext) Flow control Orifice Pressure Carbon steel Lube oil (int) Loss of material boundary Flow control Orifice Pressure Stainless steel Air-indoor None boundary (ext) Flow control 3.0 Aging Management Review Results Aging Management Program TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Surfaces Monitoring Oil Analysis None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.81.SP-98 3.4.1-11 A, 401 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.l.SP-12 3.4.1-58 A Page 3.4-47 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Orifice Pressure Stainless steel Steam (int) Cracking boundary Flow control Orifice Pressure Stainless steel Steam (int) Cracking -fatigue boundary Flow control Orifice Pressure Stainless steel Steam (int) Loss of material boundary Flow control Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) . Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Steam (int) Cracking -fatigue boundary Piping Pressure Carbon steel Steam (int) Loss of material boundary Piping Pressure Carbon steel Steam (int) Loss of material -boundary erosion Piping Pressure Carbon steel Steam (int)
Loss of material -boundary FAC 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Oil Analysis TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Flow-Accelerated Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81.SP-98 3.4.1-11 A, 401 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.81 .S-08 3.4.1-1 A Vlll.81 .SP-71 3.4.1-14 A, 401 ----H Vlll.81 .S-15 3.4.1-5 A Page 3.4-48 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Air-indoor None boundary (ext) Piping Pressure Stainless steel Air -outdoor Cracking boundary (ext) Piping Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Piping Pressure Stainless steel Lube oil (int) Loss of material boundary Pump casing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Pump casing Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Carbon steel Air-indoor Loss of material boundary (ext) Sight glass Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Lube oil (int) None boundary Strainer Filtration Stainless steel Steam (ext) Cracking 3.0 Aging Management Review Results Aging Management Program None External Surfaces Monitoring External Surfaces Monitoring Oil Analysis External Surfaces Monitoring Oil Analysis External Surfaces Monitoring Oil Analysis None None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-118 3.4.1-2 A Vlll.81.SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.l.SP-9 3.4.1-55 A Vlll.l.SP-10 3.4.1-55 A Vlll.81 .SP-98 3.4.1-11 A, 401 Page 3.4-49 Table 3.4.2-4: Main Steam System Component Intended Type Function. Material Environment Strainer Filtration Stainless steel Steam (ext) Strainer housing. Pressure Carbon steel Air-indoor boundary ' (ext) Strainer housing Carbon steel Steam (int) boundary Thermowell Pressure Carbon steel Air -outdoor boundary (ext) Thermowell Pressure Carbon steel Steam (int) boundary ThermoWell Pressure Carbon steel Steam (int) boundary Thermowell Pressure
Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel
Steam (int) boundary Thermowell Pressure Stainless steel Steam (int) boundary .' Thermowell Pressure Stainless steel Steam (int) boundary. 3.0. Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal
fatigue Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.81.SP-71 3.4.1-14 A, 401 Vlll.H.S-41 3.4.1-34 A Vlll.81.S-08 3.4.1-1 A Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Page 3.4-50 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Tubing Pressure Carbon steel Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Steam (ext) Cracking boundary Tubing Pressure Stainless steel Steam (ext) Cracking -fatigue boundary Tubing Pressure Stainless steel Steam (ext) Loss of material boundary Tubing Pressure Stainless steel Steam (int) Cracking boundary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring Water Chemistry Control -Primary and Secondary None External Surfaces Monitoring External Surfaces Monitoring Oil Analysis Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.S-29 3.4.1-34 A Vlll.81 .SP-74 3.4.1-13 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-118 3.4.1-2 A Vlll.81 .SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.81.SP-98 3.4.1-11 A, 401 ----H Page 3.4-51 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel Steam (int) Loss of material boundary Turbine casing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Turbine casing Pressure Carbon steel Steam (int) Loss of material boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Steam (int) Cracking -fatigue boundary Valve body Pressure Carbon steel Steam (int) Loss of material boundary Valve body Pressure Carbon steel Steam (int) . Loss of material -boundary FAC Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Stainless steel Air-indoor None boundary (ext) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Oil Analysis TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.81 .S-08 3.4.1-1 A Vlll.81.SP-71 3.4.1-14 A, 401 Vlll.81 .S-15 3.4.1-5 A Vlll.81.SP-74 3.4.1-13 A,401 Vlll.l.SP-12 3.4.1-58 A Page 3.4-52 i Table 3.4.2-4: Main System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body . . Pressure Stainless steel Air -outdoor Cracking boundary (ext) Valve body Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Steam (int) Cracking bqundary Valve body Pressure Stainless steel Steam (int) Cracking -fatigue boundary Valve body Pressure Stainless steel Steam (int) Loss of material boundary ' 3.0 Aging Management Review Results *Aging Management Program External Surfaces Monitoring External Surfaces Monitoring Oil Analysis Water Chemistry Control -Primary and Secondary TLAA -: metal fatigue Water Chemistry Contr9I -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU.REG-1801 Table 1 Item .'Item Notes Vlll.81:SP-118 3.4.1-2 A Vlll.81 .SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Page 3.4-53 Table 3.4.2-5-1 Slowdown System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging _Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material -Environment Management Program Item Item Notes Accumulator Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Accumulator Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H . .SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload . Bolting Integrity VllLH.SP-83 3.4.1-10 B boundary (eXt) Demineralizer Pressure Carbon steel Air-indoor 'Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) _ Monitoring Demineralizer Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Filter housing Pressure
Stainless steel Air*_ indoor None
None _ VllLLSP-12* 3.4.1-58 A boundary (ext) .. ' , -Filter housing Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E . boundary (int) Surveillance and -' .. Preventive ', Maintenance 3.0 Aging Management Review Results Page 3.4-54 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Flow element Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Flow element Pressure Stainle.ss steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-78 3.4.1-14 A,401 (shell) boundary (int) Control -Primary and Secondary Orifice Pressure Stainless steel Air-indoor None None Vlll.1.SP-12 3.4.1-58 A boundary (ext) Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C, 401 boundary Control -Primary and Secondary Pipiflg Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAG Corrosion Piping Pressure Carbon steel Treated water Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1-c boundary (int) fatigue 3.0 Aging Management Review Results Page 3.4-55 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.01 .S-408 3.4.1-60 c boundary (int) erosion Corrosion Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.F.S-16 3.4.1-5 A boundary (int) FAC Corrosion Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping *Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Pump casing Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Pump casing Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.F.S-16 3.4.1-5 A boundary (int) FAC Corrosion Pump casing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) 3.0 Aging Management Review Results Page 3.4-56 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Pump casing Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Sight glass Pressure Glass Air-indoor None None Vlll.l.SP-9 3.4.1-55 A boundary (ext) Sight glass Pressure Glass Treated water None None Vlll.l.SP-35 3.4.1-55 A boundary (int) Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74
3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Tank Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C,401 boundary Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-57 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Blowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Tank Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-75 3.4.1-12 C, 401 boundary (int) Control -Primary and Secondary Tank Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Tubing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary
and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C, 401 boundary Control -Primary and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Valve body Pressure Carbon steel Treated water Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary (int) fatigue 3.0 Aging Management Review Results Page 3.4-58 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect* Aging Component Intended Requiring Management
NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -:-Primary and Secondary Valve body Pressure Carbon steel Treated water Loss of material -Flow-Accelerated VllLA.S-16 3.4.1-5 A boundary (int) FAC Corrosion Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1:..91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Wastewater Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) .Surveillance and Preventive Maintenance Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1:-58 A boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I :ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous '. ' Piping and Ducting Components Valve'body Pressure Stainless steel Wastewater Loss of material Periodic* VI I. ES.AP-278 3.3.1-95 E boundary , (int) ' Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.4-59 Table 3.4.2-5-2 Condensate System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary ,of Aging Management Evaluation Table 3.4.2-5-2:Condensate System, Nonsafety-Related Components Affecting Safety.:Related Systems Aging Effect Aging Component Intended Requiring *Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring .
Piping Pressure Carbon st'3el Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) C.ontr9I -Primary and Secondary Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.D1 .S-408 3.4.1-60 c boundary (int) erosion Corrosion Piping Pressure Carbon steel Waste water
Loss of material Periodic Vll.E5.AP-2.81 3.3.1-91 E boundary (int) . , Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-60 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-2:Condensate System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Sight glass Pressure Glass Air-indoor None None Vlll.l.SP-9 3.4.1-55 A boundary (ext) Sight glass Pressure Glass Treated water None None Vlll.l.SP-35 3.4.1-55 A boundary (int) Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Carbon steel Waste water Loss of material Periodic VII. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.4-61 Table 3.4.2-5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-3:Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) ' Filter housing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Filter housing Pressure Stainless steel Treated water 'Loss .of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Flow element Pressure Stainless steel Air-'-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Flow element Pressure Stainless steel Treated water. Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary .. and Secondary Piping Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Piping Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) . Control -Primary and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext)
Monitoring 3.0 Aging Management Review Results 'Page 3.4-62 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-3:Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-63 Table 3.4.2-5-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Emergency Feedwater System Nonsafety-Related Components Affecting.Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-4:Emergency Feedwater System, Nonsafety-Related Components .Affecting Safety-Related Systems . . Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.01 .SP-74 '3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-64 Table 3.4.2-5-5 Feedwater System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-S:Feedwater System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 3.4.1-8 B boundary (eXt) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3.4.1-10 B boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.01 .S-402 3.4.1-63 A components boundary (ext) Monitoring Orifice Pressure Stainless steel Air -outdoor Cracking External Surfaces Vlll.01.SP-118 3.4.1-2 A boundary (ext) Monitoring Orifice Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.01 .SP-127 3.4.1-3 A boundary (ext) Monitoring Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Air -outdoor Loss qf material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.01 .SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-65 Table 3.4.2-5-6 Main Steam System Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Compo'nent Intended Requiring
Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure
Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel . Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 '3.4.1-8 B boundary (ext) *Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3A.1-10 B boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.B1 .S-402 3.4.1-63 A components bounda,.Y (ext) Monitoring Module Support for Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A criterion (a)(1) (ext) Monitoring equipment Module Support for* Carbon steel Air -outdoor Loss of material External Surfaces ---G,404 criterion (a)(1) (int) Monitoring equipment Piping Pressure Carbon steel , Air -indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-66 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-G:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 A boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Piping Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Piping Pressure Carbon steel Wastewater Loss of niaterial Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Strainer housing Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Strainer housing Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-67 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Trap Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 A boundary fatigue Trap Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81.SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Trap Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Trap Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking External Surfaces Vlll.81.SP-118 3.4.1-2 A boundary (ext) Monitoring Tubing Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.81 .SP-127 3.4.1-3 A boundary (ext) Monitoring *Tubing Pressure Stainless steel Steam (int) Cracking Water Chemistry Vlll.81 .SP-98 3.4.1-11 A,401 boundary Control -Primary and Secondary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue TLAA-metal ----H boundary fatigue 3.0 Aging Management Review Results Page 3.4-68 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-155 3.4.1-16 A, 401 boundary Control -Primary and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring / Valve body
Pressure Carbon steel-Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking-fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 A boundary fatigue . Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81.SP-71 3.4.1-14 A, 401 boundary Control -Primary. and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81.S-15 3.4.1-5 A boundary FAG Corrosion Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3, 1-91 c boundary (int) Miscellaneous Piping and Ducting .. Components Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Valve body Pressure Stainless steel Air -outdoor cracking External Surfaces Vlll.81 .SP-118 3A.1-2 . A boundary (ext) Monitoring Valve body Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.81 .SP-127 3.4.1-3 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-69 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect .Aging Component Intended Requiring Management NUREG-1801 Table 1 Ty.pe Function Material Environment
Management Program Item lterri Notes Valve body Pressure Stainless steel Steam .(int) Cracking Water Chemistry Vlll.81 .SP-98 3.4.1-11 A,401 boundary Control Primary and Secondary Valve body Pressure Stainless steel Steam (int) Cracking.-fatigue Tl.AA-metal ----H boundary fatigue Valve body Pressure Stainless steel Steam (int) Loss of material Water. Chemistry Vlll.81.SP-155 . 3.4.1-16 A, 401 boundary Control -Primary: and Secondary 3.0 Aging Management Review Results Page 3.4-70 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.5 CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS .3.5.1 Introduction This section provides the results of the aging management review for structural components and commodities that are subject to aging management review. The following structures and commodity groups are addressed in this section (descriptions are available in the referenced sections).
Reactor Building (Section 2.4.1)
Nuclear Plant Island Structure (Section 2.4.2)
Turbine Building and Other strudures (Section 2.4.3)
Bulk Commodities (Section 2.4.4) Table 3.5.1, Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and Ill of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for structures and component supports. Hyperlinks are provided to the program evaluations in Appendix B. 3.5.2 Results The following tables summarize the results of aging management reviews and the NUREG-1801 comparison for structures and component supports.
Table 3.5.2-1 Reactor Building -Summary of Aging Management Evaluation
Table 3.5.2-2 Nuclear Plant Island Structure -Summary of Aging Management Evaluation
Table 3.5.2-3 Turbine Building and Other Structures -Summary of Aging Management Evaluation
Table 3.5.2-4 Bulk Commodities -Summary of Aging Management Evaluation 3.5.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging requiring management, and aging management programs for structures and component supports subject to aging management review. Programs are described in Appendix B. Further details are provided in the structure and commodities tables. 3.0 Aging Management Review Results Page 3.5-1 Waterford Steam Electric Station, Unit 3 " """ License Renewal Application Technical Information 3.5.2.1.1 Reactor Building Materials Reactor building components are constructed of the following materials. .. Carbon steel
Coatings
Concrete
Elastomer
Stainless steel Environments Reactor building components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Air with borated water leakage
Exposed to fluid environment Aging Effects Requiring Management The following aging effects associated with the reactor building require management. * * * * * * *
Cracking Increase in porosity and permeability . Loss of bond Loss of coating integrity Loss of leak tightness Loss of material Loss of preload Loss of sealing Aging Management Programs The following aging m*anagement programs manage the effects of aging on the reactor building.
Boric Acid Corrosion
Containment lnservice Inspection -IWE
Containment Leak Rate
Fire Protection
lnservice Inspection -IWF 3.0 Aging Management Review Results Page 3.5-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Protective Coating Monitoring and Maintenance
Structures Monitoring 3.5.2.1.2 Nuclear Plant Island Structure
Materials Nuclear plant island structure components are constructed of the following materials.
Carbon steel
Concrete
Concrete block
Galvanized steel
Stainless steel Environments Nuclear plant island structure components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Exposed to fluid environment
Soil Aging Effects Requiring Management The following aging effects associated with the nuclear plant island structure require management. * * * * *
Cracking Cracks and distortion Increase in porosity and permeability Loss of bond Loss of material Loss of strength Aging Management Programs The following aging management programs manage the 'effects Cif aging on the nuclear plant island structure components.
Fire Protection 3.0 Aging Management Review Results Page 3.5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Masonry Wall
Structures Monitoring
Water Chemistry Control -Primary and Secondary 3.5.2.1.3 Turbine Building and Other Structures Materials Turbine building and other structures are constructed of the following materials.
Carbon steel
Concrete
Concrete block
Galvanized steel
Treated wood Environments Turbine building and other structures components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Exposed to fluid environment
Soil Aging Effects Requiring Management The following aging effects associated with the turbine building and other structures require management. * * * * * *
Change in material properties Cracking Cracks and distortion Increase in porosity and permeability Loss of bond Loss of material Loss of strength 3.p Aging Management Review Results Page 3.5-4 Aging Management Programs Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the effects of aging on the turbine building and other structures components.
Fire Protection
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Masonry Wall
Structures Monitoring 3.5.2.1.4 Bulk Commodities Materials Bulk commodity components are constructed of the following materials.
Aluminum
Calcium silicate
Carbon steel
Cerablanket
Concrete
Elastomers
Fibergl_ass
Galvanized steel
HEMYC
Kaowool blanket
Silicone elastomer
Siltemp fibersil cloth
Stainless steel
Thermo-lag Environments . Bulk commodity com-porients are exposed to _the following environments.
Air -indoor uncontrolled
Air -outdoor
Air with borated water leakage
Exposed to fluid environment 3.0 Aging Management Review Results Page 3.5-5 Waterford Ster;im Electric Station, Unit 3 ---, License Renewal Application Technical Information Aging Effects Requiring The following. aging effects associated with the bulk commodities require management.
Change in material properties
Cracking
Cracking/delamination, separation
Increase in porosity and permeability
Increased hardness, shrinkage, loss of strength
Loss of bond * * * * *
Loss of material Loss of mechanical function Loss of preload Loss of sealing Reduction in concrete anchor capacity Reduction or loss of isolation function Management Programs The following aging management programs manage the effects of aging on the bulk commodity components.
Boric Acid Corrosion *
External Surface$ Monitoring
Fire Protection
Fire Water System
lnservice Inspection -IWF
Structures Monitoring
Water Chemistry Control -Primary and Secondary 3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.5.2.2 of NUREG-1800. The following sections are numbered in accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further eyaluation. Programs are described in Appendix B. 3.0 Aging Management Review Results Page 3.5-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.5.2.2.1 PWR and BWR Containments 3.5.2.2.1.1 Cracking and Distortion due to Increased Stress Levels from Settlement; Reduction of Foundation Strength, and* Cracking due to Differential Settlement and Erosion of Porous Concrete Subfoundations 3.5.2.2.1.2 The WF3 containment is a low-leakage free-standing steel containment vessel (SCV) structure consisting of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate* encased in concrete which is completely enclosed by
the reinforced shield building. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the related shield building and the common rigid reinforced concrete foundation structure for the NPIS, as discussed in Section 3.5.2.2.2.1 Item 3. WF3 does not rely on a dewatering system for control of settlement. The WF3
SCV structure's base foundation is integral with the base foundation of the shield building and _is founded on a common rigid reinforced concrete foundation strudure for the NPIS and does not use a porous concrete subfoundation. Additionally, Information Notice 97-11 did not identify WF3 as a plant susceptible* to erosion of porous concrete subfoundations. Therefore, reduction of foundation strength, cracking due to differential settlement, and erosion of porous concrete subfoundations is not applica_ble to the WF3 SCV structure's base foundation concrete. Reduction of Strength and Modulus due to Elevated Temperature The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC . is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is Inaccessible, it is exempted from examinatio.n in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield 3.0 Aging Management Review Results .* Page 3.5-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information building and the Common rigid reinforced concrete foundation structure for the
NPIS and further discussed in Section 3.5.2.2.2.2. Puring normal operation, areas within containment are maintajned below an average temperature of 120°F per technical.specifications, which is below the
threshold temperature of greater than 150°F general area. Process piping carrying hot fluid (pipe temperature greater than 200°F) are routed through penetrations in the SCV that are not.encased in concrete. Therefore, the local
area temperatures greater than 200°F local is not applicable for the WF3 containment. Therefore, change in material properties due to elevated temperature is not ar:i aging effect requiring management for containment concrete. As a result, reduction of strength and modulus of concrete due to elevated . . temperatures are*not aging effects requiring management.for the WF3 standing SCV structure. The aging effect "change in material properties" is equivalent to the NUREG-1801 aging effect "reduction of strength and modulus of elasticity. * . 3.5.2.2.1.3 . Loss of Material due to General, Pitting and Cr,evice Corrosion 1. Loss of m_aterial due to general, pitting, and crevice corrosion could occur in steel of inaccessible areas for all types of PWR and BWR containments. The WF3 containment is a low-leakage free-!:)tanding SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom. liner plate encased in concrete. The WF3_ SCV.structure's base foundation is integral with the base foundation of the shield building. A moisture barrier is provided where the steel liner becomes embedded in the concrete floor. The SCV is inspected in accordance with the requirements of Subsection IWE of the ASME Code Section XI. These inspections include a visual exal'Jlination of the accessible interior and the exterior surfaces of the class MC components, parts and appurtenances .of the steel containment vessei as well as visual inspection of the moisture barrier at the concrete-to-steel interface. Loss of material due to general, pitting and crevice corrosion of the steel elements of accessible areas is managed by the Containment lnseivice Inspection-* 1wE Program, the Containment Leak Rate Program (10 CFR Part 50,* Appendix J Program) and the Boric.Acid Corrosion Program. Interior concrete is monitored for .cracks under the Structures Monitoring Program. Moisture b.arriers are intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining metal containment shell or liner at. concrete-to-metal interfaces and at metal-to-metal interfaces which are not seal welded. The WF3 moisture barrier is the elastomeric sealant between the concrete to metal containment interface. 3.0 Aging Management Review Results Page 3.5-8 3.5.2.2.1.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A review of plant operating experience was conducted from the Containment lnservice Inspection -IWE Program walkdowns. One condition report identified during the performance of visual inspections of the containment during VT-3 inspection of the containment inner moisture barrier (located between the containment vessel and the concrete floor on the ledge on elevation -4), six *damaged locations of the moisture barrier. Damage was primarily age related degradation and mechanical damage to the moisture barrier. The containment moisture barrier is intended to provide long term corrosion protection of the containment vessel. It is not required by Technical Specifications or the Technical Requirements Manual and is not required to support the function of any safety-related structures, systems or components. None of the affected areas showed signs of wetting and no corrosion of the containment vessel was noted. Corrective action removed the damaged portions of moisture barrier and replaced them with new sealant barrier material. The continued monitoring of the WF3 steel containment vessel for loss of material due to general, pitting, and crevice corrosion through the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Program provides -reasonable assurance that loss of material in inaccessible areas of Containme.nt is insignificant and will be detected prior to a loss of an intended function. 2. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus shell of Mark I containments. WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete. The WF3 PWR containment does not have a steel torus shell. Therefore, this item does not apply to WF3. 3. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus ring girders and downcomers of Mark I containments, downcomers of Mark II containments, and interior surface of suppression chamber shell of Mark Ill containments. WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete'. The WF3 PWR containment does not have*a torus ring girder or downcomers. Therefore this item does not apply to WF3. Loss of Prestress due to Relaxation, Shrinkage, Creep, and Elevated Temperature WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation is integral with the base foundation of 3.0 Aging Management Review Results Page 3.5*9 3.5.2.2.1.5 3.5.2.2.1.6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information the shield building with no prestressed tendons associated with its design. Therefore, loss of prestress due to relaxation, shrinkage, creep, and elevated temperature does not apply. Cumulative Fatigue Damage TLAAs are evaluated in accordance with 10 CFR 54.21(c) as documented in Section 4. By design, the WF3 steel containment vessel is not subject to a TLAA. Fatigue TLAAs for bellows are evaluated as documented in Section 4.6. Other containment mechanical penetration bellows that are located outside the containment building have been screened out of scope because they do not perform a pressure boundc;iry intended function and no fatigue analysis exists. The NUREG-1801 BWR components, e.g., torus, suppression pool shell, vent line bellows, and unbraced downcom.ers, related to Mark I and II containments are not
applicable to the WF3 PWR contai,nment. Cracking due to Stress Corrosion Cracking Stress corrosion cracking (SCC) is not an applicable aging mechanism for the steel containment vessel (SCV) carbon steel penetration sleeves, stainless steel penetration bellows, and. dissimilar metal welds. The WF3 SCV and associated . penetration sleeves are carbon steel. High temperature piping systems \. penetrating the containment are carbon steel. Stress corrosion cracking is only applicable to stainless steel and is predicted only under certain conditions. There are dissimilar metal welds associated with stainless steel bellows welded to carbon steel penetration sleeves, sec of dissimilar metal welds of stainless steel at the penetration sleeves is not considered credible because stainless steel sec requires a concentration of chloride or sulfate contaminants, which are not normally present in significant quantities, as well as high stress and temperatures greaterthan 140°F. Leakage of water in the containment, which might contact the penetration sleeves, is event driven. The containment pressure welds between stainless steel piping and penetration sleeves, with normal operating temperatures above 140°F, are not highly stressed. In addition, the Technical Specification limits the average air temperature inside the primary containment durin*g normal plant operation to 120°F. Therefore cracking of these components due to stress corrosion cracking is not applicable. However, cracking due to SCC of dissimilar metal welds for carbon steel and stainless steel will be managed by the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Pr?gram. NUREG-1801 recommends further evaluation of inspection methods to detect cracking due to stress corrosion cracking (SCC) since visual VT-3 examinations may be unable to detect this aging effect. Potentially susceptible components at WF3 are penetration sleeves and bellows. 3.0 Aging Management Review Results Page 3.5-10 3.5.2.2.1.7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Three factors are necessary to initiate and propagate cracking due to sec, including trahsgranular stress corrosion cracking (TGSCC). These factors are susceptible or sensitized material (resulting from manufacturing or installation process), a high tensile stress (residual or applied), arid corrosive environment (high temperatures, moist or wetted environment or an environment contaminated with chlorides, fluorides, or sulfates). Elimination or reduction of any of these factors will decrease the likelih'ood of SCC. TGSCC of WF3 stainless steel bellows is not considered credible because the corrosive environment (concentration of chloride or sulfate contaminants and temperatures greater than 140°F) does not exist for the bellows .. Therefore, SCC of WF3 stainless steel bellows due to TGSCC is not expected. A review of plant experience did not identify cracking of this component, and containment pressure boundary functions have not been identified as a concern.
sec is not an applitable aging mechanism for the SCV carbon steel penetration sleeves, and dissimilar metal welds. The WF3 SCV and associated penetration sleeves are carbon steel. High temperature piping systems penetrating the containment are generally carbon steel. Stress corrosion cracking is only applicable to*stainless steel and is predicted only under certain conditions as discussed sec of dissimilar metal welds of stainless steel at the penetration sleeves is not considered credible because stainless steel sec
requires a concentration of chloride or sulfate contaminants, which are not present in significant quantities, as well as high stress and greater than 14q°F: Leakage of water in the containment, which mighf contact the penetration sleeves, is not the normal operating environment .. The containment pressure boundary welds between stainless steel piping and penetration sleeves, with normal operating temperatures. above 14.0°F, are not highly stressed. In addition,
the Technical Specification limits the average air temperature inside the primary containment during normal plant operation t.o 120°F. A review of plant operating experience did not identify cracking of these components, and containment pressure boundary functions have not been identified as ;f cqncern. Therefore, cracking of these components due to stress corrosion cracking is not expected. Nevertheless, the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Program manage cracking due to SCC of stainless steel bellows and dissimilar metal welds for carbon steel and steel. Loss of Material (Scaling, Spalling) and Cracking due to Freeze-Thaw
The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure!. for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC 3.0 Aging Management Review Results Page 3.5-11 3.5.2.2.1.8 3.5.2.2.1.9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). The base foundation of the SCV is below grade and protected from the outer environment by the shield building's base foundation and is not subject to freeze-thaw action. The WF3 concrete structures subject to the air-outdoor environment are not exposed to temperatures of 32°F or less of sufficient durations that would cause freeze-thaw aging effects to occur. WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90.
As a result, loss of material and cracking due to freeze-thaw are not aging effects requiring management for WF3 SCV structure's base foundation concrete. Therefore, loss of material and. cracking due to freeze-thaw are not aging effects requiring management for the WF3 SCV concrete base foundation. Cracking due to Expansion from Reaction with Aggregate The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome, and an eliipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). Based on ongoing industry operating experience, the Structures Monitoring Program manages cracking due to expansion from reaction with aggregate in accessible concrete areas for the WF3 SCV concrete base foundation. However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield building and the common rigid reinforced concrete foundation structure for the NPIS and further discussed in Section 3.5.2.2.2.1 Item 2. Increase in Porosity and Permeability due to Leaching of Calcium Hydroxide and Carbonation The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's *containment that is classified as Class CC 3.0 Aging Management Review Results Page 3.5-12 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield building and the common rigid reinforced concrete foundation structure for the NPIS and further discussed in Section 3.5.2.2:2.1 Item 4. Therefore, increase in porosity and permeability due to leaching of calcium hydroxide and carbonation are not aging effects requiring*management for the WF3 SCV concrete base foundation. 3.5.2.2.2 Safety-Related and Other Structures and Component Supports . 3.5.2.2.2.1 Structure groups and component support groups as used in the following discussions are defined in NUREG-1800, Section 3.5.1. Aging Management of Inaccessible Areas 1. Loss of Material (Spalling, Scaling) and Cracking Due to Freeze-Thaw in Below Grade Inaccessible Concrete Areas of Groups 1-3, 5 and 7-9 Structures The Groups *1-3, 5 and 7-9 Structures at WF3 subject to the air-outdoor environment are not exposed to temperatures of 32°F or less of sufficient durations that would cause freeze-thaw aging effects to occur. WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90. Also, air entraining admixture was used in concrete and total air content including that due to use of chemical admixtures generally ranged between 3.5 and .6.5 percent by volume. A review of the WF3 corrective action program was conducted to
determine whether inspection activities.identified evidence of cracking or spalling due to freeze-thaw degradation. This review found no documented conditions of freeze-thaw degradation in exterior concrete structures exposed to an air-outdoor environment. As a result, loss of material and cracking due to freeze-thaw in below-grade inaccessible concrete areas of Groups 1-3, 5 and 7-9 structures are not aging effects requiring management for WF3. Therefore, loss of material and cracking due to freeze-thaw are not aging effects requiring management for the grade inaccessible concrete areas of WF3 Groups 1-3, 5 and 7-9 structures. 2. Cracking Due to Expansion and Reaction with Aggregates in Below Grade Inaccessible Concrete Areas for Groups 1-5 and 7-9 Structures . The Groups 1-5 C!nd 7-9 Structures at WF3 are designed in accordance with ACI 318-63 and/or ACI 318-71 and constructed in accordance with the recommendations in ACI 318-63 and ACI 318-71 using ingredients/materials 3.0 Aging Management Review Results Page 3.5-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information conforming to ACI and ASTM standards. The concrete mix-uses Portland cement conforming to ASTM C150, Type II. Concrete aggregates conform to the requirements of ASTM C33. Materials for concrete used in WF3 concrete structures and components were specifically investigated, tested, and examined in accordance with pertinent ASTM standards. Nevertheless, based on ongoing industry operating experience, cracking due to expansion and reaction with aggregates in below-grade inaccessible concrete areas for WF3 Groups 1-5 and 7-9 structures will be managed. WF3 has not identified operating experience for this aging effect; however, WF3 has *conservatively elected to manage this aging effect by the Structures Monitoring Program. 3. Cracking and Distortion due to Increased Stress Levels from Settlement for Below Grade lnaccessfble Concrete Areas of structures for all Groups and Reduction in Foundation Strength, and Cracking, due to Differential Settlement and Erosion of Porous Concrete Subfoundation in .Below Grade Inaccessible Concrete Areas for Groups 1-3, 5-9 Structures The Groups 1-3 and 5-9 Structures at WF3 are founded on a compacted backfill. For .the inaccessible concrete areas of Groups 1-3 and 5-9 Structures at WF3 the safety-related nuclear plant island structures' (NPIS) foundations (basemat) are. integral and are founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The aging effect cracking and distortion due to increased stress levels from settlement is applicable and will be managed by the Structures Monitoring Program. For the WF3 turbine building and other nonsafety-related concrete structures which are founded on compacted structural backfill or soil, the aging effect cracking and distortion due to increased stress levels from settlement is applicable and will be managed by the structures Monitoring Program. Therefore, cracking and distortion due to increased stress levels from settlement is an applicable aging effect for WF3 Groups 1-3 and 5-9 below-grade inaccessible concrete structures, and for the turbine building and other nonsafety-related concrete structures and will be managed by the structures Monitoring Program. The Groups 1-3 and 5-9 Structures at WF3 do not rely on a dewatering system for control of settlement. The WF3 Groups 1-3 and 5-9 concrete* structures do not use porous concrete subfoundations. Therefore, reduction of foundation strength, and cracking due to differential settlement and erosion of porous concrete subfoundations is not an applicable aging effect for WF3 Groups 1-3 and 5-9 below-grade inaccessible concrete structures. Additionally, the WF3 site configuration does not have Group 6 Structures. Therefore, reduction of foundation strength, and cracking due to differential settlement and erosion of
porous concrete subfoundations in below-grade inaccessible concrete areas is not applicable for WF3 Group 6 structures. 3.0 Aging Management Review Results Page 3.5-14 3.5.2.2.2.2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4. Increase in Porosity and Permeability, and Loss of Strength Due to Leaching of Calcium Hydroxide and Carbonation of Below-grade Inaccessible Concrete Areas of Groups 1-:--5 and 7-9 Structures The Groups 1-5 and 7-9 Structures at WF3 are designed in accordance with ACI 318-63 and/or ACI 318-71 and.constructed in accordance with the
recommendations in ACI 318-63 and ACI 318-71 using ingredients/materials conforming to ACI and ASTM standards. The concrete mix uses Portland cement conforming to ASTM C150, Type IL Concrete aggregates conform to the requirements of ASTM C33. Materials for concrete used in WF3 concrete structures and components were specifically investigated, tested, and examined in accordance with pertinent ASTM standards. The type and size of aggregate, slump, cement and additives have been established to produce durable concrete in accordance with ACI. Cracking is controlled through proper arrangement and distribution of reinforcing steel. Concrete structures and concrete components are constructed of a dense, well-cured concrete with an *amount of cement suitable for strength development and achievement of a water-to-cement ratio that is characteristic of concrete having low permeability. This is consistent with the recommendations and guidance provided by ACI 201.2R-77. The below-grade inaccessible concrete areas of Groups 1-5 and 7-9 concrete structures at WF3 are exposed to groundwater which is considered equivalent to a flowing water environment. Therefore, increase in porosity and permeability, and loss of strength due to leaching* of calcium hydroxide and carbonation in below-grade inaccessible concrete areas is an applicable aging effect for the inaccessible concrete of WF3 Groups 1-5 and 7-9 concrete structures. The Structures Monitoring Program manages increase in porosity and permeability, and loss of strength due to leaching of calcium hydroxide and carbonation in below-grade inaccessible concrete areas of WF3 Groups 1-5 and 7-9 concrete structures. Reduction of Strength and Modulus of Concrete Structures due to Elevated Temperature ACI 349 specifies concrete temperature limits for normal operations or any .other long-term period. During normal operation, areas within the Group 1-5 structures at WF3 are maintained oelow a bulk average temperature of 150°F by plant cooling systems. Process piping carrying hot fluid (pipe temperature greater than 200°F) routed through penetrations in the concrete walls by design do not result in .. temperatures exceeding 200°F locally or result in "hot spot" .on the concrete surface. The penetration configuration includes guard pipes and insulation of the process piping to minimize heat transfer from the process pipe to the exterior environment surrounding the process piping. Therefore, change in material properties due to elevated temperature is not an aging effect requiring management for WF3 Group 1-5 Structures. The aging effect "change in material 3.0 Aging Manageme.nt Review Results Page 3.5-15 3.5.2.2.2.3 3.5.2.2.2.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information properties" is equivalent to the NUREG-1801 aging effect "reduction of strength and modulus." Aging Management of Inaccessible Areas .for Group 6 structures 1. Loss of Material (Spalling, Scaling) and Cracking Due to Freeze-thaw in grade Inaccessible Concrete Areas of Group 6 Structures. The WF3 site configuration does not have Group 6 Structures. Therefore, loss of material (spallihg, scaling) and cracking due to freeze-thaw in below-grade inaccessible c9ncrete ar,eas is not applicable. 2. Cracking Due to Expansion and Reaction with Aggregates in Below-Grade Inaccessible Concrete Areas of Group 6 Structures The WF3 site configuration does not have Group 6 Structures. Therefore, cracking due to expansion and reaction in below-grade inaccessible concrete areas is not applicable. 3. Increase in Porosity and Permeability and Loss of strength due to Leachin*g of Calcium Hydroxide and Carbonation in *inaccessible Are_as of Concrete Elements of Group 6 structures * * '"'* The WF3 site configuration does not have Group 9 Structures. Therefore, increase in porosity and permeability due to leaching of calcium hydroxide and carbonation in below-grade inaccessible concrete areas is not a*pplicable. Cracking due to Stress Corrosion Cracking and Loss of Material due to Pittjng and Crevice Corrosion NUREG-1800 Section 3.5.2.2.2.4 applies to stainless steel liners for concrete or steel tanks. No tanks with stainless steel liners are included in the structural scope of license renewal. However, the corresponding NUREG-1801 items can be compared to the stainless steel liners of other components, such as reactor cavity and containment sump. These liners can be exposed to a fluid environment and may be subject to loss of material. The stainless steel liners, exposed to fluid environment, are not in an environment conducive to stress corrosion cracking (SCC). Consistent with GALL Report Chapter IX, Sections D arid F, the factors necessary to initiate and propagate sec are combined actions of stress (both applied and residual tensile stresses), and .harsh environment (significant presence of halogens, specifically chlorides), attemperature above 140°F (60°C). Although SCC has been observed in stagnant, oxygenated borated water systems at lower temperatures than* this 140°F threshold, all of these instances have identified a significant presence of contaminants (halogens, specifically chlorides) in the failed components. SCC of stainless steel liners is not credible 3.0 Aging Management Review Results Page 3.5-16 3.5.2.2.2.5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information because they are not exposed to a harsh environment (significant presence of contaminants [halogens, specifically chlorides]), and the normal operating temperature of the fluid environment to which these stainless steel liners are exposed is less than the SCC threshold temperature of, 140°F. Therefore, cracking due to sec is not an aging effect requiring management for the stainless steel liners exposed to fluid environment. The Structures Monitoring Program manages loss of material by periodic inspections. Cumulative Fatigue Damage due to Fatigue TLAAs are evaluated in accordance with 10 CFR 54.21(c) as documented in Section 4 of this application. During the process of identifying TLAAs in the WF3 current licensing basis, no fatigue analyses were identified for component support members, welds, and support anchorage to building structure for Groups 81 .1, 81 .2; and 81 .3. 3.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix 8 Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.5.2.2.4 Ongoing Review of Operating Experience See Appendix 8 Section 8.0.4 for discussion of WF.3 operating experience review of aging management programs. 3.5.2.3 Time-Limited Aging Analysis Potential TLAAs identified for structural components and commodities include fatigue analyses for crane rails and structural girders, expansion bellows and refueling bellows assembly, and steel containment vessel penetrations. TLAAs are discussed in Section 4. 3.5.3 Conclusion The structural components and commodities subject to aging management review have been identified in accordance with the criteria of 1 O CFR 54.21. The aging management programs selected to manage-the.effects of aging on structural components and commodities are identified in Section 3.5.2.1 and the following tables. A description of the aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the structural components and commodities will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.5-17 Table 3.5.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and Ill of NUREG-1801
Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion .. : .. :::. :, 3.5.1-1 Concrete: dome; Cracking and ISi (IWL) or Structures Yes, if a de-Waterford 3 (WF3)'does not rely on a de-wall; basemat; ring distortion due to Monitoring Program watering system watering system to control settlement. The girders; buttresses, increased stress is relied upon to WF3 containment system does not utilize a Concrete elements, levels from If a de-watering system is control settlement concrete containment. The WF3 primary all settlement containment is a free-standing steel relied upon for control of containment vessel (SCV) which is settlement, then the completely enclosed by the reinforced licensee is to ensure proper functioning of the concrete shield building. TheWF3SCV structure's base foundation is integral with de-watering system the base foundation of the shield building through the period of and is founded on a common rigid extended operation. " reinforced concrete foundation structure for the nuclear plant island structure (NPIS). Since the WF3 primary containment concrete foundation (basemat) is inaccessible, it is exempted from inspection " and ISl-IWL program does not apply. For further evaluation, see Section 3.5.2.2.1.1. 3.0 Aging Management Review Results Page 3.5-18 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-2 Concrete; . Reduction of Structures foundation; foundation strength Program. subfoundation and cracking due to differential If a de-watering system is settlement and erosion of porous relied upon for control of concrete erosion, then the licensee subfoundation is to ensure proper functioning of the de-watering system through the period of extended operation. 3.5.1-3 Concrete: dome; Reduction of A plant-specific aging wall; basemat; ring strength and management program is to girders; buttresses, modulus due to be evaluated. Concrete: elevated containment; wall; temperature (>150°F basemat, Concrete: general; >200°F basemat, concrete local) fill-in annulus 3.5.1-4 BWRonly 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if a de-watering system is relied upon to control settlement Yes, if temperature limits are exceeded Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 does not have a porous concrete subfoundation or rely on a de-watering system to control settlement. The WF3 SCV structure's base foundation is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS. Therefore, the listed aging effects are not applicable to WF3 primary containment foundation. For further evaluation, see Section 3.5.2.2.1.1. The concrete foundation (basemat) of the WF3 primary containment is not exposed to general and local temperatures that exceed the thresholds. Therefore the listed aging effects are not applicable to the concrete foundation (basemat) of the WF3 primary containment. For further evaluation, see Section 3.5.2.2.1.2. Page 3.5-19 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-5 Steel elements Loss of material due ISi (IWE) and 10 CFR Part (inaccessible areas): to general, pitting 50; Appendix J liner; liner anchors; and crevice integral attachments, corrosion Steel elements * (inaccessible areas): suppression chamber; drywall; drywall head; embedded shell; region shielded by diaphragm floor (as applicable) 3.5.1-6 BWRonly 3.5.1-7 BWRonly 3.5.1-8 Prestressing system; Loss of prestress Yes, TLAA tendons due to relaxation, shrinkage, creep; elevated temperature .. 3.0 Aging Management Review Results Further Evaluation -Recommended Yes, if corrosion is indicated from the IWE examinations. Yes, TLAA Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG 1801. The Containment lnservice Inspection -IWE and the Containment Leak Rate Programs manage the loss of material of the inaccessible interior and the exterior surfaces of the Class MC components of the SCV. For further evaluation, see Section 3.5.2.2.1.3 Item 1. WF3 is a PWR with SCV consisting of a cylindrical. wall, a hemispherical dome, and an ellipsoidal bottom encased in reinforced concrete supported on a common rigid reinforced concrete foundation structure for the NPIS. There are no prestressed tendons associated with WF3 primary containment design. For further evaluation, see Section 3.5.2.2.1.4. Page 3.5-20 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-9 Penetration sleeves; Cumulative fatigue Yes, TLAA penetration bellows, damage due to Steel elements: fatigue (only if torus; vent line; vent [current licensing header; vent line basis] CLB fatigue bellows; analysis exists) downcomers, Suppression pool shell; unbraced downcomers, Steel elements: vent header; down comers 3.5.1-10 Penetration sleeves, Cracking due to ISi (IWE) and 10 CFR Part penetration bellows stress corrosion 50, Appendix J cracking .. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, TLAA Yes, detection of aging effects is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for containment penetrations that experience cyclic loading. Fatigue analysis for penetration bellows is a TLAA and evaluated in Section 4. For further evaluation, see Section 3.5.2.2.1.5. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. For further evaluation see Section 3.5.2.2 .. 1.6 .. Page 3.5-21 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-11 Concrete Loss of material Further evaluation is (inaccessible areas): (spalling,. scaling) needed for plants that are dome; wall; and cracking due to located in moderate to basemat; ring freeze-thaw severe weathering girders; buttresses,
conditions (weathering Concrete index >100 day-inch/yr) (inaccessible areas): (NUREG-1557). basemat, Concrete (inaccessible areas): dome; wall; basemat 3.0 Aging Management Review Results Further Evaluation Recommended Yes, for plants located in moderate to severe weathering conditions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and protected from the external environments by the shield building's base foundation. Also WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90. Therefore, the concrete.elements of the SCV foundation (basemat) are not subject to the listed aging effects due to freeze-thaw. For further evaluation, see Section 3.5.2.2.1.7. Page 3.5-22 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-12 Concrete Cracking due to. Further evaluation is (inaccessible areas): expansion from required to determine if a dome; wall; reaction with plant-specific aging basemat; ring aggregates management program is girders; buttresses, needed. Concrete (inaccessible areas): basemat, Concrete (inaccessible areas): containment; wall; basemat, Concrete (inaccessible areas): basemat, concrete fill-in annulus 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if concrete is not constructed as stated function Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. The listed aging. effect for concrete elements of the SCV foundation {basemat) is addressed by Item 3.5.1-43. For further evaluation, see Section 3.5.2.2.1.8. Page 3.5-23 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Further Item Aging Effect/ Aging Management Evaluation Number Component .Mechanism Programs Recommended 3.5.1-13 Concrete Increase in porosity Further evaluation is Yes, if leaching is (inaccessible areas): and permeability; required to determine if a observed in basemat, Concrete loss of strength due plant-specific aging accessible areas (inaccessible areas): to leaching of management program is that impact dome; wall; basemat calcium hydroxide needed. intended function and carbonation 3.5.1-14 Concrete Increase in porosity Further evaluation is Yes, if leaching is (inaccessible areas): and permeability; required to determine if a observed in dome; wall; loss of strength due plant-specific aging accessible areas basemat; ring to leaching of management program is that impact girders; buttresses, calcium hydroxide needed. intended function Concrete and carbonation (inaccessible areas): containment; wall; bas em at 3.0 Aging Management Review Results ., Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and protected from the external environments by the shield building's base foundation. Since the WF3 primary containment concrete foundation {basemat) is inaccessible, it is exempted from inspection and the ISl.-IWL program does not apply. Accordingly, WF3 does not have an ISl-IWL program. The listed aging effects are addressed by Item 3.5.1-47. For further evaluation, see Section 3.5.2.2.1.9. NUREG-1801 items referencing this Item Number are associated with PWR concrete. containment and WF3 is a steel containment structure. For further evaluation, see Section 3.5.2.2.1.9. Page 3.5-24 Table 3.5. f: Containment, and ComponentSupports, NUREG-1801 Item Aging Effect/ Number Component Mechanism 3.5.1-15 Concrete Increase in porosity (accessible areas): and permeability;
base mat. loss of strength due to leaching of calcium hydroxide and carbonation 3.5.1-16 Concrete Increase in porosity* (accessible areas): and permeability; basemat, Concrete: cracking; loss of co.ntainment; wall; material (spalling, baseimat scaling) due to aggressive chemical attack .. 3.5.1-17 BWRonly. . ' ( 3.0 Aging Management Review Results Aging Management Programs ISi (IWL). ISi (IWL) or Structures Monitoring Program Further Evaluation . Recommended No -No Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Discussion WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the base liner plate of the SCV .and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Accordingly, WF3 does not have an ISl-IWL program. Therefore the listed aging effects are not applicable to WF3. WF3 has ;;in SCV and does not have accessible concrete (basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the scv which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the ba$e liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore the listed aging effects are not applicable to WF3. Page 3.5-25 Table 3.5.1: Containm.ent, Structures and Comp<;>nent Supports,' NUREG-1801
Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended 3.5.1-18 Concrete Loss of material ISi (IWL) No (accessible areas): (spailing, scaling) dome; wall; and cracking due to . basemat; ring freeze-thaw girders; buttresses, Concrete (accessible areas): basemat '. 3.5.1-19 Concrete Cracking due to ISl(IWq No (accessible areas): expansion from dome; wall; reaction with basemat; ring .aggregates *girders; buttresses, Concrete (accessible areas): basemat, Concrete (accessible areas) containment; wall; basemat, concrete fill-in annulus 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has an SCV and does not have an accessible concrete {basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the SCV which is integral with the shield
building concrete foundation (basemat).
The SCV concrete basemat is below the base liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the program does not apply. Therefore, the listed aging effects are not applicable to WF3. WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete .is the circular concrete bas'e foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the base liner plate the SCV and, therefore,
is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore, the listed aging effect is not applicable to WF3. Page 3.5-26 )

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-20 Concrete .Increase in porosity ISi (IWL) (accessible areas): and permeability; dome; wall; loss of strength due basemat; ring to leaching of girders; buttresses, calcium hydroxide Concrete and carbonation (accessible areas): containment; wall; basemat 3.5.1-21 Concrete Cracking; loss of ISi (IWL) (accessible areas): bond; and loss of dome; wall; material (spalling, basemat; ring scaling) due to girders; buttresses; corrosion of reinforcing steel, embedded steel Concrete (accessible areas): basemat; reinforcing steel, Concrete (accessible areas): dome; wall; basemat; reinforcing steel 3.5.1-22 BWRonly. 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-1801 items referencing this Item Number are associated with PWR concrete containment structures and WF3 has *a steel containment structure. Therefore this aging effect is not applicable to WF3. WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete is the circular concrete base* foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basema\ is below the base liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore, the listed aging effect is not applicab_le to WF3. Page 3.5-27 Table 3.5.1 :. Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism *Programs 3.5.1-23 Concrete Cracking; loss of ISi (IWL} or Structures (inaccessible areas): bond; and loss of Monitoring Program basemat; reinforcing material (spalling, steel, Concrete scaling) due to (inaccessible areas): corrosion of dome; wall; embedded steel basemat; reinforcing steel 3.5.1-24 Concrete Increase in porosity ISi (IWL) or Structures (inaccessible areas): and permeability, Monitoring Program dome; wall; cracking, loss of basemat; ring material (spalling, girders; buttresses, , scaling) due to Concrete aggressive chemical (inaccessible areas): attack basemat, (accessible areas): .. dome; wall; basemat -3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. Sirice the WF3 primary containment concrete foundation (basemat) is ,inaccessible, it is exempted from and the ISl-IWL program does not apply. The listed aging effects are addressed by Item 3.5.1-66. NUREG-1801 items referencing this Item are not associated with the WF3 steel containment structure. WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. Since the WF3 primary containment concrete foundation (basemat) is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. The listed aging effects are addressed by Item 3.5.1-67. Page 3.5-28 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-25 Concrete Cracking; loss of ISi (IWL) or Structures (inaccessible areas): bond; and loss of Monitoring Program dome; wall; material (spalling, basemat; ring scaling) due to girders; buttresses; corrosion of reinforcing steel embedded steel 3.5.1-26 Moisture barriers Loss of sealing due ISi (IWE) (caulking, flashing, to wear, damage, and other sealants) erosion, tear, surface cracks, or other defects 3.5.1-27 Penetration sleeves; Cracking due to ISi (IWE) and 10 CFR Part penetration bellows, cyclic loading (CLB 50, Appendix J Steel elements: fatigue analysis torus; vent line; vent does not exist) header; vent line bellows; downcomers, Suppression pool shell 3.5.1-28 Personnel airlock, Loss of material due ISi (IWE) and 10 CFR Part equipment hatch, to general, pitting, 50, Appendix J CRD hatch and crevice corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-1801 items referencing this item are associated with PWR concrete containment structures and WF3 has an SCV. Therefore, this aging effect is not applicable to WF3. Consistent with NUREG 1801. The Containment lnservice Inspection -IWE manages the listed aging effect. WF3 is a PWR with a free-standing SCV that does not have a CLB fatigue analysis. However, WF3 does have a CLB fatigue analysis for penetration bellows, which is evaluated in Section 4.6. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Page 3.5-29 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-29. Personnel airlock, Loss of leak ISi (IWE) and 10 CFR Part equipment hatch, tightness due to 50, Appendix J CRD hatch: locks, mechanical wear of hinges, and closure locks, hinges .and mechanisms closure mechanisms 3.5.1-30 Pressure-retaining Loss of preload due ISi (IWE) and 10 CFR Part bolting to self-loosening 50, Appendix J 3.5.1-31 Pressure-retaining Loss of material due ISi (IWE) bolting, Steel to general, pitting, elements: and crevice " downcomer pipes corros.ion .. 3:5.1-32

Prestressing system: Loss of material due ISi (IWL) tendons; anchorage to corrosion
components 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The : Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Consistent with NUREG-1801. The . Containment lnservice lnspeCtion IWE Program manages the pressure-retaining bolting aging effect. The steel elements: downcomer pipes are associated with BWR Mark I and Mark II containments. WF3 is a PWR. NUREG.:.1801 items referencing this item are associated with concrete containments and applicable to PWR and BWR prestressed concrete containments. WF3 is a PWR with free-standing SCV. There are no prestressed tendons associated with WF3 primary containment design. Therefore this aging effect is not applicable to WF3. Page 3.5-30 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-33 Seals and gaskets Loss of sealing due 10 CFR Part 50, Appendix to wear, damage, J erosion, tear, surface cracks, or other defects 3.5.1-34 Service Level I Loss of coating Protective Coating coatings integrity due to Monitoring and blistering, cracking, Maintenance Program flaking, peeling, delamination, rusting, or physical damage 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Containment Leak Rate Program manages the listed aging effect. Consistent with NU REG 1801. The Protective Coating Monitoring and Maintenance Program manages the listed aging effect. Page 3.5-31 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-35 Steel elements Loss of material due ISi (IWE) and 10 CFR Part (accessible areas): to general, pitting, 50, Appendix J liner; liner anchors; and crevice integral attachments, corrosion Penetration sleeves, Steel elements (accessible areas): drywell shell; drywell head; drywell shell in sand pocket regions; Steel elements (accessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable}, Steel elements (accessible areas): drywell shell; drywell head 3.5.1-36 BWRonly. 3.5.1-37 BWRonly. 3.5.1-38 BWRonly. 3.5.1-39 BWRonly. 3.0 Aging Management Review Results Further Evaluation Recommended No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. WF3 is a PWR with free-standing SCV and it does not contain a drywell and components associated with sand pocket region. Page 3.5-32 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-40 BWR only. 3.5.1-41 BWRonly. Safety-Relc1tedi:J.nd0ther StnJctures; and CorTiponerit Supports '< 3.5.1-42 Groups 1-3, 5, 7-9: Loss of material Further evaluation i$ Concrete. (spalling, scaling) required for plants that are (inaccessible areas): and cracking due to located in moderate to foundation freeze-thaw severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557) 3.5.1-43 All Groups except Cracking due to Further evaluation is Group 6: Concrete expansion from required to determine if a (inaccessible areas): reaction with plant-specific aging all aggregates management program is needed. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, for plants located in moderate to severe weathering conditions Yes, if concrete is not constructed as stated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion <' ,, WF3 is located in a region where weathering conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the concrete elements are not subject to listed aging effects due to freeze-thaw. For further discussion, see Section 3.5.2.2.2.1 Item 1. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. For further evaluation, see Section 3.5.2.2.2.1 Item 2. Page 3.5-33 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-44 All Groups: Cracking and Structures Monitoring concrete: all distortion due to Program increased stress levels from If a system is settlement relied upon for control of settlement, then the licensee .is to ensure proper functioning of the de-watering system through the periqd of extended operation. BWRonly. 3.5.1-46 Groups 1-3, 5-9: Reduction in . Structures Monitoring . concrete: foundation strength, Program ,, foundation; cracking due to subfoundation differential .If.a system is settlement, erosion relied upon for control of of porous concrete settlemen( then the subfoundation licensee is to ensure . ' proper functioning of the .. de-watering system through.the period .of extended operation. 3.0 Aging Management Review Results Further .Evaluation Recommended
Yes, if a de-watering system is relied upon to control settlement *. Yes, if a de-watering system is relied upon to control settlement Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. WF3 does not rely on a de-watering system to control settlement. For further evaluation, see Section 3.5.2.2.2.1 *Item 3. WF3 does not rely on a de-watering system to control settlement and it does not have porous concrete subfoundation. Therefore, the listed aging effects are not .applicable to WF3 fourdation; subfoundation. For fu.rther evaluation, see Section 3.5.2.2.2. 1 Item 3.
Page 3.5-34 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-47 Groups 1-5, 7-9: Increase in porosity Further evaluation is concrete and permeability; required to determine if a . (inaccessible areas): loss of strength due plant-specific aging exterior above and to leaching of management program is below-grade; calcium hydroxide needed. foundation and carbonation 3.5.1-48 Group 1-5: concrete: Reduction of A plant-specific aging all strength and management program is to modulus due to be evaluated. elevated temperature (>150°F general; >200°F local) 3.5.1-49 Groups 6 -concrete Loss of material Further evaluation is (inaccessible areas): (spalling, scaling) required for plants that are exterior above-and and cracking due to located in moderate to below-grade; freeze-thaw severe weathering foundation; interior conditions (weathering slab index :>.100 day-Inch/yr)* (NUREG-1557) 3.5.1-50 Groups 6: concrete Cracking due to Further evaluation is (inaccessible areas): expansion from required to determine if a all reaction with plant-specific aging aggregates management program is needed. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if leaching is observed in accessible areas that impact intended function Yes, if temperature limits are exceeded Yes, for plants located in moderate to severe weathering conditions Yes, if concrete is not constructed as stated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. For further evaluation, see Section 3.5.2.2.2.1 Item 4. WF3 concrete in areas for this grouping are not exposed to general and local temperatures that exceed the listed thresholds. Therefore the listed aging effect is not applicable to WF3 structures in this group. For further evaluation, see* Section 3.5.2.2.2.2. WF3 has not identified components for this grouping. Therefore this line item was not used. For fur.ther evaluation, see Section 3.5.2.2.2.3 Item 1. WF3 has not identified components for this grouping. Therefore this line item was not used. For further evaluation, see Section 3.5.2.2.2.3 Item 2. Page 3.5-35 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-51 Groups 6: concrete Increase in porosity Further evaluation is (inaccessible areas): and permeability; required to determine if a exterior above-and loss of strength due plant-specific aging below-grade; to leaching of management program is foundation; interior calcium hydroxide needed. slab and carbonation 3.5.1-52 Groups 7, a*-steel Cracking due to A aging components: tank stress corrosion management program is to liner cracking; Loss of be evaluated. material due to
pitting and crevice corrosion 3.5.1-53 Support members; Cumulative fatigue Yes, TLAA welds; bolted damage due to connections; support fatigue (Only if CLB anchorage to fatigue analysis building structure exists) 3.5.1-54 All groups except 6: Cracking due to Structures Monitoring concrete (accessible expansion from Program areas): all reaction with aggregates. 3.0 Aging Management Review Results *Further Evaluation Recommended Yes, if leaching is observed in accessible areas that impact intended function Yes, plant-specific ' Yes, TLAA No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has not identified components for this grouping. Therefore this'line item was not used. For further evaluation, see Section 3.5.2.2.2.3 ltem3. Consistent with NUREG-11;!01. The Structures Monitoring Program _manages loss of material for this group of components. Cracking due to stress corrosion is not an aging effect requiring management for an environment of water-standing< 140°F (< 60°C). There are no stainless steel tank liners with intended functions exposed to an environment of water-standing> 140°F (> 60°C). For further evaluation, see Section . 3.5.2.2.2.4. No CLB fatigue analysis exists for component supports members, welds, and support anchorage to building structure. For further evaluation, see Section 3.5.2.2.2.5. Consistent with NUREG-1801. The Structures Program manages the listed aging effect. Page 3.5-36
Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-55 Building concrete at Reduction in Structures Monitoring locations of concrete .anchor Program expansion and capacity due to local grouted anchors; concrete grout pads for degradation/ service support base plates induced cracking or other concrete aging mechanisms 3.5.1-56 Concrete: exterior Loss of material due Regulatory Guide 1.127, above-and below-to abrasion; "Inspection of Water-grade; foundation; cavitation Control Structures interior slab Associated with Nuclear Power Plants" or the FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-57 Constant and Loss of mechanical ISi (IWF) variable load spring function due to hangers; guides; corrosion, distortion, stops dirt, overload, fatigue due to vibratory and cyclic thermal loads 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. . This NUREG 1801 line item is specific to Group 6 components. WF3 has not identified components for this grouping. Therefore this line item was not used. Consistent with NUREG-1801. The ISl-IWF Program m*anages the listed aging effect. Page 3.5-37 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Programs 3.5.1-58 Earthen water-Loss of material; Regulatory Guide 1.127, control structures: lpss of form due to "Inspection of Water-dams; erosion, settlement, Control Structures embankments; sedimentation, frost Associated with Nuclear reservoirs; channels; action, waves, Power Plants" or the canals and ponds .currents, surlace FERG/US Army Corp of runoff, seepage Engineers dam inspections and maintenance . programs . 3.5.1-59 Group 6: concrete Cracking; loss of Regulatory Guide 1.127, (accessible areas): bond; and loss of "Inspection ofWater-all material (spalling, Control Structures scaling) due to . Associated with Nuclear corrosion of Power Plants" or the embedded steel FERC/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-60 Group 6: concrete Loss of material Regulatory Guide 1.127, (accessible areas): (spalling, scaling) "Inspection of Water-exterior above-and and cracking due to : Control Structures below-grade; freeze-thaw Associated with Nuclear foundation Power Plants" or the FERC/US. Army Corp of Engineers dam inspections and maintenance programs. 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion This NUREG 1801 line item is specific to Group 6 components. WF3 has not identified components for this grouping. Therefore, this line item was not used. WF3 has not identified components for this grouping. Therefore, this line item was nof used. WF3 has not identified components for this . grouping. Therefore, this line item was not used. Page 3.5-38 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-61 Group 6: concrete Increase in porosity Regulatory Guide 1.127, (accessible areas): and permeability; "Inspection of Water-exterior above-and loss of strength due Control Structures below-grade; to leaching of Associated with Nuclear foundation; interior calcium hydroxide Power Plants" or the slab and carbonation FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-62 Group 6: Wooden. Loss of material; Regulatory Guide 1.127, Piles; sheeting change in material Inspection of Water-properties due to Control Structures weathering, Associated with Nuclear chemical Power Plants" or the degradation, and FERG/US Army Corp of insect infestation Engineers dam inspections repeated wetting and maintenance and drying, fungal programs. decay 3.5.1-63 Groups 1-3, 5, 7-9: Increase in porosity Structures Monitoring concrete (accessible and permeability; Program areas): exterior loss of strength due above and below-to leaching *of grade; foundation calcium hydroxide , and carbonation 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has not identified components for this grouping. Therefore, this line item was not used. WF3 Structures Monitoring Program manages the listed aging effects for the wooden piles associated with fire pump house. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Page 3.5-39 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-64 1-3, 5, 7-9: Loss of material Structures Monitoring concrete (accessible (spalling, scaling) Program areas): exterior and cracking due to above and below-freeze-thaw grade; foundation 3.5.1-65 Groups 1-3, 5, 7-9: Cracking; loss of Structures Monitoring concrete bond; and loss of Program (inaccessible areas): material (spalling, below-grade scaling) due to exterior; foundation, corrosion of Groups 1-3, 5, 7-9: embedded steel concrete (accessible areas): below-grade exterior; foundation, Grqups 6: concrete (inaccessible areas): all 3.5.1-66 Grpups 1-5, 7, 9: Cracking; loss of Structures Monitoring concrete (accessible bond; and loss of Program areas): interior and material. (spalling, above-grade exterior scaling) due to corrosion of embedded steel 3.0 Aging Management Review Results Further Evaluation . Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is located in a region where weathering .conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the concrete elements associated with these groups are not subjectto the listed aging effects due to freeze-thaw. The Structures Monitoring Program manages the listed aging effects for listed groups except for Group 6. WF3 has not identified components for Group 6; therefore, it is not applicable. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effeqts. Page 3.5-40 *, *,

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-67 Groups 1-5, 7, 9: Increase in porosity Structures Monitoring Concrete: interior; and permeability; Program above-grade cracking; loss of exterior, Groups 1-3, material (spalling, 5, 7-9 -concrete scaling) due to (inaccessible areas): aggressive chemical below-grade attack exterior; foundation, Group 6: concrete (inaccessible areas): all 3.5.1-68 High-strength due to ISi (IWF) structural bolting stress corrosion cracking 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion The Structures Monitoring Program manages the listed aging effects for listed groups except for Group 6. WF3 has not identified components for Group 6, therefore it is not applicable. NUREG-1801 item referencing this item defines the bolting susceptible to sec as: high strength (actual measured yield strength greater than or equal to 150 kilo-pound per square inch [ksi] or greater than or equal to 1,034 MPa) for structural bolts greater than 1 inch (25 mm) in diameter. Per EPRI 1015078, a periodically wetted environment and the use of thread lubricant containing molybdenum disulfide must be present to initiate sec in high yield-strength bolting. Since Molybdenum disulfide thread lubricants are not used at WF3, for structural bolting applications, sec of high strength structural bolting is not an aging effect requiring management at WF3. Page 3.5-41 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-69 High-strength Cracking due to Structures Monitoring structural bolting stress corrosion Program Note: .ASTM A cracking 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone bSCC. SCC potential need not be evaluated for these bolts. 3.5.1-70 Masonry walls: all Cracking due to Masonry Wall Program restraint shrinkage,* creep, and .aggressive environment 3.5.1-71 Masonry walls: all Loss of material Masonry Wall Program (spalling, scaling) and cracking due to freeze-thaw 3.5.1-72 Seals; gasket; Loss of sealing due Structures \ moisture barriers to deterioration of Program (caulking, flashing, seals, gaskets, and and other sealants)

moisture barriers (caulking, flashing, and other sealants) 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion As defined in this line item, ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. V\(F3 procedures do not identify the use of high strength bolts ASTM A325 and A-490 for structural applications. Therefore, the listed aging effect is not applicable for WF3 high strength bolting. Consistent with NUREG-1801. lhe Masonry Wall Program manages the listed aging effect. WF3 is located in a region where weathering conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the masonry walls associated with this line item are not subject to the listed aging effects due to freeze-thaw. Consistent with NUREG-1801, the Structures Monitoring Program manages the listed aging effect. Page 3.5-42

( Table 3.5.1: Containment, Structures and Component Supp9rts, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-73 Service Level I Loss of coating Protective Coating coatings integrity due to Monitoring and blistering, cracking, Maintenance flaking, peeling, delamination, rusting, or physical damage 3.5.1-74 Sliding support Loss of mechanical Structures Monitoring bearings; sliding function due to Program support surfaces

corrosion, distortion, dirt, debris, overload, wear 3.5.1-75 Sliding surfaces Loss of mechanical ISi (IWF) function due to corrosion, distortion, dirt, debris, overload, wear 3.5.1-76 Sliding surfaces: Loss of mechanical Structures Monitoring radial beam seats in function due: to Program BWRdrywell corrosion, distortion, dirt, overload, wear 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Protective Coating Monitoring and Maintenance Program manages the listed aging effect. NUREG-1801 item referencing this item is associated with Lubrite plates. Lubrite plates are not subject to aging management because the listed aging mechanisms are event driven and typically can be avoided though proper design. NUREG-1801 item referencing this item is associated with Lubrite plates. Lubrite plates are not subject to aging management because the listed aging mechanisms are event driven and typically can be avoided though proper design. Loss of material which could cause loss of mechanical function is addressed under Item 3.5.1-77 related to component support members. This NUREG-1801 item is for BWR having a drywall with radial beam seats. WF3 is a PWR with a free-standing SCV containment and does not have radial beam seats. Page 3.5-43 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management' Number Component Mechanism Programs 3.5.1-77 Steel components: Loss of material due Structures Monitoring all structural steel to corrosion Program 3.5.1-78 Steel components: Cracking due to Water Chemistry and fuel pool liner *stress corrosion Monitoring of the spent fuel cracking; Loss of . pool water level in material due to accordance with technical pitting *and crevice specifications and leakage corrosion from the leak chase channels. '\ 3.5.1-79 Steel components: Loss of material due Structures Monitoring piles to corrosion Program 3.5.1-80 Structural bolting Loss of material due Structures Monitoring to general, pitting Program and crevice corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No, unless leakages have been detected through the SFP liner that cannot be accounted for from the leak chase channels No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Consistent with NUREG-1801. The Water Chemistry Control -Primary and Secondary Program and monitoring of the spent fuel pool water level manage loss of material on the spent fuel pool liner. Monitoring spent fuel pool water level in accordance with technical specifications and monitoring leakage from the leak chase channels will also continue during the period of extended operation. Cracking due to stress corrosion is not an aging effect requiring management for an environment oftreatec;I water< 140°F (< 60°C). There are no stainless steel spent fuel components with intended functions exposed to an environment of treated water > 140°F (> Not applicable. WF3 has no steel piles subject to the listed aging effect; therefore this .line *item was not used. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Page 3.5-44 \

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number

Component Mechanism Programs 3.5.1-81 Structural bolting Loss of material due ISi (IWF) to general, pitting and crevice corrosion 3.5.1-82 Structural bolting Loss of material due Structures Monitoring to general, pitting Program and crevice corrosion 3.5.1-83 Structural bolting Loss of material due Chapter Xl.S7, "Regulatory to general, pitting Guide 1.127, Inspection of and crevice Water-Control Structures corrosion Associated with Nuclear Power Plants" or the FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-84 Structural bolting Loss of material due Water Chemistry and ISi to pitting and crevice (IWF) corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. Consistent with NU REG-1801. The Structures Monitoring Program manages the listed aging effect. The Structures Monitoring Program manages the listed aging effect. NUREG-1801 item referencing this Item Number is associated with ASME Class MC stainless steel structural bolting in a fluid environment. WF3 does not have this componenU material/environment combination. Therefore this line item was not used. Page 3.5-45 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs. 3.5.1-85 Structural bolting Loss of material due Water Chemistry for BWR to pitting and crevice water, and ISi (IWF) corrosion 3.5.1-86 Structural bolting Loss of material due ISl(IWF) to pitting and crevice corrosion 3.5.1-87 Structural bolting Los.s of preload due ISi (IWF) to self-loosening 3.5.1-88 bolting Loss of preload due Structures Monitoring to self-loosening Program 3.5.1-89 Support members; Loss of material due Boric Acid Corrosion welds; bolted to boric acid Program connections; support corrosion . anchorage to building structure 3.5.1-90 Support members; Loss of material due Water Chemistry for BWR welds; bolted to general (steel water, and ISi. (IWF) connections; support only), pitting, and anchorage to crevice corrosion building structure 3.0 Aging Management Review Results ( Further Evaluation Recommended* No No No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-'1801 item referencing this Item Number is associated with ASME Class 1, 2 and 3 stainless steel structural bolting in a fluid environment for a BWR. WF3 is a PWR and does not have this component/ material/environment combination. Therefore this line item was not used. Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the list.ed aging effect. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Consistent with NUREG-1801. The Boric Acid Corrosion Program manages the listed aging effect. WF3 is a PWR with SCV. The WF3 Water Chemistry Control -Primary and Secondary and lnservice Inspection -IWF Programs manage the listed aging effect. Page 3.5-46 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-91 Support members; Loss of material due ISi (IWF) welds; bolted to general and connections; support pitting corrosion anchorage to building structure 3.5.1-92 Support members; Loss of material due Structures Monitoring welds; bolted to general and Program* connections; support pitting corrosion anchorage to building structure 3.5.1-93 Support members; Loss of material due Structures Monitoring welds; bolted to pitting and crevice Program connections; support corrosion anchorage to building structure 3.5.1-94 Vibration isolation Reduction or loss of ISi (IWF) elements* isolation function due to radiation hardening, temperature, humidity, sustained vibratory loading 3.0 Aging Management Review Results Further Evaluation Recommended No No No No* Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. The Structures Monitoring and Fire Water System Programs manage the listed aging effect. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. No ISl-IWF vibration isolation elements have been identified at WF3, however for non-IWF in-scope commodities, the Structures Monitoring Program manages the listed aging effects. Page 3.5-47 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-95 Aluminum, None None galvanized steel and stainless steel support members; welds; bolted connections; support anchorage to building structure exposed to Air*-indoor, uncontrolled 3.0 Aging Management.Review Results Further Evaluation Recommended NA-NoAEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG 1801. Page 3.5-48 Notes for Table 3.5.2-1 through 3.5.2-4 Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line -item. AMP is c_onsistent with NUREG-1801.AMP description. 8. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consist.ent with NUREG-1801 AMP description. D. Component is different, but consistent with material,* environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 501. Steel piles driven into undisturbed soils are unaffected by corrosion. Where steel piles are driven into disturbed soils, operating experience has shown that only minor to moderate corrosion has occurred that would not significantly affect the performance of the component intended function during the license renewal term. The steel piles* are steel casings used as forms for the concrete inside the steel piles. The concrete inside the steel casing is not susceptible to degradation that could impair the ability of the concrete to perform its intended function. Therefore, no aging management is required. 3.0 Aging Management Review Results Page 3.5-49 Table 3.5.2-1: Reactor Building Intended Component Type Function Crane: rails and HS, SNS structural girders Crane -structural HS, SNS girders Penetration bellows EN, HS, PB, SSR Penetration bellows EN, HS, PB, SSR Penetration sleeves EN, HS, PB, MB, SNS, SRE, SSR Penetration sleeves EN, HS, PB, SNS, SRE, SSR Plant stack SSR Steel components: MB,PB, SSR annulus access lock 3.0 Aging Management Review Results Table 3.5.2-1 Reactor Building Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NU REG-Table 1 Material Environment Management Programs 1801 Item Item Notes Carbon steel Air-indoor Loss of material Inspection of Vll.B.A-07 3.5.1-52 A uncontrolled
OVHLL Carbon steel Air-indoor Cracking TLAA-metal Vll.B.A-06 3.3.1-1 A uncontrolled fatigue Stainless Air-indoor Cracking TLAA-metal ll.A3.C-13 3.5.1-9 A steel uncontrolled fatigue Stainless Air-indoor Cracking Cll-IWE 11.A3.CP-38 3.5.1-10 A steel uncontrolled Containment Leak Rate Carbon steel Air-indoor Loss of material Cll-IWE ll.A3.CP-36 3.5.1-35 A uncontrolled Containment Leak Rate Stainless Air-indoor None None lll.B2.TP-8 3.5.1-95 c steel uncontrolled Carbon steel Air-indoor Loss of material Structures 111.A 1.TP-302 3.5.1-77 c Monitoring Carbon steel Air-indoor Loss of material Structures llf.A1.TP-302 3.5.1-77 c uncontrolled or Monitoring Air -outdoor Page 3.5-50 Table 3.5.2-1: Reactor Building Intended Component Type Function Material En:vironment Steel components: FB Carbon steel Air-indoor annulus access lock uncontrolled /Air -outdoor Steel components: EN, HS, MB, Carbon steel Air-indoor beams, columns and SNS, SSR uncontrolled plates Steel components: EN, HS, MB, Carbon steel Air with borated beams, columns arid SNS, SSR water leakage plates Steel components: HS, MB, Carbon steel Air-indoor impingement barriers SSR uncontrolled Steel components: HS, MB,
Carbon steel Air with borated impingement barriers SSR water leakage Steel components: HS, SNS Carbon steel Air-indoor jib cranes uncontrolled Steel components: HS, SSR Stainless Exposed to fluid liner plate steel environment Steel components: HS, SSR Stainless Air-indoor liner plate steel uncontrolled Steel components: MB, PB, Carbon steel Air-indoor maintenance. hatch SSR uncontrolled or shield door Air -outdoor Steel components: FB Carbon steel Air-indoor maintenance hatch uncontrolled /Air shield door -outdoor ' 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Fire Protection Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monito.ring Loss of material Structures Monitoring None Nm1e Loss of material Structures Monitoring Loss of material Fire Protection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 . 1801 Item Item Notes Vll.G.A-21 3.3.1-59 c Vll.G.A-22 lll.A4.TP-302 3:5.1-77 A lll.B5.T-25 3.5.1-89 c lll.A4.TP-302 3.5.1-77 A lll.B5.T-25 3.5.1-89 c lll.A4.TP-302 3.5.1-77 A lll.A7.T-23 3.5.1-52 E lll.B5.TP-8 3.5.1-95 c II l.A4. TP-302 3.5.1-77 c Vll.G.A-21 3.3:1-'59 G Vll.G.A-22 Page 3.5-51 Table 3.5.2-1 : Reactor Building Intended Component Type Function Material Environment Steel components: HS, SNS Carbon steel Air -indoor
monorails uncontrolled Steel components: EN, PB, Carbon steel Air-indoor personnel airlock, SNS, SRE, uncontrolled escape lock, SSR construction hatch, maintenance hatch Steel components: FB Carbon steel Air-indoor personnel airlock, uncontrolled /Air escape lock, -outdoor construction hatch, maintenance hatch Steel components: PB,SSR Carbon steel Air-indoor personnel airlock, uncontrolled escape lock, construction hatch; maintenance hatch: locks, hinges, and closure mechanisms Steel components: PB,SSR Carbon steel Air-indoor personnel airlock, uncontrolled escape lock, construction hafoh; maintenance hatch: locks, hinges, and closure mechanisms 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of leak tightness Aging Management Programs Structures Monitoring Cll-IWE Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II 1.A4. TP-302 3.5.1-77 c ll.A3.C-16 3.5.1-28 A Containment Leak Rate Fire Protection Vll.G.A-21 3.3.1-59 c Vll.G.A-22 Cll-IWE ll.84.CP-148 3.5.1-31 A Cll-IWE ll.A3.CP-39 3.5.1-29 A Containment* Leak Rate Page 3.5-52 Table 3.5.2-1 : Reactor Building Intended -Component Type Fun.ction Material Environment Steel components: PB,SSR. Stainless Air-indoor personnel airlock, steel uncontrolled escape lock, construction hatch; maintenance hatch: locks, hinges, and closure mechanisms Steel components: HS, PB, SSR Carbon steel Air-indoor pressure retaining Stainless uncontrolled bolting steel Steel components: MS, PB, SSR Carbon steel Air-indoor pressure retaining uncor:itrolled bolting
Steel component: HS, MB, Carbon steel Air-indoor reactor missile shield SSR uncontrolled Steel component: HS, MB, Carbon steel Air with borated reactor missile shield SSR water leakage Steel component: FLB, HS, Stainless Exposed to fluid reactor cavity seal SNS, SSR steel environment ring and hatches Steel component: FLB, HS, Stainless Air-indoor reactor cavity seal *sNS, SSR steel uncontrolled ring and hatches Steel components: HS, SNS Carbon steel Air-indoor refueling uncontrolled maintenance structure 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of leak tightness Loss of preload Loss of material Loss of material Loss of material Loss of material None Loss of material Aging Management Programs Cll-IWE Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ll.A3.CP-39 3.5.1-29 A Containment Leak Rate Cll-IWE ll.A3.CP-150 3.5.1-30 A Containment Leak Rate Cll-IWE ll.A3.CP-148 3.5.1-31 A Structures lll.A4.TP-302 3.5.1-77 c Monitoring Boric Acid lll.B5.T-25 3.5.1-89 c Corrosion Structures lll.A7.T-23 3.5.1-52 E Monitoring None lll.B5.TP-8 3.5.1-95 A Structures lll.A4.TP-302 3.5.1-77 c Monitoring Page 3.5-53 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Steel components: HS, SNS Carbon steel Air-indoor refueling platform uncontrolled equipment assembly and rails Steel elements EN, HS, PB, Carbon steel Air-indoor (accessibfe areas): SRE, SSR uncontrolled liner; liner anchors; integral attachments (steel containment vessel) Steel elements EN, HS, PB, Carbon steel Air with borated (accessible areas): SRE, SSR water leakage liner; liner anchors; integral attachments (steel containment vessel) Steel elements EN, HS, PB, Carbon steel Air-indoor (inaccessible areas): SRE, SSR uncontrolled liner; liner anchors; integral attachments (steel containment vessel) Steel elements: SIS HS, SSR Stainless Exposed to fluid sump screens/ steel environment strainers 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Inspection of Vll.B.A-07 3.3.1-52 A OVHLL Cll-IWE 11.A2.CP-35 3.5.1-35 A Containment Leak Rate Boric Acid 111.85.T-25 3.5.1-89 A Corrosion* Cll-IWE 11.A2.CP-98 3:5.1-5 A Containment Leak Rate Structures lll.A7.T-23 3.5.1-52 E Monitoring Page 3.5-54 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Steel elements: HS, SSR Stainless Air-indoor SIS sump screens steel uncontrolled I strainers Support members: HS, SSR Carbon steel Air-indoor welds; bolted uncontrolled connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) Support members: HS, SSR Carbon steel Air with borated welds; bolted water leakage connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None .Loss of material ISl-IWF Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes 111.85.TP-8 3.5.1-95 c 111.81 .1.T-24 3.5.1-91 A 111.81 .1.T-25 3.5.1-89 A Page 3.5-55 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Support members: HS, SSR Carbon steel Air-indoor welds; bolted uncontrolled connections; support anchorage to '. building structure (supports and restraints for the reactor pressure vessel) Support members: HS, SSR Carbon steel Air with borated
welds; bolted water leakage. connections; support* anchorage to building structure (supports and restraints for the reactor pressure vessel) Beams, columns, EN,HS, MB, Concrete Air-indoor floor slabs and SNS, SRE, uncontrolled interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and missile shield and barriers) 3.0 Aging Management Review Results / : Aging Effect Aging Requiring : Management Management Programs Loss of material ISl-IWF " Loss of material Boric Acid Corrosion Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) \. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.B1 .1.T-24 3.5.1-91 A : lll.B1.1.T-25 3.5.1-89 A lll.A4.TP-28 3.5.1-67 A Page 3.5-56 Table 3.5.2-1 : Reactor Building Intended Component Type Function Material Beams, columns, EN, HS, MB, Concrete floor slabs and SNS, SRE, interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and missile shield and barriers) Beams, columns, EN, HS, MB, Concrete floor slabs and SNS, SRE, interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and
missile shield and barriers) Concrete (accessible EN, FLB, Concrete areas): shield MB, PB, building; all SNS, SRE, SSR Concrete (accessible EN, FLB, *Concrete areas): shield MB, PB, building; all SNS, SRE, SSR 3.0 Aging Management Review Results Aging Effect Requiring Environment Management Air-indoor Cracking, loss of uncontrolled bond, and loss of material (spalling, scaling) Air-indoor Cracking uncontrolled Air-indoor Cracking uncontrolled or Air -outdoor Air-indoor Increase in uncontrolled or porosity and Air -outdoor permeability, cracking, loss of material (spalling, scaling) Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A4.TP-26 3.5.1-66 A lll.A4.TP-25 3.5.1-54 A lll.A1.TP-25 3.5.1-54 A lll.A4.TP-28 3.5.1-67 A Page 3.5-57 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield. MB, PB, uncontrolled or building; all SNS, SRE,. Air -outdoor SSR Concrete (accessible EN, MB, Concfete Air-indoor areas): refueling SNS, SRE, -uncontrolled canal SSR Concrete (accessible EN, HS, MB, Air-indoor areas): refueling SNS, SRE, uncontrolled canal SSR Concrete (accessible EN, HS, MB, Concrete Air-indoor areas): refueling SNS, SRE, uncontrolled canal SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): Shield MB, PB, uncontrolled _or building wall and SNS, SRE, Air -outdoor dome; interior and. SSR above-grade exterior 3.0 Aging Management Review Results Aging Effect Aging Requiring -Management Management Programs Cracking, loss of Structures bond, and loss of Monitoring material (spalling, . scaling) Cracking Structures Monitoring Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) -r Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A4.TP-26 3.5.1-66 A lll.A5.TP-25 3.5.1-54 A lll.A4.TP-28 3.5.1-67 A lll.A4.TP-26 3.5.1-66 A 111.A1.TP-26 3.5.1-66 A Page 3.5-58 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield MB, SNS, uncontrolled or building wall and SRE, SSR Air -outdoor dome; interior and above-grade exterior Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield MB, SNS, uncontrolled or building wall and
SRE, SSR Air -outdoor dome; interior and above-grade exterior Concrete EN, HS,MB,. Concrete Air-indoor (inaccessible areas): SNS, SRE, uncontrolled refueling canal SSR Concrete EN, FLB, Concrete Air-indoor (inaccessible areas): MB, SNS, uncontrolled or shield building; all .. SRE, SSR Air -outdoor Compressible seals PB,SSR Elastomer Air-indoor for annulus lock; uncontrolled escape lock; personnel lock; maintenance hatch Containment FB, PB, SSR Elastomer Air-indoor penetration seals uncontrolled and sealant 3.0 Aging Management Review Results. Aging Effect Requiring Management Increase in porosity and permeability,. cracking, loss of material (spalling, scaling) Cracking Cracking Cracking
Loss of sealing Loss of sealing, Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam El.ectric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A1.TP-28 3.5.1-67 A lll.A1.TP-25 3.5.1-54 A lll.A5.TP-204 3.5.1-43 E .111.A1.TP-204 3.5.1-43 E Containment Leak ll.A3.CP-41 3.5.1-33 A Rate ' Containment Leak .ll.A3.CP-41 3.5.1-33 A Rate Page 3.5-59 Table 3.5.2-1: Reactor Building Intended ..
Component Type Function Material Environment Inflatable seal for PB, SSR Elastomer Air-indoor maintenance hatch uncontrolled shielding door Moisture barrier EN,SSR Elastomer Air-indoor uncontrolled . Service Level I .SNS Coatings Air-indoor coating$ uncontrolled Service Level I SNS Coatings Air-indoor coatings uncontrolled ". 3.0 Aging Management Review Results Aging Effect Re.quiring Management of sealing Loss of sealing *' Loss of coating '. integrity Loss of coating integrity Aging Management Programs Structures Monitoring .Cll-IWE Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1
1801 Item Item Notes 111.A6.TP-7 3.5.1-72 A 3.5.1-26 A . Protective Coating ll.A3.CP-152 3.5.1-34 A Monitoring -and* . Maintenance Protective Coating lll.A4.TP-301 3.5.1-73 A Monitoring and Maintenance .. . Page 3.5-60 Table 3.5.2-2 Nuclear Plant Island Structure Summary of Aging Management Evaluation. Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program*s Control room ceiling SNS Carbon steel Air-indoor Loss of material Structures support system uncontrolled Monitoring Cooling tower fill/mist HS, SSR Stainless Exposed to fluid Loss of material Structures eliminators steel environment Monitoring Cranes: rails SNS Carbon steel Air-indoor Loss of material Inspection of uncontrolled
OVHLL Cranes: structural SNS Carbon steel Air-indoor Loss of material Inspection of girders uncontrolled OVHLL Cranes: structural SNS Carbon steel Air-indoor Cumulative fatigue TLAA-metal girders uncontrolled damage fatigue* Steel components: EN, SNS, Carbon steel Air-indoor Loss of material Structures all structural steel SRE, SSR uncontrolled or _Monitoring Air -outdoor Steel components: EN, SNS, Galvanized Exposed to fluid Loss of material Structures all structural steel SRE, SSR steel environment Monitoring Steel components: FLB, HS, Stainless Air-indoor None None fuel pool gate SSR steel uncontrolled 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II 1.A3. TP-302 3.5.1-77 A 111.AB.T-23 3.5.1-52 E Vll.B.A-07 3.3.1-52 A Vll.B.A-07 3.3.1-52 A Vll.B.A-06 3.3.1-1 A II l.A3.TP-302 3.5.1-77 c II I.AS. TP-302 lll.A6.TP-221 3.5.1-77 E 111.84.TP-8 3.5.1-95 c Page 3.5-61 Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Intended Requiring Component Type Function Material Environment Management Steel components: FLB, HS, Stainless Exposed to fluid Loss of material fuel pool gate SSR steel environment Steel components: *HS, SSR Stainless Air-indoor None fuel pool liner plate steel uncontrolled Steel components: HS, SSR Stainless Exposed to fluid Loss of material fuel pool liner plate steel environments Steel components: EN, HS, Stainless Exposed to fluid Loss of material CSP liner plate SSR steel environments 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Water Chemistry lll.A5.T-14 3.5.1-78 A Control -Primary and Secondary Monitoring of spent fuel storage pool level per Tech Spec and monitoring leakage from leak chase channel None 111.84.TP-8 3.5.1-95 c Water Chemistry lll.A5.T-14 3.5.1-78 A Control -Primary and Secondary Monitoring of spent fuel storage pool level per Tech Spec and monitoring leakage from leak chase channel Structures lll.A7.T-23 3.5.1-52 E Monitoring Water Chemistry Control -Primary and Secondary Page 3.5-62 Table 3.5.2-2: Nuclear Plant Island Structure Intended Component Type Function Material Environment Steel components: EN, HS, Stainless Exposed to fluid RWSP liner plate SSR steel environments Steel components: SNS Carbon steel Air-indoor monorails uncontrolled Steel components: EN, SSR Stainless Exposed to fluid vortex breakers/ steel environments screens/strainers Beams, columns, EN, FLB, Concrete Air-indoor floor slabs and pipe HS, MB, uncontrolled chase SNS, SRE, SSR Beams, columns, EN, FLB, Concrete Air-indoor floor slabs and pipe HS, MB, uncontrolled chase SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): all HS, MB, uncontrolled/ Air SNS, SRE, -outdoor/ Soil I SSH Exposed to fluid environment 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring Water Chemistry Control -Primary and Secondary Loss of material Structures Monitoring Loss of material Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Cracking Structures Monitoring Cracking Structures Monitoring Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A7.T-23 3.5.1-52 E 111.A3.TP-302 3.5.1-77 c lll.A5.TP-302 lll.A7.T-23 3.5.1-52 E lll.A3.TP-26 3.5.1-66 A lll.A5.TP-26 lll.A3.TP-25 3.5.1-54 A lll.A5.TP-25 lll.A3.TP-25 3.5.1-54 A 111.AS.TP-25 Page 3.5-63 Table 3.5.2-2: Nuclear Plant Island Structure r Intended
Component Type Function Material Environment I Concrete (accessible EN, FLB, Concrete Exposed to fluid areas): all HS, MB, environment SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Exposed to fluid areas): all HS, MB, environment SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Soil areas): below-grade HS, MB, exterior; foundation SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): interior and HS, MB, uncontrolled or above-grade exterior SNS, SRE, Air -outdoor SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): interior and HS, MB, uncontrolled or above-grade exterior SNS, SRE, Air -outdoor SSR Concrete (accessible EN, FLB, Concrete Soil areas): NPIS exterior HS, MB, above-and below-SNS, SRE, grade; foundation SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability; Loss of strength Cracking, loss of Structures bond, and loss of *material (spalling, Monitoring scaling) Cracking, loss of Structures bond, and .loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability; cracking; loss of material (spalling, scaling) Cracking and Structures distortion Monitoring Waterford Steam Electric Station, Unil 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-27 3.5.1-65 A lll.A5.TP-27 lll.A3.TP-24 3.5.1-63 A 111.A5.TP-:24 lll.A3.TP-27 3.5.1-65 A lll.A5.TP-27 lll.A3.TP-26 3.5.1-66 A lll.A5.TP-26 lll.A3.TP-28 3.5.1-67 A 111.A5.TP-28 lll.A3.TP-30 3.5.1-44 A lll.A5.TP-30 Page 3.5-64 Table 3.5.2-2: Nuclear Plant Island Structure Intended Component Type Function Material Environment Concrete EN, FLB, Concrete Air-indoor (inaccessible areas): HS, MB, uncontrolled/ Air all SNS, SRE, -outdoor/ Soil/ SSR Exposed to fluid environment Concrete EN, FLB, Concrete Soil (inaccessible areas): HS, MB, exterior above-and SNS, SRE, below-grade; SSR foundation Concrete EN, FLB, Concrete Soil (inaccessible areas): HS, MB, exterior above-and SNS, SRE, below-grade; SSR foundation Masonry walls EN, SNS, Concrete Air-indoor SRE, SSR block uncontrolled Masonry walls FB Concrete Air-indoor block uncontrolled Masonry walls FB Concrete Air-indoor block uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking
Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Masonry Wall Cracking Structures Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II l.A3. TP-204 3.5.1-43 E lll.A5.TP-204 lll.A3.TP-212 3.5.1-65 A lll.A5.TP-212 lll.A3.TP-29 3.5.1-67 A lll.A5.TP-29 lll.A3.T-12 3.5.1-70 A lll.A5.T-12 Vll.G.A-90 3.3.1-60 c Vll.G.A-91 3.3.1-62 c Page 3.5-65 Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Intended Requiring Component Type Function Material Environment Management Roof slabs EN, MB, Concrete Air-indoor Cracking, loss of SRE, SSR uncontrolled/ Air bond, and loss of -outdoor material (spalling, scaling) 3.0 Aging Management Review Results Aging Management Programs Structures Moniforing . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-26 3.5.1-66 A 111.AS.TP-26 Page 3.5-66 Table 3.5.2-3 Turbine Building and Other Structures Summary of Aging Management Evaluation Table 3.5.2-3: Turbine Building and Other Structures Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Cranes: rails and SNS Carbon steel Air-indoor Loss of material Inspection of structural girders OVHLL Steel components: EN, SNS, Carbon steel Air-indoor Loss of material Structures all structural steel SRE uncontrolled or Monitoring Air -outdoor Steel components: EN, SNS Galvanized Air-indoor Loss of material Structures Metal siding steel uncontrolled or Monitoring Air -outdoor Steel components: EN Galvanized Air-indoor Loss of material Structures Roof decking or floor steel uncontrolled or Monitoring decking Air -outdoor Steel components: FB Galvanized Air-indoor Loss of material Fire Protection Roof decking or floor steel uncontrolled decking Steel piles SRE Carbon Steel Soil None None Transmission tower, SRE Galvanized Air-indoor Loss of material Structures angle tower, pull-off steel Monitoring tower Beams, columns, EN, SNS, Concrete Air-indoor Cracking, loss of Structures floor slabs SRE uncontrolled bond, and loss of Monitoring material (spalling, scaling) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes G lll.A3.TP-302 3.5.1-77 A lll.A3.TP-302 3.5.1-77 A II l.A3.TP-302 3.5.1-77 A Vll.G.AP-150 3.3.1-58 c I, 501 111.82.TP-6 3.5.1-93 c lll.A3.TP-26 3.5.1-66 A Page 3.5-67 Table 3.5.2-3: Turbine Building and Other Strucrtures '. Aging Effect , Intended '* Requiring Component Type Function Material Environment Management Beams, columns, EN, SNS, Air :-indoor Cracking floor slabs SRE *uncontrolled
Concrete (accessible EN, SNS,
Concrete Air-indoor Cracking areas): all SRE *' uncontrolled or . Air -outdoor Concrete (accessible EN, SNS, Concrete : Soil Cracking, loss.of *' areas): below-grade SRE bond, and loss of exterior; foundation material (spalling, *. scaling) Concrete (accessible EN, SNS,* Concrete Air-indoor Cracking, loss of areas): interior and SRE
uncontrolled or bond, and loss of above-wade exterior . Air -outdoor , material (spalling, scaling) Concrete (accessible EN, SNS, Concrete Air-indoor Increase in interior and SRE uncontrolled or and above-grade exterior. Air -outdoor permeability; cracking; loss of ; material (spalling, scaling) Concrete (accessible EN, SNS,** Concrete Exposed to flt} id, Increase in areas): exterior SRE environment
porosity and above-and .below-. permeability; Loss grade; foundation :of strength Concrete (accessible EN, SNS, Concrete . Soil . . Cracking and areas): exterior SRE distortion above-and below-grade; foundation ., 3.0 Aging Management Review Results Aging Management Programs . Monitoring Structures
Monitoring Structures Monitoring Structures
Monitoring Structures llJ!onitoring Structures . Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-* Table 1 1801 Item Item Notes lll.A3.TP-25 3.5.1-54 A lll.A3.TP-25 3.5.1-54 A lll.A3.TP-27 3.5.1-65 A Ul.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A lll.A3.TP-24 3.5.1-63 A lll.A3.TP-30 3.5.1-44 A Page 3.5-68 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Concrete EN, SNS, Concrete Air-indoor (inaccessible areas): SRE uncontrolled/ Air all -outdoor/ Soil I Exposed to fluid environment Concrete EN, SNS, Concrete Soil (inaccessible areas): SRE exterior above-and -below-grade; foundation Concrete EN, SNS, Concrete Soil (inaccessible areas): SRE exterior above-and below-grade; foundation Duct banks EN, SNS, Concrete Soil SRE Duct banks EN, SNS, Concrete Soil SRE 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity. and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking and Structures distortion Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item .Item Notes I I I .A3. TP-204 3.5.1-43 A lll.A3.TP-212 3.5.1-65 A lll.A3.TP-29 3.5.1-67 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A Page 3.5-69 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Duct banks EN, SNS, Concrete Soil SRE Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Air -outdoor switchyard, transformers, tanks, circuit breakers) 3.0 Aging Management Review Results Aging Effect Requiring Management Increase in porosity and permeability, cracking, loss of material (spalling, scaling) Cracking and distortion Cracking, loss of bond, and loss of material (spalling, scaling) Increase in porosity and permeability, cracking, loss of material (spalling, scaling) Cracking, loss of bond, and loss of material (spalling, scaling) / Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-29 3.5.1-67 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A lll.A3.TP-29 3.5.1-67 A lll.A3.TP-26 3.5.1-66 A Page 3.5-70 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Foundations (e.g., SNS,SRE Concrete Air -outdoor switchyard, transformers, tanks, circuit breakers) Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Loss of material Structures (spalling, scaling) Monitoring and cracking Cracking and Structures distortion Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-28 3.5.1-67 A lll.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A I I l.A3. TP-23 3.5.1-64 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A Page 3.5-71 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE Manholes and FB Concrete
Air -outdoor hand holes Manholes and FB Concrete Air -outdoor -handholes *-Masonry wall SNS. Concrete Air-indoor
block uncontrolled Masonry wall FB Concrete Air-indoor block uncontrolled Masonry wall FB Concrete Air-indoor block uncontrolled Wooden .Piles SNS Treated wood Soil 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures material Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection ,Cracking Masonry Wall -,, Cracking Structures Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection Loss of material Structures Change in material Monitoring
properties Waterford Steam Electric Station, Unit 3 _ License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-29 3.5.1-67 A Vll.G.A-92 3.3.1-61 A Vll.G.A-93 3.3.1-62 A-. lll.A3.T-12 3.5.1-70 A Vll.G.A-90 3.3.1-60 c Vll.G.A-91 3.3.1-62 c II 1.A6. TP-223 3.5.1-62 E Page 3.5-72 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE1 embedments SSR Anchorage I SNS, SRE, embedments SSR Anchorage I SNS, SRE, embedments SSR 3.0 Aging Management Review Results Table 3.5.2-4 Bulk Commodities Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Materiiil Environment Management Programs Carbon steel Air-indoor Loss of material Structures uncontrolled or Monitoring Air -outdoor Carbon steel Air-indoor Loss of material Structures uncontrolled or Monitoring Air -outdoor Carbon steel Air-indoor Loss of material ISl-IWF uncontrolled or Air -outdoor Carbon steel Exposed to fluid Loss of material Structures environment Monitoring Carbon steel Air with borated Loss of material 8oricAcid water leakage Corrosion Stainless Exposed to fluid Loss of material Water Chemistry steel environment Control -Primary (temp< 140) and Secondary ISl-IWF Stainless Air-indoor None None steel uncontrolled Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1. TP-302 3.5.1-77 c II l.A3. TP-302 II 1.A4. TP-302 II I.AS. TP-302 111.82.TP-43 3.5.1-92 c 111.81.1.T-24 3.5.1-91 c . 111.81 .2.T-24 lll.A6.TP-221 3.5.1-83 E 111.82.T-25 3.5.1-89 c 111.81.1.TP-10 3.5.1-90 c " 111.82.TP-8, 3.5.1-95 c 111.83.TP-8, 111.84.TP-8, 111.85.TP-8 Page 3.5-73 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Anchorage/ SNS, SRE, Stainless Air with borated embedments SSR steel water leakage Cable tray SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Cable tray SNS, SRE, Carbon steel Air with borated SSR water leakage Cable tray SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Cable tray SNS, SRE, Galvanized Air with borated SSR steel water leakage Cable tray SNS, SRE, Galvanized Air -outdoor SSR steel Conduit SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Conduit SNS, SRE, Carbon steel Air with borated SSR water leakage Conduit SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Conduit SNS, SRE, Galvanized Air with borated SSR steel water leakage Conduit SNS, SRE, Galvanized Air -outdoor SSR steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Leiss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-4 3.5.1-95 c 111.83.TP-4 111.84.TP-4 111.85.TP-4 111.82.TP-43 3.5.1-92 c 111.82.T-25 3.5.1-89 c 111.82.TP-8 3.5.1-95 c 111.82.TP-3 3.5.1-89 c lll.B2.TP-6 3.5.1-93 c 111.82.TP-43 3.5.1-92 c 111.82.T-25 3.5.1-89 c lll.B2.TP-8 3.5.1-95 c lll.B2.TP-3 3.5.1-89 c lll.B2.TP-6 3.5.1-93 c Page 3.5-74 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Constant and SRE, SSR Carbon steel, Air-indoor variable load spring Galvanized uncontrolled hangers; guides; steel stops (Supports for ASME Class 1, 2 and 3 piping and components) Doors EN, FLB, Carbon steel Air-indoor MB, PB uncontrolled Doors EN, FLB, Carbon steel Air -outdoor MB, PB Doors EN, FLB, Carbon steel Air with borated MB, PB water leakage Fire doors FB Carbon steel Air-indoor
uncontrolled Fire doors SRE Carbon steel Air-indoor uncontrolled Fire doors SRE Carbon steel Air with borated water leakage Fire hose reels SRE Carbon steel Air-indoor uncontrolled or Air -outdoor 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of mechanical function Loss of material Loss of.material Loss of material Loss of material Loss of material Loss of material Loss of material Aging Management Programs ISl-IWF Structures Monitoring Structures Monitoring Boric Acid Corrosion Fire Protection Structures Monitoring Boric Acid Corrosion ., Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B1.1:T-28 3.5.1-57 A lll.B1 .2.T-28 lll.B1.3.T-28 lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 lll.A4.TP-302 II l.A5. TP-302 lll.A1 .TP-302 3.5.1-77 c lll.A3.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Vll.G.A-21 3.3.1-59 A lll.A1.TP-302 3.5.1-77 c II l.A3. TP-302 lll.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Fire Water System lll.B2.TP-43 3.5.1-92 E Page 3.5-75 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Fire hose reels SRE Carbon steel Air with borated water leakage Fire protection FB Carbon steel Air-indoor components -uncontrolled
miscellaneous steel including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Fire protection SNS,SRE Carbon steel Air with borated components -water leakage miscellaneous steel including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Manways, hatches, EN, FLB, Carbon steel Air-indoor manhole covers and PB, MB, uncontrolled or hatch covers SNS, SRE, Air -outdoor SSR Manways, hatch.es, EN, FLB, Carbon steel. Air with borated manhole covers and PB, MB, water leakage hatch covers SNS, SRE, SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material Fire Protection Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B2.T-25 3.5.1-89 c Vll.G.A-21 3.3.1-59 c lll.B2.T-25 3.5.1-89 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 II l.A4. TP-302 II I.AS. TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-76 Table 3.5.2-4: Bulk Commodities . Intended Component Type Function Material Environment Mirror insulation SNS Stainless Air-indoor steel uncontrolled Mirror insulation SNS Stainless. Air with borated steel water leakage Missile shields EN, MB Carbon steel Air-indoor uncontrolled or Air -outdoor Missile shields EN, MB Carbon steel Air with borated
water leakage Miscellaneous steel EN, FLB, Carbon steel 'Air -indoor (decking, grating, SNS, SSR
uncontrolled or handrails, ladders, Air -outdoor enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Carbon steel Air with borated (decking, grating, SNS, SSR
water leakage handrails, ladders, enclosure plates, *-stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None, None None None Loss of material Structures ' Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss bf material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-17 3.3.1-120 c lll.B2.TP-4 3.5.1-95 c lll.A7.TP-302 .3.5.1-77 c ' lll.B2.T-25 3.5.1-89 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 .111.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-77 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Miscellaneous steel EN, FL8, Galvanized Air-indoor (decking, grating,* SNS,SSR steel
uncontrolled handrails, ladders, enclosure plates, platforms, stairs, .. vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Galvanized Air -outdoor (decking, grating, SNS,SSR steel handrails, ladders, enclosure plates, *. platforms, stairs, *' vents and louvers, framing steel, etc) Miscellaneous steel EN, FL8, Galvanized Air with borated * (decking, grating, SNS, SSR steel water leakage
handrails, ladders, enclosure plates, ... stairs, vents and louverf\, framing steel, etc) Miscellaneous steel EN, FLB, Aluminum Air:-indoor (decking, grating, SNS, SS.R ' uncbritrolled handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc)* 3.0 Aging Management Review Results Aging Effect *Aging Requiring
Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None, None " .. '. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-8 3.5.1-95 c 111.85.TP-8 Ill.A 1.TP-302 3.5.1-77 c II l.A3. TP-302 II l.A4. TP-302 II l.A5. 111.82.TP-3 3:5.1-89 c . 111.82.TP-8 3,5.1-95 c 111.85.TP-8 Page 3.5-78 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Miscellaneous steel EN, FLB, Aluminum Air -outdoor (decking, grating, SNS, SSR handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Aluminum Air with borated (decking, grating, SNS, SSR water leakage handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Penetration seals FB Carbon steel Air-indoor (end caps) uncontrolled Penetration seals EN, FLB, Carbon steel Air-indoor (end caps) PB, SNS, uncontrolled or SSR Air -outdoor Penetration seals EN, FLB, Carbon steel Air with borated (end caps) PB, SNS, water leakage SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Fire Protection Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-6 3.5.1-93 c lll.B2.TP-3 3.5.1-89 c lll.B5.TP-3 Vll.G.A-21 3.3.1-59 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 lll.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-79 Table 3.5.2-4: Bulk Commodities Intended Type* Function Material Environment Penetration sleeves FB Carbon steel Air-indoor (mechanical/ uncontrolled electrical not penetrating PC boundary) Penetration sleeves EN, FLB, . Carbon steel Air-indoor (mechanicai/ PB, SNS, uncontrolled or electrical not SSR ' Air_: outd9or
penetrating PC boundary) Penetration sleeves EN, FLB, Carbon steel Air with borated (mechanical/ PB, SNS, water leakage electrical not SSR penetrating PC boundary) Racks, panels, . ' EN, SNS, Carbon steel Air-indoor cabinets and SRE, SSR uncontroiled or enclosures* for Air -outdoor electrical equipment.* and instrumentation Racks, panels, . EN, SNS, Carbon steel
Air with borated cabinets and SRE, SSR water leakage enclosures for electrical equipment and instrumentation 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Fire Protection .. Loss of material
Structures Monitoring .. Loss of material Boric Acid* Corrosion Loss of material Structures Monitoring Loss of material
BoricAcid .. Corrosion .. ... Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.G.A-21 3.3.1-59 c '* -lll.B2.TP-43 3.5.1-92 c lll.B2.T-25 3.5.1-89 c lll.B3.TP-43 3.5.1-92 c lll.B3.T-25 3.5.1-89 c -Page 3S80 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Racks, panels, EN, SNS, Galvanized Air-indoor cabinets and SRE, SSR steel uncontrolled enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Galvanized Air -outdoor cabinets and SRE, SSR steel enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Galvanized Air with borated cabinets and SRE, SSR steel water leakage enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Stainless Air-indoor cabinets and SRE, SSR steel -uncontrolled enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Stainless Air -outdoor cabinets and SRE, SSR steel enclosures for electrical equipment and instrumentation 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.83.TP-8 3.5.1-95 c 3.5.1-92 c 111.83.TP-3 3.5.1-89 c 111.83.TP-8 3.5.1-95 c 111.82.TP-6 3.5.1-93 c 111.84.TP-6 Page 3.5-81 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Racks, panels, EN, SNS, Stainless Air with borated cabinets and SRE, SSR steel water leakage enclosures for electrical equipment and instrumentation Tube track SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Tube track SNS, SRE, Carbon steel Air with borated SSR water leakage Tube track SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Tube track SNS, SRE, Galvanized Air -outdoor SSR steel Tube track SNS, SRE, Galvanized Air with borated SSR steel water leakage Supports for ASME SRE, SSR Carbon steel Air with borated Class 1, 2 and 3 water leakage piping and components (Constant and variable load spring hangers; guides; stops) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B3.TP-4 3.5.1-95 c lll.B2.TP-43 3.5.1-92 c lll.B2.T-25 3.5.1-89 c lll.B2.TP-8 3.5.1-95 c lll.B2.TP-6 3.5.1-93 A lll.B2.TP-3 3.5.1-89 c lll.B1.1.T-25 3.5.1-89 A lll.B1.2.T-25 Page 3.5-82 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Supports for ASME SRE, SSR Galvanized Air with borated Class 1, 2 and 3 steel water leakage piping and components (Constant and variable load spring hangers; guides; stops) Support members; SNS, SRE, Carbon steel Air-indoor welds; bolted SSR uncontrolled or connections; support Air -outdoor anchorage to building structure Support members; SNS, SRE, Carbon steel Air-indoor welds; bolted SSR uncontrolled or connections; support Air -outdoor anchorage to building structure Support members; SNS, SRE, Carbon steel Air with borated welds; bolted SSR water leakage connections; support anchorage to building structure 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material ISl-IWF Loss of material Structures Monitoring Loss of material 8oricAcid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-3 3.5.1-89 A 111.81.2.TP-3 lll.B1 .1.T-24 3.5.1-91 A lll.B1.2.T-24 lll.B2.TP-43 3.5.1-92 A lll.B3.TP-43 111.84.TP-43 111.BS.TP-43 lll.B1.1.T-25 3.5.1-89 A 111.Bt.2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 Page 3.5-83 Table 3.5.2-4: . Bulk Commodities Intended Component Type Function Material Environment Support members; SNS, SRE, Galvanized Air-indoor welds; bolted SSR steel uncontrolled connections; support anchorage to building structure Support members; SRE, SSR Galvanized Air -outdoor welds; bolted steel connections; support anchorage to building structure Support members; SNS, SRE, Galvanized Air with borated welds; bolted SSR steel water leakage connections; support anchorage to building structure Support members; SNS, SRE, Galvanized Air -outdoor welds; bolted SSR steel connections; support anchorage to building Support members; SNS, SRE, Galvanized Air -outdoor welds; bolted SSR steel connections; support anchorage to building structure 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material ISl-IWF Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring Loss of material Structures . Monitoring Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information NUREG-1801
Table 1 Item Item Notes 111.81.1.TP-8 3.5.1-95 A 111.81 .2.TP-8 111.82.TP-8 111.83.TP-8 111.84.TP-8 111.85.TP-8 111.81.1.T-24 3.5.1-91 A 111.81.2.T-24 111.81 .1.TP-3 3.5.1-89 A 111.81-2.TP-3 111.82.TP-3 111.83.TP-3 111.84.TP-3 111.85.TP-3 111.82.TP-6 3.5.1-93 A 111.84.TP-6 111.83.TP-43 3.5.1-92 A 111.85.TP-43 Page .3.5-84 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Support members; SNS, SRE, Stainless Air-indoor welds; bolted SSR steel uncontrolled connections; support anchorage to building structure Support members; SNS, SRE, Stainless Air -outdoor welds; bolted SSR steel connections; support anchorage to building structure Support members; SNS, SRE, Stainless Air with borated welds; bolted SSR steel water leakage connections; support anchorage to building structure Anchor bolts SNS, SRE, Carbon steel Air-indoor SSR uncontrolled Anchor bolts SNS, SRE, Carbon steel Air -outdoor SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring None None Loss of material Structures Monitoring Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-8 3.S.1-9S A 111.83.TP-8 111.82.TP-6 3.S.1-93 A 111.84.TP-6 111.82.TP-4 3.S.1-9S A 111.83.TP-4 lll.A1.TP-248 3.S.1-80 A II l.A3. TP-248 II l.A4. TP-248 II I.AS. TP-248 I II .A6. TP-248 111.A1.TP-274 3.S.1-82 A lll.A3.TP-274 II l.A4. TP-27 4 I I I .AS. TP-27 4 Page 3.5-85 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Anchor bolts SNS, SRE, Carbon steel Air with borated SSR water leakage Anchor bolts SNS, SRE, Carbon steel Exposed to fluid SSR environment Anchor bolts SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Anchor bolts SNS, SRE, Galvanized Air*-outdoor SSR steel Anchor bolts SNS, SRE, Galvanized Air with borated SSR steel water leakage -Anchor bolts SNS, SRE, Galvanized Exposed to fluid SSR steel environment Anchor bolts SNS, SRE, Stainless Air-indoor SSR steel uncontrolled Anchor bolts SNS, SRE, Stainless Air -outdoor SSR steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material Structures Monitoring None None Loss of material Structures . Monitoring Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring None None Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Applic?tion Technical Information NUREG-1801 .*Table 1 Item Item Notes 111.81.1.T-25 3.5.1-89 c 111.81.2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 lll.A6.TP-221 3.5.1-83 111.82.TP-8 3.5.1-95 c 111.A 1 .TP;.27 4 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 lll.A5.TP-274 111.81 .1.TP-3 3.5.1-89 c 111.81-2.TP-3 111.82.TP-3 -111.83.TP-3 111.84.TP-3 111.85.TP-3 lll.A6.TP-221 3.5.1-83 E 111.82.TP-8 3.5.1-95 c 111.82.TP-6 3.5.1-93 c 111.84.TP-6 Page3.5-86 Table 3.5.2-4: Bulk Gommodities Intended Component Type Function Material Environment Anchor bolts SNS, SRE, Stainless Air with borated SSR steel water leakage Anchor bolts SNS, SRE, Stainless Exposed to fluid SSR steel environment (Temp< 140) High strength SNS, SRE, Carbon steel Air-indoor structural bolting SSR uncontrolled (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Carbon steel Air with borated structural bolting SSR water leakage (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Stainless Air-indoor structural bolting SSR steel uncontrolled (Supports for ASME Class 1, 2, and 3 piping and components) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Water Chemistry Control -Primary and Secondary ISl-IWF Loss of material ISl-IWF Loss of material 8oricAcid Corrosion None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-4 3.5.1-95 c 111.83.TP-4 111.81.1.TP-10 3.5.1-90 c 111.81.1.TP-226 3.5.1-81 A 111.81 .2.TP-226 111.81.1.T-25 3.5.1-89 A 111.81 .2.T-25 111.81 .1.TP-8 3.5.1-95 A 111.81 .2.TP-8 Page 3.5-87 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material High strength SNS, SRE, Stainless structural bolting SSR steel (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Carbon steel structural bolting SSR Stainless (Supports for ASME steel Class 1, 2, and 3 piping and components) Structural bolting; SNS, SRE, Carbon steel Structural steel and SSR miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management
Environment Management Programs Air with borated None None water leakage Air-indoor Loss of preload ISl-IWF uncontrolled or Air with borated water leakage Air-indoor Loss of material Structures uncontrolled Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-4 3.5.1-95 A 111.81 .2.TP-4 111.81 .1.TP-229 3.5.1-87 A 111.81 .2.TP-229 lll.A1.TP-248 3.5.1-80 A II l.A3. TP-248 lll.A4.TP-248 lll.A5.TP-248 Page 3.5-88 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Structural bolting; SNS, SRE, Carbon steel Air -outdoor Structural steel and SSR miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, Structural bolting; SNS, SRE, Carbon steel Air with borated Structural steel and SSR water leakage miscellaneous steel connections, including high strength bolting _/ (decking, grating, handrails, ladders, : platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring . Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 111.85.T-25 3.5.1-89 c Page 3.5-89 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Structural bolting; SNS, SRE, Galvanized Structural steel and SSR steel miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) Structural bolting; SNS, SRE, Galvanized Structural steel and SSR steel miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Environment Management Programs Air-indoor None None uncontrolled Air -outdoor Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.85.TP-8 3.5.1-95 c lll.A1.TP-274 3.5.1-82 A 111.A3.TP-274 lll.A4.TP-274 111.A5.TP-274 Page 3.5-90 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Structural bolting; SNS, SRE, Galvanized Air with borated Structural steel and SSR steel water leakage miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) Structural bolting SNS, SRE, Carbon steel Air-indoor SSR uncontrolled Structural bolting SNS, SRE, Carbon steel Air-indoor SSR uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring *Management Management Programs Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring Loss of material ISl-IWF Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.85.TP-3 3.5.1-89 c II I.A 1.TP-248 3.5.1-80 A lll.A3.TP-248 II l.A4. TP-248 lll.A5.TP-248 111.82.TP-248 111.83.TP-248 111.84.TP-248 111. 85. TP-248 111.81.1.TP-226 3.5.1-81 A 111.81 .2.TP-226 Page 3.5-91 Table 3.5.2-4: Bulk Commodities Aging Effect Intended Requiring Component Type Function Material Environment Management Structural bolting SNS, SRE, Carbon steel Air -outdoor Loss of material SSR Structural bolting SNS, SRE, Carbon steel Air -outdoor Loss of material SSR Structural bolting SRE, SSR Carbon steel Air -outdoor Loss of material Structural bolting SNS, SRE, Carbon steel Air with borated Loss of material SSR water leakage Structural bolting SNS, SRE, Galvanized Air-indoor None SSR steel uncontrolled 3.0 Aging Management Review Results Aging Management Programs Structures Monitoring Structures Monitoring ISl-IWF 8oricAcid Corrosion None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 II I.AS. TP-27 4 111.82.TP-274 111.83.TP-274 111.84.TP-274 111.85.TP-274 lll.A6.TP-221 3.5.1-83 E 111.81 .1.TP-235 3.5.1-86 A 111.81 .2.TP-235 111.81 .1.T-25 3.5.1-89 c 111.81 .2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 111.81 .1.TP-8 3.5.1-95 c 111.81.2.TP-8 111.82.TP-8 111.83.TP-8 111:84.TP-8 111.85.TP-8 Page 3.5-92 Table 3.5.2-4: Bulk Commodities Aging Effect Intended Requiring Component Type Function Material Environment Management Structural bolting SNS, SRE, Galvanized Air -outdoor Loss of material SSR steel Structural bolting SRE, SSR Galvanized Air -outdoor Loss of material steel Structural bolting SRE, SSR Galvanized Air with borated Loss of material steel water leakage Structural bolting SRE, SSR Stainless Air-indoor None steel uncontrolled Structural bolting SNS, SRE, Stainless Air -outdoor Loss of material SSR steel Structural bolting SRE, SSR Stainless Air -outdoor Loss of material steel 3.0 Aging Management Review Results Aging Management Programs Structures Monitoring ISl-IWF Boric Acid Corrosion None Structures Monitoring ISl-IWF Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A I 11.A3. TP-27 4 II l:A4. TP-27 4 lll.A5.TP-274 111.82.TP-274 111.83.TP-274 111.84.TP-274 111.85.TP-274 111.81 .1.TP-235 3.5.1-86 A 111.81 .2.TP-235 111.81.1.TP-3 3.5.1-89 c 111.81-2.TP-3 111.82.TP-3 111.83.TP-3 111.84.TP-3 111.85.TP-3 111.81 .1.TP-8 3.5.1-95 c 111.81 .2.TP-8 111.82.TP-8 111.83.TP-8 111.82.TP-6 3.5.1-93 A 111.84.TP-6 111.82.TP-6 3.5.1-93 E Page 3.5-93 Table 3.5.2-4: Bulk Commodities Intended Component Type
Function Material Environment Structural bolting SRE, SSR Stainless Air with borated steel water leakage Structural bolting SNS, SRE, Carbon steel, Air-indoor SSR Stainless uncontrolled or steel, Air -outdoor or Galvanized Air with borated steel water leak_age Structural bolting SNS, SRE, *Carbon steel, Air-indoor SSR Stainless uncontrolled or steel, Air -outdoor or Galvanized Air with borated steel water leakage Building concrete at SNS, SRE, Concrete Air-indoor locations of SSR uncontrolled or expansion and Air -outdoor grouted anchors; grout pads for ,_ suppor:t base plates Equipment pads/ SNS, SRE, Concrete Air-indoor foundations SSR uncontrolled or Air -outdoor* 3.0 Aging Management Review Results Aging Effect Aging.* Requiring Management
Management Programs None -None Loss of preload Structures Monitoring _Loss of preload ISl-IWF Reduction in Structures concrete anchor Monitoring *.capacity Cracking, loss of Structures bond, and loss of-Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-4 3.5.1-95 c 111.81.2.TP:..4 111.82.TP-4 111.83.TP-4 111.A1.TP-261 3.5.1-88 A lll.A4.TP-261 lll.A5.TP-261 111.83.TP-261-111.85.TP-261 111.81 .1. TP-229 3.5.1-87 A 111.81 .2.TP-229 . -* 111.81 .1.TP-42 3.5.1-55 A 111.81 .2. TP-42 111.82.TP-42 111.83.TP-42 111.84.TP-42 ' -111.BS.TP-42 .. lll.A1.TP'-26 A lll.A3.TP-26 I I I .A4.TP-26 lll.A5.TP-26 'Page 3.5-94 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Equipment pads/ SNS, SRE, Concrete Air-indoor foundations
SSR uncontrolled or Air -outdoor Equipment pads/ SNS, SRE, Concrete Air-indoor foundations SSR uncontrolled or Air -outdoor Curbs FLB, Concrete Air-indoor SNS,SRE uncontrolled Curbs FLB, SNS, Concrete Air-indoor SRE uncontrolled Curbs FLB, SNS, Concrete Air -: indoor . SRE uncontrolled Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs .Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 111.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 lll.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A lll.A3.TP-25 3.5.1-54 A Ill.A 1.TP-26 3.5.1-66 A lll.A3.TP-26 lll.A4.TP-26 lll.A5.TP-26 Page 3.5-95 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor Manways, hatches, FB Concrete Air-indoor manhole covers and uncontrolled hatch covers Manways, hatches, FB Concrete Air-indoor manhole covers and uncontrolled hatch covers Manways, hatches, FB Concrete Air -outdoor manhole covers and hatch covers Manways, hatches, FB Concrete Air -outdoor manhole covers and hatch covers Missile shields MB Concrete Air-indoor uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking Fire Protection Structures Monitoring Cracking. loss of Fire Protection material Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1. TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 lll.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 Vll.G.A-91 3.3.1-62 A Vll.G.A-90 3.3.1-60 A Vll.G.A-92 3.3.1-61 A Vll.G.A-93 3.3.1-62 A 111.A?.TP-26 3.5.1-66 *A Page 3.5-96 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Missile shields MB Concrete Air-indoor uncontrolled Missile shields MB Concrete Air-indoor uncontrolled Structural fire FB Concrete Air-indoor barriers; walls, Uncontrolled ceilings, floor slabs, curbs, dikes Structural fire FB Concrete Air-indoor barriers; walls, Uncontrolled ceilings, floor slabs, curbs, dikes Structural fire FB Concrete Air -outdoor barriers; walls, ceilings, floor slabs, curbs, dikes Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking -Fire Protection Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking, loss of Fire Protection material Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.A?.TP-28 3.5.1-67 A 111.A?.TP-25 3.5.1-54 A Vll.G.A-90 3.3.1-60 A VILG.A-91 3.3.1-62 A Vll.G.A-92 3.3.1-61 A lll.A1.TP-26 3.5.1-66 A lll.A3.TP-26 lll.A4.TP-26 lll.A5.TP-26 Page 3.5-97 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Mate.rial Environment Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor Compressible joints SNS, SSR Elastomers Air-indoor and seals uncontrolled or Air -outdoor Compressible joints SNS, SSR Elastomers Exposed to fluid and seals environment Fire stops FB Cerablanket, Air-indoor kaowool uncontrolled blanket, HEMYC, Siltemp fibersil cloth, Thermo-lag, elastomers 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Loss of material, Fire Protection Change in material properties, Cracking/ delamination, separation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1.TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 lll.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 lll.A6.TP-7 3.5.1-72 A lll.A6.TP-7 3.5.1-72 A j Page 3.5-98 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Fire wrap FB Cera blanket, Air-indoor Kaowool uncontrolled blanket, HEMYC, Siltemp fibersil cloth, Silicone elastomers, Thermo-lag, elastomers Insulation (includes SNS Fiberglass, Air-indoor jacketing, wire mesh, . calcium uncontrolled tie wires, straps, silicate clips) Insulation (includes IN Fiberglass, Air-indoor jacketing, wire mesh, calcium uncontrolled tie wires, straps, silicate clips) Insulation (includes SNS Aluminum Air-indoor jacketing, wire mesh, uncontrolled tie wires, straps, clips) Insulation (includes SNS Aluminum Air with borated jacketing, wire mesh, water leakage tie wires, straps, clips) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material, Fire Protection Change in material properties, Cracking/ delamination, separation Loss of material, Structures Change in material Monitoring properties Reduced thermal External Surfaces insulation Monitoring resistance None* None Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item . Item Notes J J Vlll.S-401 3.4.1-64 A .. Vll.J.AP-36 3.3.1-113 c 111.82.TP-3 3.5.1-89 c Page 3.5-99 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Insulation (includes SNS Stainless Air-indoor jacketing, wire mesh, steel uncontrolled tie wires, straps, clips) Insulation (includes IN, SNS Stainless Air with borated jacketing, wire mesh, steel water leakage tie wires, straps, clips) Penetration seals FB Elastomers Air-indoor uncontrolled Penetration seals EN, FLB, Elastomers Air-indoor PB, SNS uncontrolled or Air -outdoor Roof membranes EN, SNS Elastomers Air -outdoor Seals and gaskets FLB, PB,
Elastomers Air-indoor (doors, manways SSR uncontrolled or and hatches) Air -outdoor Vibration isolators SNS, SSR Elastomers Air-indoor uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring . Management Management Programs None None None None Increased Fire Protection hardness, shrinkage, loss of strength Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Reduction or loss Structures of isolation function Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-17 3.3.1-120 c lll.B2.TP-4 3.5.1-95 c VII G.A-19 3.3.1-57 A lll.A6.TP-7 3.5.1-72 A lll.A6.TP-7 3.5.1-72 c lll.A6.TP-7 3.5.1-724 A lll.B4.TP-44 3.5.1-94 E Page 3.5-100 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.6 ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.1 Introduction This section provides the results of the aging management review for WF3 electrical components which were subject to aging management review. Consistent with the methods described in NEI 95-10, the electrical and l&C aging management reviews focus on commodity groups rather than systems. As discussed in Section 2.5, the following electrical commodity groups requiring aging management review are addressed in this section.
High-voltage insulators
Non-EQ insulated cables and connections -Cable connections (metallic parts) -Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements -Electrical cables not subject to 1 O CFR 50.49 EQ requirements used in instrumentation circuits -Fuse holders (insulation material) -Inaccessible 400 V) cables (e.g., installed underground in conduit, duct bank or direct buried) not subject to 1 O CFR 50.49 EQ requirements
Metal-enclosed bus
Switchyard bus and connections
Transmission conductors and connections Table 3.6.1, Summary of Aging Management Programs for Electrical Components Evaluated in Chapter VI of NUREG-1801, provides the summary of the aging management reviews, and the programs evaluated in NUREG-1801 for the electrical and l&C components. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program* evaluations in Appendix B.
3.6.2 Results Table 3.6.2-1, Electrical and l&C Components-Summary of Aging Management Evaluation, summarizes the results of aging management reviews and the NUREG-1801 comparison for electrical and l&C components. 3.6.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The* following sections list the materials, environments, aging effects requiring management, and aging management programs for electrical and l&C components subject to aging management review. Programs are described in Appendix B. Further details are provided in Table 3.6.2-1. 3.0 Aging Management Review Results Page 3.6-1 Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Electrical and l&C components subject to aging management review are constructed of the following materials.
Aluminum
Copper
Cement
Elastomers
Galvanized metals (including steel)
Insulation material -various organic polymers
Porcelain
Steel and steel alloys
Stainless steel
Various metals used for bus and electrical connections Environments Electrical and l&C components subject to aging management review are exposed to the following environments. * *
*
Air -indoor controlled Air -indoor uncontrolled Air -outdoor Air with borated water leakage Heat, moisture, or radiation and air Significant moisture Aging Effects Requiring Management The following aging effects associated with electrical and l&C components require management. * * * *
Change in material properties Increased resistance of connection Increased resistance of connection due to corrosion of connector contact surfaces caused by intrusion of borated water Loss of material Reduced insulation resistance (IR) 3.0 Aging Management Review Results Page 3.6-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs The following aging management programs will manage the effects of aging on electrical and l&C components.
Boric Acid Corrosion
Metal Enclosed Bus Inspection
Non-EQ Electrical Cable Connections
Non-EQ lnaccessi.ble. Power Gables (2'.. 400 \/) *
Non-EQ Insulated Cables and Connections
Non-EQ Sensitive.Instrumentation Circuits Test.Review 3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 indicates that further evaluation*is necessary for certain aging effects and other issues. Section of NUREG-1800 discusses these aging effects and other issues that require further evaluation. The following sections, corresponding to the in NUREG-1800, explain the WF3 approach to these areas requiring further evaluation. Programs are described in Appendix B. of this application.
3.6.2.2.1 *Electrical Equipment Subject to Environmental Qualification Electrical equipment environmental qualification (EQ) analyses may be TLAAs as defined in 10 CFR 54.3: TLAAs are evaluated in accordance with 10 CFR54.21(c). The evaluation of EC:l' TLAAs are addressed in Sectiort4.4 .. EQ components are subject to replacem*ent based on a qualified life. Therefore, in accordance with 10 CFR 54.21(a)(1)(ii), EQ components are not subject to aging management review. 3.6.2.2.2 Degradation of Insulator Quality due to Presence of Any Salt Deposits and Surface Contamination, and Loss of Material due to Mechanical Wear The discussion in NUREG-1800 concerns effects of these aging mechanisms ori high voltage insulators .. High voltage insulators are subject to aging management review if they are necessary for the alternate AC (AAC) source for SBO, or recovery of offsite power following an SBO. Other high voltage insulators are not subject to aging management review since they do not perform a license* renewal intended function. The high voltage insulators evaluated for WF3 license renewal are those used to support uninsulated, high-voltage electrical components such as transmission conductors and switchyard buses that are in the scope of license renewal. Various airborne materials such as dust, salt and industrial effluents can contaminate insulator surfaces. The buildup of surface contamination is gradual and in most areas washed away by rain. The glazed insulator surface aids this contamination removal. . 3.o Aging Management Review Results Page 3.6-3 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information A large buildup of contamination enables the conductor voltage to track along the surface more easily and can lead to insulator flashover.
Surface contamination can be a problem in. c;ireas where there are greater. concentrations of airborne particles such as near facilities that discharge soot or near the seacoast where salt spray is prevalent. WF3 is located near the seacoast and
near other sources of airborne particles. However, salt spray buildup is a short-term concern based on local weather conditions (event-driven). Flashover due to salt contamination of insulators is caused .by events, typically storms, regardless of the age of the insulators. This is clearly*not an effect of aging. Surfa.ce contamination is not an applicable aging mechanism for high-voltage insulators at WF3; however,* because of the significance of this event, system walkdowns are performed periodically to do a visual inspection of the swjtchyard high-voltage insulators that are in-scope of license renewal. Therefore, reduced insulation resistance due to surface* contamination is n9t an applicable aging effect for high-voltage insulators at WF3. Loss of material due to mechanical wear is a potential aging effect for strain and suspension insulators subject to movement. Although this aging effect is possible, .industry experience has shown transmission conductors do not normally swing and when subjected to a substantial wind, movement.will*subside after a short period. Wear has not been apparent during routine inspections and is not a credible aging effect.
Wind loading could cause transmission conductor vibration or sway. Wind loading
that can cause a transmission line and insulators to vibrate is considered in the design and.installation of transmission conductors at WF3. Loss of material (wear) and fatigue that cot.lid be caused by transmission conductor vibration or sway are not applicable aging effects in that they would not cause a loss of intended function if left unmanaged for the period of extended operation. There are no aging effects requiring management for WF3 high-voltage insulators. 3.6.2.2.3 Loss of Material due to Wind Induced Abrasion and Fatigue. Loss of Conductor Strength due to Corrosion. and Increased Resistance of Connection due to Oxidation or Loss of Pre-load
Transmission conductors are uninsulated, stranded electrical cables used outside buildings in high voltage applications. The transmission conductor commodity group includes the associated fastening hardware but excludes the high-voltage insulators. Major active equipment assemblies include their associated transmission conductor terminations. Transmission conductors are subject to aging management review if they are necessary for recovery of offsite power following an SBO. At WF3, transmission conductors from the WF3 230 kV switchyard to the startup transformers (3A and 38) support recovery from an SBO. Other transmission conductors are not subject to 3.0 Aging Management Review Results Page 3.6-4*

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information aging management review since they do not perform a license renewal intended function. Switchyard bus is uninsulated, un-enclosed, rigid electrical conductors used in medium-and high-voltage applications. Switchyard bus includes the hardware used to secure the bus to high-voltage insulators. Switchyard bus establishes electrical connections to disconnect switches, switchyard breakers, and transformers. Switchyard bus is subject to aging management review if it is necessary for recovery of offsite power following an SBO. *At WF3, switchyard bus from the 230 kV -switchyard breakers to the 230 kV transmission conductors support recovery from an SBO. Other switchyard bus does not require aging management review !;ince it does* not perform a license renewal intended function. Loss of Material due to Wind Induced Abrasion and Fatigue Wind loading could cause transmission conductor vibration or sway. Wind loading that can cause a transmission line and insulators to vibrate is considered in the

design ahd installation' of transmission conductors at WF3. Loss of material (wear) and fatigue that .could be caused by transmission conducfor vibration or sway are not applicable-aging effects in that they would not *cause"a*loss of intended function if left unmanaged for the period of extended operation.* Switchyard bus is connected to active equipment by short sections of flexible conductors that the rigid bus does not normally vibrate, since it is supported by insulators and ultimately by static, structu*ral such as concrete footings and structural steel. Vibration issues occur early in plant life and as a *result of inadequate design, installation, or maintenance. The flexible conductors withstand the minor vibrations associated with the active switchyard components. Flexible conductors are part of the switchyard bus commodity group. Vibration is not applicable since flexible connectors connecting switchyard bus fo active components eliminate potential for vibration. .* A review of industry operating experience and NRC generic communications related to the aging of transmission conductors ensu.red that iio additional aging effects exist beyond those previously identified. A-review of plant-specific operating experience di_d not identify any unique aging effects for transmission conductors. . -Therefore, loss of material due to wear of transmission conductors is not an aging effect requiring management-at WF3. Therefore, loss of m*aterial due to wear-of switchyard bus is not an aging effect requiring management at WF3.
3.0 Aging Management Review Results Page 3.6-5
Loss of Conductor Strength due to Corrosion ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The aging effeqt loss of conductor strength (corrosion) applies to aluminum conductor steel reinforced (ACSR) transmission conductors. The most prevalent mechanism contributing to loss of conductor strength .of an ACSR transmission conductor is corrosion, which includes corrosion of the steel core and aluminum strand. pitting. For ACSR transmission conductors, degradation begins as a loss of zinc from the galvanized steel core wires. WF3 ACSR conductors are susceptible to environmental influences, such as sulfur dioxide (S02) concentration in the air. When the steel core of an ACSR conductor loses its galvanjze.d co*ating, it wi!I continually corrode causing a in ultimate strength.
Corrosion in ACSR conductors is a very slow acting mechanism, and the corrosion rates depend largely on air quality, which includes suspended particles chemistry, 802 concentration in air, precipitation, fog chemistry and meteorological conditions .. perforr:ned by Ontario Hydroe[ectric showed a 30 percent loss of composite conductor strength of an 80-year-old ACSR conductor due to corrosion. The License Renewal Electrical_ Handbook (LREH) makes statements relative to transmission -_conductor a,ged strengths based upon testi_ng performed Ontario Hydro. This specific conductor construction type at WF3 was included in the Ontario *.Hydroelectric test so the results of this test are representativ_e* of the WF3 230 kV condu9tors. The 336.4 thousand circular mils (MCM) 26/7 ACSR transmission
identified in the .Ontario Hydro electric test, as documented in the companion paper, "Aged ACSR Conductors, Part II-Prediction of Remaining Life," bounds the WF3, transmissio11 conductors. The example presented in LREH
compares a 410 ACSR conductor to the Ontario Hydroelectric Study. The same-comparison method is made here for.the WF3 transmission conductors. There is a set percentage of composite c*onductor strength established at which a trans_missiori conductor is repiaced. As illustrated below, there is ample strength :margin to maintain the WF3 transmissio_n conductor intended function through the of extended operation.
The National Electrical Safety Code (N.ESC) requires that tension on inst.ailed conductors be a maximum of 60 percent of the ultimate conductor strength. _The NESC.also sets the maximum tension a conductor must be designed to withstand under heavy load requirements; which includes consideration of ice, wind and temperature. These requirements are reviewed concerning the specific conductors included in this The fo.llowing evaluation of the conductor type with the smallest ultimate strength margin (4/0 ACSR) in the NESC illustrates the conservative nature of the design of WF3 transmission conductors required for offsite power recovery. 3.0 Aging Management Review Results Page 3.6-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The ultimate strength and the NESC heavy load tension requirements of 410 ACSR are 8350 lbs. and 2761 lbs. respectively. The margin between the NESC Heavy Load and the ultimate strength is 5589 lb.; i.e., there is a 67 percent of ultimate strength margin. The Ontario Hydroelectric study showed a 30 percent loss of composite conductor strength in an 80-year-old conductor. In the case of the 4/0 ACSR transmission conductors, a 30 percent loss of ultimate strength would mean that there would still be a 37 percent ultimate strength margin between what is required by the . NESC and the actual conductor strength. The 4/0 ACSR conductor type has the lowest initial design margin of transmission conductors included in the AMR. This illustrates with reasonable assurance that transmission conduetors will have ample strength through the period of extended operation. A review of industry operating experience and NRC generic communications related to the aging of transmission conductors ensured that no additional aging effects exist beyond those identified. A review of plant-specific operating experience did not identify any unique aging effects for transmission conductors:
Therefore, loss of conductor strength is not an aging effect requiring management for transmission conductors. Increased Resistance of Connection due to Oxidation Corrosion due to surface oxidation for aluminum switchyard bus and connections are not applicable since switchyard bus connections requiring AMR are welded connections. However, the flexible conductors, which are welded to the switchyard bus, are bolted to the other switchyard com*ponents. These* steel and steel:-alloy switchyard component connections are included in the infrared inspection of the 230 kV switchyard connections, which verifies the* effectiveness of the connection design and installation practices. WF3 performs infrared inspections of the 230 kV switchyard connections and transformer yard connections to verify the integrity of the connections at least once a year. This inspection and the absence of plant-specific operating experience verifies that this aging effect is not significant for WF3. Increased connection resistance due to surface oxidation is a potential aging mechanism, but is not significant enough to cause a loss of intended function. The aluminum, and steel alloy components in the switchyard are exposed to precipitation, . but these components do not experience aging effects in this environment, except for *minor oxidation, which does not affect the ability of the connections to perform their intended function. At WF3, switchyard connection surfaces are coated with an oxidant compound (i.e., a grease-type sealant) prior to tightening the connection to
prevent the formation of oxides on the metal surface and to prevent moisture from entering the connections thus reducing the chances of corrosion. Based on operating experience (WF3 and the industry), this method of installation provides a resistant low electrical resistance connection. In addition, the infrared inspection of the 230 kV switchyard verifies that this aging effect is not-significant for WF3. This 3.0 Aging Management Review Results Page 3.6-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information discussion .is applicable for bolted connections of transmission conductors and switchyard bus.
Therefore, increased connection resistance due to general corrosion resulting from oxidation of switchyard connection metal surfaces is not an aging effect requiring management at WF3. Increased Resistance of Connection due to Loss of Pre-load Increased connection resistance due to loss of pre-load (torque relaxation) for switchyard connections is not an aging effect requiring management. The LREH does not list this as an applicable aging effect. The design of the transmission conductor bolted connections precludes torque relaxation as confirmed by specific operating experience. The WF3 operating experience report did not identify any failures of switchyarc;t connections. The design of switchyard bolted connections includes Bellville washers and an anti-oxidant compound (no-ox grease). The type of bolting plate and the use of Bellville washers is the industry standard to preclude torque relaxation. This combined with. the proper sizing of the conductors eliminates the need to consider this aging mechanism; therefore, increased connection resistance due to loss of pre-load is not an aging effect requiring management. This discussion is applicable for bolted connections of transmission conductors and switchyard bus. In-scope transmission conductors at WF3 are to the connections from the 230 kV switchyard to *Startup Transformers 3A and 3B for the off-site pc;>wer recovery paths. WF3 performs infrared inspection of the 230 kV.switchyard connections as part of a repetitive preventive maintenance task to verify the integrity of the connections. These routine inspections and the absence of plant-specific operating experience verifies that this aging effect is not significant for WF3. Based on this information, incr:eased connection resistance due to loss of pre-load of .transmission conductor and switchyard bus connections is not an aging effect requiring management for WF3. . . . There are no applicable aging effects that could cause loss of the intended function of the transmission conductors for the period of extended operation. There are no aging effects requiring management .tor WF3 transmission conductors. and switchyard bus connections. 3.6.2.2.4 Quality Assurance for Aging Management of Nonsafety-Related Components
See Appendix B Section B.0.3 for discussion of WF3 quality assurance procedures
and administrative controls for aging management programs. 3.0 Aging Management Review Results Page 3.6-8 3.6.2.2.5 Ongoing Review of Operating Experience Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information See Appendix B Section B.0.4 for discussion of WF3 operating experience revieVI.'. programs. 3.6.2.3 Time-Limited Aging Analysis The only TLAAs identified for the *electrical and l&C commodity componen_ts are evaluations for environmental qualification (EQ) associated with 1 o* CFR 50.49. The EQ TLAAs are evaluated in Section 4.4. 3.6.3 Conclusion Electrical and l&C components that are subject to aging management review have been identified in accordance with the requirements of 10 CFR 54.21 (a)(1 ). Aging management programs selected to manage aging effects for the electrical and l&C components are identified in Section 3.6.2.1 and in the followingJables. A description of aging management programs is provided in Appendix B of this application, along with the demonstration that the aging effects will. be managed for the period of extended operation. Based on the demonstrations provided in Appendix B, the effects of aging associated with electrical and l&C components will be managed such that there is reasonable assurance the* intended0functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.6-9 Table' 3.6.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical. Information Summary .of Aging Management Programs for the EiC Components Evaluated in Chapter VI of NUREG-1801 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-1 Electrical equipment Various aging effects .subject to 1 o CFR 50.49 due to various EQ requirements mechanisms in composed of various accordance with polymeric and metallic 10CFR 50.49 materials exposed to adverse localized environment caused by heat, radiation, o><Ygen, moisture, or voltage .. 3.0 Aging Management Review Results Aging Management Programs EQ is a time-limited aging analysis (TLM) to be evaluated for the period of extended operation. See the Standard Review Plan, Section 4.4, "Environmental Qualification (EQ) of Electrical Equipment," for acceptable methods for meeting the requirements of 10 CFR54.21(c)(1)(i)
and (ii). l See Chapter X.E1, "Environmental Qualification (EQ) of Electric Components, of this report for meeting the requirements of 10 CFR 54.21 (c)(1 )(iii). J Further Evaluation Recommended Discussion Yes, TLAA EQ equipment is not subject to aging management review because the equipment is subject to replacement based on a qualified life. EQ analyses are evaluated as potential TLMs in Section 4.4. See Section 3.6.2.2.1 for further evaluation. Page 3.6-10 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-2 High-voltage insulators Loss of material due to composed of porcelain; mechanical wear malleable iron; aluminum; caused by wind galvanized steel; cement *blowing on exposed to air -outdoor transmission conductors 3.6.1-3 High-voltage insulators Reduced insulation composed of porcelain; resistance due to malleable iron; aluminum; presence of salt galvanized steel; cement deposits or surface exposed to air -outdoor contamination 3.6.1-4 Transmission conductors Loss of conductor composed of aluminum; strength due to steel exposed to air -corrosion outdoor ' 3.6.1-5 Transmission connectors Increased resistance of composed of aluminum; connection due to steel exposed to air -oxidation or loss of pre-outdoor .. load 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated A plant-specific aging management program is to be evaluated for plants located such that the potential exists for salt
deposits or surface contamination (e.g., in the vicinity of salt water bodies or industrial pollution) A plant-specific aging management program is to be evaluated for ACSR A plant-specific aging management program is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant specific NUREG-1801 aging effects are not applicable td WF3. See Section 3.6.2.2.2 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.2 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Page 3.6-11 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-6 Switchyard bus and of material due to connections composed of wind-induced abrasion; aluminum; copper; Increased resistance of bronze; stainless steel; connection due to galvanized steel exposed oxidation or loss of pre-to air -outdoor load 3.6.1-7 Transmission conductors Loss of material due to composed of aluminum; wind-induced abrasion steel exposed to air -outdoor 3.6.1-8 Insulation material for Reduced insulation electrical cables and resistance due to -connections (including thermal/ therm oxidative terminal blocks, fuse degradation of holders, etc.) Qomposed organics, radiolysis, of various organic and photolysis (UV polymers (e.g., EPR, SR, sensitive materials EPDM, XLPE) exposed to only) of organics; adverse localized radiation-induced environment caused by . oxidation; moisture heat, radiation, or intrusion moisture 3.0 Aging Management Review Results Aging. Management Programs A plant-specific aging management program is to be evaluated A plant-specific aging management program is to be evaluated for AGAR andACSR Chapter Xl.E1, "Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaiuation. No Consistent with NUREG-1801. The Non-EQ Insulated Cables and Connections Program will manage the effects of aging. This program includes inspection of non-EQ electrical and l&C
penetration cables and conn*ections. WF3 EQ electrical and l&C penetration assemblies are covered under the program. Page 3.6-12 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-9 Insulation material for Reduced insulation electrical cables and resistance due to connections used in thermal/ thermoxidative instrumentation circuits degradation of that are sensitive to organics, radiolysis, reduction in conductor and photolysis (UV insulation resistance (IR) sensitive materials composed of various only) of organics; organic polymers (e.g., radiation-induced EPR, SR, EPDM, XLPE) oxidation; moisture exposed to adverse intrusion localized environment caused by heat, radiation, or moisture 3.6.1-10 Conductor insulation for Reduced insulation inaccessible power resistance due to cables greater than or moisture equal to 400 volts (e.g., installed in conduit or direct buried) composed of various organic polymers (e.g., EPR, SR, EPDM, XLPE) exposed to adverse localized environment caused by significant moisture 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.E2, "Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits" Chapter Xl.E3, "Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Non-EQ Sensitive Instrumentation Circuits Test Review Program will manage the effects of aging. This program includes review of calibration results or surveillance findings for instrumentation circuits. No Consistent with NUREG-1801. The Non-EQ Inaccessible Power Cables (;::: 400 V) Program will manage the effects of aging. This program includes inspection and testing of power cables exposed to significant moisture as required. Page 3.6-13 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-11 Metal enclosed bus: cracking, enclosure assemblies crazing, scuffing, composed of elastomers dimensional change exposed to air -indoor, * (e.g. "ballooning" and controlled or uncontrolled "necking"), shrinkage, or air -outdoor discoloration,* hardening and loss of strength due to elastomer degradation 3.6.1-12 Metal enclosed bus: bus/ Increased resistance of connections composed of connection due to the various metals used for loosening -of bolts electrical bus and caused by thermal connections exposed to cycling and ohmic air -indoor, controlled. or heating uncontrolled or air -outdoor 3.6.1-13 Metal enclosed bus: Reduced insulation insulation; insulators resistance due to composed of porcelain; thermal/thermoxidative xenoy; degradation of . organic polymers organics/ exposed to air -indoor, thermoplastics, controlled or uncontrolled radiation-induced or air -outdoor oxidation, moisture/ debris intrusion, and ohmic heating 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.E4, "Metal
Enclosed Bus," or Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.E4, "Metal Enclosed Bus" .. Chapter Xl.E4, "Metal Enclosed Bus" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Metal. Enclosed Bus Inspection Program will manage the effects of aging. This program includes elastomers associated with flexible boots. No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of interior portions of bus. No Consistent with NUREG-1801. The. Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of interior portions of the bus. Page 3.6-14 Table 3.6.1: EiC Components . Item Aging Effect/ Number Component Mechanism 3.6.1-14 Metal enclosed bus: Loss of material due to external surface of general, pitting, and enclosure assemblies crevice corrosion composed of steel exposed to air -indoor, uncontrolled or air -outdoor 3.6.1-15 Metal enclosed bus: Loss of material due to external surface of pitting and crevice enclosure assemblies corrosion composed of galvanized steel; aluminum exposed to air -outdoor 3.0 Aging Management Review Results \ 5 J Aging Management Programs Chapter Xl.E4, "Metal Enclosed Bus," or Chapter Xl.S6, "Structures Monitoring" Chapter Xl.E4, "Metal Enclosed Bus," or Chapter Xl.S6, "Structures Monitoring" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of exterior portions of the bus. No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of exterior portions of the bus. Page 3.6-15 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-16 Fuse holders (not part of Increased resistance of active equipment): connection due to metallic clamps chemical composed of various contamination, metals used for electrical corrosion, and connections exposed to oxidation (in an air, air -indoor, uncontrolled indoor controlled environment, increased resistance of connection due to chemical contamination, corrosion and oxidation do not apply); fatigue due to ohmic heating, thermal cycling, electrical transients 3.0 Aging Management Review.Results Aging Management Programs Chapter XI.ES, "Fuse Holders" ' Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No NUREG-1801 aging effects are not applicable to WF3. A review of WF3 documentation indicated that fuse holders utilizing metallic clamps are either located in circuits that perform no license renewal intended function, or part of an active component. Therefore, fuse holders with metallic clamps at WF3 are not subject to aging management review, and do not have aging effects that require an aging management program. Page 3.6-16 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-17 Fuse holders (not part of Increased resistance of active equipment): connection due to metallic clamps fatigue caused by composed of various frequent manipulation metals used for electrical or vibration connections exposed to air -indoor, controlled or uncontrolled 3.6.1-18 Cable connections Increased resistance of (metallic parts) composed connection due to of various metals used for thermal cycling, ohmic electrical contacts heating, electrical to air -indoor, transients, vibration, controlled or uncontrolled chemical or air -outdoor contamination, corrosion, and oxidation 3.0 Aging Management Review Results Aging Management Programs Chapter XI.ES, "Fuse Holders" .No aging management program is required for those applicants who can demonstrate these fuse holders are located in an environment that does not subject them to environmental aging mechanisms or fatigue caused by frequent manipulation or vibration Chapter Xl.E6, "Electrical Cable Connections Not Subject to 10 CF.R 50.49 Environmental Qualification Requirements" Further Evaluation Waterford.Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No NUREG-1801 aging effects are not applicable to WF3. A review of WF3 documents indicated that fuse holders utilizing metallic clamps are either located in circuits that perform no license renewal intended function, or part of an active component. Therefore, fuse holders with metallic clamps at WF3 are not subject to aging management review, and do not have aging effects that require an aging management program. No Consistent with NUREG-1801. The one-time inspection program (Non-EQ Electrical Cable Connections) will verify the absence of aging effects requiring management. Page 3.6-17 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-19 Connector contacts for Increased resistance of electrical connectors connection due to exposed to borated water corrosion of connector leakage composed of contact surfaces Various metals used for caused by intrusion of electrical contacts borated water exposed to Air with borated water leakage 3.6.1-20 Transmission conductors Loss of conductor composed of aluminum strength due to exposed to air -outdoor corrosion 3.6.1-21 Fuse holders (not part of None a larger assembly): insulation material, metal . enclosed bus: external surface of enclosure assemblies composed of insulation material: bake lite;. phenolic melamine or ceramic; molded polycarbonate; other, galvanized steel; aluminum, steel exposed to air -indoor, controlled or uncontrolled 3.0 Aging Management Review Results .,-\.. Aging' Management Programs Chapter Xl.M10, "Boric Acid Corrosion" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Boric Acid Corrosion Program will manage the effects of aging. None -for Aluminum . No NUREG-1801 materi.al and aging Conductor Aluminum Alloy effects are not applicable to WF3. Reinforced (ACAR) None NA-NoAEM or Consistent with NUREG-1801. AMP ,. ' Page 3.6-18 r ( i \, ' ' '

Notes for Table 3.6.2-1 Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, agirig effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. 8. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 601. WF3 fuse holders with metallic fuse clips are either part of an active component or located in circuits that perform no license renewal intended function and thus are not subject to aging management review. Therefore, fuse holders (metallic clamp) at WF3 do not have aging effects that require an aging management program. 3.0 Aging Management Review Results Page 3.6-19 Table 3.6.2-1 Electrical and l&C Components Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.6.2-1 : Electrical and l&C Aging E.ffect . Aging Intended Requiring. Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Cable connections CE Various Air-indoor Increased Non-EQ Electrical Vl.A.LP-30 3.6.1-18 A (metallic parts) metals used* controlled or resistance of

Cable Connections Vl.A-1 for electrical uncontrolled or connection (LP-12) connections Air -outdoor Insulation material IN Insulation Heat, moisture, Reduced insulation Non-EQ Insulated Vl.A.LP-33 3.6.1-8 A for electrical._cables material-or radiation and resistance (IR) Cables and Vl.A-2 and connections various air Connections (L-01) (including terminal organic blocks, fuse holders, polymers etc.) not subject to 1 OCFR50.49 EQ requirements '. (includes non-EQ . electrical and l&C penetration conductors and connections) Insulation material IN Insulation Heat, moisture, Reduced insulation Non-EQ Sensitive VIALP-34 3.6.1-9 A for electrical cables material-or radiation and resistance (IR) Instrumentation Vl.A-3 not subject to 10 various air Circuits Test (L-02) CFR 50.49 EQ organic Review requirements used in polymers instrumentation circuits 3.0 Aging Management Review Results Page 3.6-20 /' /

Table 3.6.2-1 : Electrical and l&C Components -Intended Component Type Function Material Environment Fuse holders (not IN Insulation Air-indoor part of active material-controlled or equipment): various uncontrolled insulation material organic polymers Fuse holders (not CE Various Air-indoor part of active metals used controlled or equipment): metallic for electrical uncontrolled clamps connections Fuse holders (not CE Various Air-indoor part of active metals used controlled or equipment): metallic for electrical uncontrolled clamps connections High voltage IN Porcelain, Air -outdoor insulators (high galvanized voltage insulators for metal, cement SBO recovery) High voltage IN Porcelain, Air -outdoor insulators (high galvanized voltage insulators for metal, cement SBO recovery) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None < None None None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-24 3.6.1-21 A Vl.A-7 (LP-02) Vl.A.LP-31 3.6.1-17 I, 601 Vl.A-8 (LP-01) Vl.A.LP-23 3.6.1-16 I, 601 Vl.A-8 (LP-01) Vl.A.LP-32 3.6.1-2 I Vl.A-10 (LP-11) Vl.A.LP-28 3.6.1-3 I Vl.A-9 (LP-07) Page 3.6-21 \ Table 3.6.2-1: Electrical and l&C Components Intended Component Type Function Material Environment Conductor insulation IN Insulation Significant for inaccessible material-moisture power cables various 400 V) not subject organic to 10 CFR 50.49 EQ polymers; requirements paper and oil Metal enclosed bus: CE Various Air -indoor, bus/connections metals used controlled or for electrical uncontrolled or bus and Air -outdoor connections Metal enclosed bus: CE Elastomers Air -indoor, enclosure controlled or assemblies uncontrolled or Air -outdoor Metal enclosed bus: CE Galvanized Air -indoor, external surface of steel; controlled or enclosure aluminum uncontrolled assemblies Metal enclosed bus: CE Galvanized Air -outdoor external surface of steel; enclosure aluminum assemblies Metal enclosed bus: CE Steel Air -indoor, external surface of controlled enclosure assemblies 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Reduced insulation Non-EQ resistance (IR) Inaccessible Power Cables 400 V) Increased Metal Enclosed connection Bus Inspection resistance Change in material Metal Enclosed properties Bus Inspection None None Loss of material Metal Enclosed Bus Inspection None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-35 3.6.1-10 B Vl.A-4 (L-03) Vl.A.LP-25 3.6.1-12 A Vl.A.LP-29 3.6.1-11 A Vl.A.LP-41 3.6.1-21 A Vl.A.LP-42 3.6.1-15 A Vl.A.LP-44 3.6.1-21 A Page 3.6-22 Table 3.6.2-1: Electrical and l&C Components Intended Component Type Function Material Environment Metal enclosed bus: CE Steel Air -indoor, external surface of uncontrolled or enclosure Air -outdoor assemblies Metal enclosed bus: IN Porcelain; Air -indoor, insulation; insulators insulation controlled or material-uncontrolled or various Air -.outdoor organic polymers Switchyard bus and CE Aluminum, Air -outdoor connections steel, steel (switchyard bus for alloy SBO recovery) Transmission CE Aluminum Air -outdoor conductors (transmission conductors for SBO recovery) Transmission CE Aluminum Air -outdoor conductors (transmission conductors for SBO recovery) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Metal Enclosed Bus Inspection Reduced insulation Metal Enclosed resistance Bus Inspection None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-43 3.6.1-14 A Vl.A.LP-26 3.6.1-13 A Vl.A.LP-39 3.6.1-6 I Vl.A-15 (LP-9) --Vl.A.LP-46 3.6.1-4 c Vl.A-16 (LP-08) Vl.A.LP-47 3.6.1-7 I Vl.A-16 (LP-08) Page 3.6-23 Table 3.6.2-1 : Electrical and l&C Components Intended Component Type Function Material Environment Transmission CE Aluminum, Air -outdoor connectors steel, steel (transmission alloy connectors for SBO recovery) Connector contacts CE Various Air with borated for electrical metals used water leakage connector§ exposed for electrical to borated water contacts leakage 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Increased Boric Acid resistance of Corrosion connection due to corrosion bf connector contact surfaces caused by intrusion of borated water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A:LP-48 3.6.1-5 I Vl.A-16 (LP-08) Vl.A.LP-36 3.6.1-19 A Vl.A-5 (L-04) Page 3.6-24

r [ 4.0 TIME-LIMITED AGING ANALYSES Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of evaluations of time-limited aging analyses (TL,A.As) and exemptions based on a TLAA. This s.ection evaluates each identified TLAA in accordance with 10 CFR 54.21(c). Section 4.1 provides the 10 CFR Part 54 definition of TLAAs and requirements for evaluation of TLAAs and summarizes the process used for identifying .and evaluating TLAAs and exemptions. Subsequent sections of this chapter describe the evaluation of TLAAs within the following categories. *
Section 4.2, Reactor Vessel Neutron Embrittlement
Section 4.3, Metal Fatigue .
Section 4.4, Environmental Qualification (EQ) of Electric Equipment
Section 4.5, Concrete C.ontainment Tendon Prestress
Section 4.6, Containment Liner Plate, Metal Containments, and Penetrations Fatigue Analysis
Section 4.7, Other Plant-Specific TLAAs* References for Section 4 are provided in Section 4.8. 4.1* IDENTIFICATION OF TIME-LIMITED AGING ANALYSES Time-limited aging analyses are defined in 10 CFR 54.3. Time-limited aging analyses, for the purposes of this part, are those licensee calculations and analyses that: (1) Involve systems, structures, and components within the scope of license renewal, as delineated in § 54.4(a); * (2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, for example, 40 years; (4) Were determined to be relevant by the licensee in making a safety determination; * (S) Involve conclusions or provide the basis for conclusions related to the capability
of the system, structure, and component to perform its intended functions, as delineated in§ 54.4(b); and (6) Are contained or incorporated by reference in the CLB. 4.0 Time-Limited Aging Analyses Page 4.1-1 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Section 10 CFR 54.21(c) requires a list of TLAAs be included in an application for a renewed license. Section 10 CFR 54.21 (c)(2) requires a list of exemptions granted pursuant to 1 O CFR 50.12 that are based on a TLAA to be in the application for a renewed license. § 54.21 Contents of application -technical information. (c) An evaluation of time-limited aging analyses. (1) A list of time-limited aging analyses, as defined in§ 54.3, must be provided. The applicant shall demonstrate that-(i) The analyses remain valid for the period of extended operation; (ii) The analyses have been projected to the end of the period of extended operation; or (iii) The effects of aging on the intended function(s) will be adequately managed for the period of extended operation. (2) A list must be provided of plant-specific exemptions granted pursuant to 10 CFR 50.12 and in effect that are based on time-limited aging analyses as defined in § 54.3. The applicant shall provide an evaluation that justifies the continuation of these exemptions for the period of extended operation. 4.1.1 Identification of TLAAs The process for identifying time-limited aging analyses is consistent with the guidance provided in NEI 95-10 (Ref. 4-1). Calculations and analyses that potentially meet the definition of a TLAA in 10 CFR 54.3 were identified by searching current licensing basis documents including the following. -* Final Safety Analysis Report (FSAR)
Technical Specifications and Bases
Technical Requirements Manual *
Facility Operating License
Fire protection program documents
lnservice inspection procedures _
Relevant NRC safety evaluation reports (SERs)
Relevant Westinghouse Commercial Atomic Power reports (WCAPs)
Docketed licensing correspondence Industry documents that list generic TLAAs were also reviewed to provide additional assurance of the_ completeness of the identification of WF3 TLMs. These documents included NEI 95-1 O (Ref. 4-1); NUREG-1800 (Ref. 4-2); and EPRI Report TR-105090 (Ref. 4-4). Table 4.1-1 provides a summary listing of the TLAAs applicable to WF3. Table 4.1-2 provides a comparison of the WF3 TLAAs to the potential TLAAs identified in NUREG-1800. 4.0 Time-Limited Aging Analyses Page 4.1-2 )

4.1.2 Identification of Exemptions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Exemptions for WF3 were identified through a review of the FSAR, the operating license, the Technical Specifications, NRG SERs, ASME Section XI Program documentation, fire protection program documents, NRG Agencywide Documents Access and Management System (ADAMS) database, and docketed correspondence. There are no exemptions that were granted in accordance with 1 O GFR. 50 .12 that are based on a TLAA, regardless of whether the exemptions remain in effect for the period of extended operation. 4.0 Time-Limited Aging Analyses Page 4.1-3 TLAA Description Table 4.1-1 List of TLAAs **_Reactor Ve$$e1 Embrittlement Analy!;es Reactor vessel fluence Upper-shelf energy Pressurized thermal shock Pressure-temperature limits Low temperature overpressure protection (LTOP) setpoints . MetalFatigue , , ,, .r* Reactor vessel Reactor vessel internals Pressurizer Steam generators Control element drive mechanisms Reactor coolant pumps Reactor coolant system Class 1 piping Non-class 1 piping and in-line components Flexible connections and expansion joints 4.0 Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information . Resolution Option .. Analysis projected 10 CFR 54.21(c)(1)(ii) Analysis projected 10 CFR 54.21(c)(1)(ii) Analysis projected 10 CFR 54.21 (c)(1 )(ii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) . ' .'.* Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Analysis remains valid 10 CFR 54.21(c)(1)(i) Analysis remains valid 10 CFR 54.21(c)(1)(i) LRA Section 4.2 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.3 4.3.1.1 4.3.1.2 4.3.1.3 4.3.1.4 4.3.1.5 4.3.1.6 4.3.1.7 4.3.2.1 4.3.2.2 Page 4.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 4.1-1 (Continued) List of TLAAs TLAA Description Non-Class 1 heat exchangers with fatigue analysis Effects of reactor water environment on fatigue life Resolution Option Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) qualification Equipment ;"< '" . *, ' .,,,.,,, . -.* Environmental qualification analyses of electrical equipment cbrltrete '* ... ,., . *' Concrete containment tendon prestress analysis r Containment vessel design Containment penetration bellows analyses . *** .. ' . "' ,. .. *.**-.. Other Plant-Specific.TLAAs' * ' . . . ' Crane load cycle analysis Leak-before-break analysis Postulation of high energy line break (HELB) locations Reactor vessel internals evaluations (other than fatigue) 4.0 Time-Limited Aging Analyses *':,, Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) ,,, ,i .... ' ,* ' 1::' None. WF3 containment does not include tendons. No TLAA identified for containment vessel design . . Analysis remains valid 10 CFR 54.21(c)(1)(i) ,.-i .:'*. .. .. Analysis remains valid 10 CFR 54.21 (c)(1 )(i) Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) Aging effects managed 10 CFR 54.21 (c)(1 )(iii) . . LRA Section 4.3.2.3 4.3.3 4.4 4.4 4.5 4.5 4.6 4.6 4.6 4.7 47.1 4.7.2 4.7.3 4.7.4 Page 4.1-5. Waterford Steam Electric Station, Unit 3 License Renewal Application

Technical lnformati1on Table 4.1-2 Comparison of WF3 TLAAs to NUREG-1800 Potential TLAAs NUREG-1800 Applicable-to WF3 TLAA Description (Yes/No) :Y .** Reactor vessel neutron embrittlement Metal fatigue Environmental qualification *of electrical equipment Concrete containment tendon prestress lnservice local metal containment corrosion analyses lntergranular separation in the affected zone of reactor vessel low-alloy steel under austenitic stainless steel (SS) cladding.
Low-temperature overpressure protection (LTOP) analyses Fatigue a*nalysis for the main steam supply lines to the turbine-driven *auxiliary feedwater pumps Fatigue analysis of the reactor coolant pump flywheel Fatigue analysis of polar crane Flow-induced vibration endurance *limit for the reactor vessel internals Transient cycle count assumptions for the reactor vessel internals Ductility [sic] reduction of fracture toughness for the reactor vessel internals 4,0 Time-Limited Aging Analyses Yes Yes Yes No. There are no pre-stressed tendons in the WF3 containment structure . . No. There are no metal containment corrosion analyses. No. There are no analyses associated with underclad cracking. Yes* Yes. Included with non-Class 1 fatigue. No. Does not meet the definition of TLAAs, since it does not involve limited assumptions defined by the current operating term. Yes No.* There is no RVI flow-induced vibration analysis meeting the definition of TLAAs. Yes Yes LRA *section 4.2 4.3 4.4 4.5 NA NA 4.2.5 4.3.2 NA 4.7.1 NA 4.3.1.2 4:7.4 Page 4.1-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 4.1-2 (Continued) Comparison of WF3 TLAAs to NUREG-1800 Potential TLAAs NUREG-1800 Applicable to WF3 LRA TLAA Description (Yes/No) Section Leak before break Yes 4.7.2 analysis for the containment liner No. No fatigue evaluation performed for NA plate containment vessel design. Containment penetration pressurization Yes 4.6 cycles Metal corrosion allowance No. No TLAAs were identified for metal NA corrosion allowances. High-energy line-break postulation based Yes 4.7.3 on fatigue cumulative usage factor lnservice flaw growth analyses that No. No analyses were identified that meet NA demonstrate structure stability for 40 years the definition of TLAAs. 4.0 Time-Limited Aging Analyses Page4.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT The regulations governing reactor vessel integrity are in 1 O CFR Part 50. Light-water reactors are required by 10 CFR 50.60 to meet the fracture toughness, pressure-temperature limits, and material surveillance program requirements for the reactor coolant pressure boundary set forth in Appendices G arid Hof 10 CFR Part 50 (Ref. 4-6, 4-7). The operating license for WF3 expires on December 18, 2024. With a renewed license, the license will expire on December 18, 2044. Through mid-year 2014, WF3 had accumulated approximately 24.7 EFPY of operation. Assuming WF3 is operated at a capacity factor qf 99 percent from mid-year 2014 until the end of the renewed license period will result in the following estimate of the EFPY at the end of the period of extended operation. 24.7 + 0.99 (30.5 years of operation after mid-year 2014) =approximately 54.9 EFPY. Therefore, 55 EFPY will .be used to bound the expected EFPY for WF3 at the end of the period of extended operation. 4.2.1 Reactor Vessel Fluence ' . Fluence is calculated based on a period of operation defined by the operating license term. Fluence projected to the end of the period of e?<tended operation is a time-limited assumption used in neutron embrittlement analyses. Therefore, analyses that evaluate reactor *vessel neutron embrittlement based on projected fluence are TLAAs. The neutron fluence values for the WF3 reactor pressure vessel have been projected to 55 EFPY of operation. (Ref. 4-11) The methods used to calculate the WF3 vessel fluence satisfy the criteria set forth in Regulatory Guide (RG) 1.190 (Ref. 4-8). These methods have been approved by the NRC and are described in detail in WCAP-14040-A, Revision 4, and WCAP-16083-NP-A, Revision 0. (Ref. 4-9, 4-10) FSAR Section 5.3.1.6 additional information on the specimen capsules and the associated dosimeters. See Section B.1.34 for additional information on the -Reactor Vessel Surveillance Program. Figure 4.2-1 and Figure 4.2-2 identify the vessel weld and plate names used in this section. *The reactor vessel beltline components with fluence values greater than 1.0 x 1017 n/cm2 (E > 1.0 MeV) at 55 EFPY are the three upper shell plates, three upper shell longitudinal welds, upper to intermediate shell circumferential weld, the three lower shell plates, three intermediate shell plates, three intermediate shell longitudinal welds, three lower shell longitudinal welds, and the intermediate shell to lower shell circumferential weld. Locations with fluence values that are greater than 1.0 x 1017 n/cm2 (E > 1.0 MeV) are in Tables 4.2-1 and 4.2-3. 4.0 Time-Limited Aging Analyses Page 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Contrary to the definition of TLAAs in 1 O CFR 54.3, the calculation of fluence does not consider the effects of aging. Nevertheless, it is treated as a TLAA that has been projected to the end of the period of extended operation in accordance with 1 O CFR 54.21 (c)(1 )(ii). 4.0 Time-Limited Aging Analyses . Page 4.2-2 Figure 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Vessel Weld Identification for WF3 4.0 Time-Limited Aging Analyses Page 4.2-3

/ Figure 4.2-2 Waterford Steam Electric Station, Unit 3 License Ren.ewal Application Technical Information Reactor Vessel Plate Identification for WF3 4.0 Time-Limited Aging Analyses Page 4.2-4 Table 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculated Maximum Fast Neutron Fluence (E+19 n/cm2, E > 1.0 MeV) Projections for the WF3 Vessel Welds and Plates at 55 EFPY %T At Clad/Base Location (Thickness )(a) Metal Interface , Intermediate Shell Plates M-1003-1, 2, and 3 2.575 4'.28 Lower Shell Plates M-1004-1, 2, and 3 2.575 4.32 Intermediate Shell Longitudinal Weld 101-124A 2.575 4.28 Intermediate Shell Longitudinal Welds 101-1248 and C 2.575 2.62 Lower Shell Longitudinal Weld 101-142A 2.575 4.32 Lower Shell Longitudinal Welds 101-1428 and C 2.575 2.65 Intermediate to Lower Shell Circumferential Weld 101-171 2.575 4.28 Upper Shell Plates M-1002-1, 2, and 3 0.035 0.0582 Upper Shell Longitudinal Welds 101-122A, 8, and C 0.035 0.0582 Upper to Intermediate Shell Circumferential Weld 106-121 0.035 0.0582 a. The Y..T fluence was calculated using the RG 1.99, Revision 2 correlation, and the WF3 reactor vessel wall thickness of 8.625 inches. For intermediate and lower shell weld and plate locations, the maximum fluence value of 2.575 E+19 n/cm2 was applied for conservatism. For upper shell weld and plate locations (last three locations shown), the maximum fluence value of 0.035 E+19 n/cm2 was applied for conservatism. 4.0 Time-Limited Aging Analyses Page 4.2-5 ( 4.2.2 Upper-Shelf Energy Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Upper-shelf energy (USE) was evaluated for beltline materials. Fracture toughness criteria in 1 O CFR Part 50 Appendix G require that beltline materials maintain USE no less than 50 ft-lb during operation of the reactor. The 55 EFPY USE values for the beltline were determined using methods with RG 1.99 (Ref. 4-12). The value of peak %T fluence

was used. Two methods can be used to predict the decrea$e in USE with irradiation, depending on the availability of credible surveillance capsule data as defined in RG 1.99. For vessel beltline materials that are not in the surveillance program or for locations with non-credible data, the USE is assumed to decrease as a function of flu.ence and copper (Cu) content, as indicated in RG 1.99, Revision 2 (Position 1.2). When two or more credible surveillance data sets are available from the reactor, they may be used to determine the USE of the survefllance material. The surveillance are then used in conjunction with RG 1.99 to predict the change in USE of the reactor vessel material due to irradiation (Position 2.2). The 55 EFPY Position 1.2 USE values of the vessel *materials can be predicted using the corresponding %T fluence projection, the copper content of the materials, and Figure 2 in RG 1.99, Revision 2. The predicted Position 2.2 USE values are determined for the reactor vessel materials that are contained in the surveillance program by using the plant surveillance data along with the corresponding %T fluence projection. The projected USE values were calculated to determine if the WF3 beltline materials remain no less than the USE limit of 50 ft-lb at 55 EFPY. The results are summarized in Table 4.2-2. For WF3 (see Table 4.2-2), the limiting USE value at 55 EFPY is 73 ft-lb for the upper stiell longitudinal welds. The USE of all of the beltline materials in the WF3 reactor are projected to remain above the USE limit of 50. ft-lb through 55 EFPY. Therefore, the WF3 reactor vessel USE TLAA has been projected to the end of the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(ii). 4.0 Time-Limited Aging Analyses Page 4.2-6
' Table 4.2-2 Predicted USE Values at 55 EF_PY for WF3 RPV Beltline Materials ' Initial Cu %T Fluence(b) USE RPV Material(a) * --(Wt.%) (x1019 n/cm2) (ft-lb) Intermediate Shell Plate M-1003-1 0.02 2.575 108 Intermediate Shell Plate M-1003-2 0.02 2.575 132 Intermediate Shell Plate M-1003-3 '0.02 2:575 111 Lower Shell Plate M-1004-1 0.03 2.575 135 Lower Shell Plate M-1004-2 0.03 2.575 141 Lower Shell Plate M-1004-2 (using WF3 surveillance 0.03 .2.575 141 data) Lower Shell Plate M-1004-3 0.03 2.575 .118 Intermediate Shell Longitudinal Weld 101-124A 0.02 2.575 106 (Heat # BOLA & HODA) .f -. Intermediate Shell Longitudinal Welds 101-1248 & C 0.02 2.575 131 (Heat # HODA) Lower Shell Longitudinal Welds 101-142A, 8 & C ?* . 0.03 2.575 129 (Heat# 83653) " .-Intermediate to Lower Shell Circumferential Weld * ; 156 101-171(Heat#88114) 0.05 2.575 Intermediate to Lower Shell Circumferential Weld 0.05. 2.575 -156 101-171 (Heat# 88114) (using WF3 surveillance data) : 4.0 *Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Projected 55 EFPY . USE USE. . Decrease(c)(%) (ft-lb) 24 82 24 100 24 84 24 103 24 107 17(d) 117 24 90 24 81 24. 100 24 98 24 119 '* 15 (d)_. 133 Page 4.2-7 Table 4.2-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Predicted USE Values at 55 EFPY for WF3 RPV Beltline Materials (Continued) Initial Projected 55 EFPY Cu % T Fluence!b) USE USE USE RPV Material(a) (Wt.%) (x1019 n/cm2) (ft-lb) Decrease( cl(%) (ft-lb) Upper Shell Plate M-1002-1 0.13. 0.035 104 10 94 Upper Shell Plate M-1002-2 0.13 0.035 95 10 86 Upper Shell Plate M:.1002-3 0.10 0.035 120 9 109 Upper Shell Longitudinal Welds 101-122 A, B & C 0.23 0.035 88 17 73 (Heat# 606L40) Upper Shell Longitudinal Welds 101-122 A, B & C 0.02 0.035 ; 119 7 111 (Heat # FOCA) .-Upper Shell Longitudinal Welds 101-122 A, B & C 0.03 0.035 125 8 115 (Heat# JBHA) Upper Shell Longitudinal Welds 101-122 A, B & C 0.02 0.035 131 7 122 (Heat# HODA) Upper to Intermediate Shell Circumferential Weld 106-1'21 (Heat #-.3P4767)
0.16 0.035 87 14 75 ., Upper to .Intermediate Shell Weld 0.03 0.035 >87 8 > 80 106-121 (Heat# IAGA) Upper to Intermediate Shell Circumferential Weld 0.03 0.035 113 8 104 106-121 (Heat# KOHA) a. Table is derive,d from Table 5-1 of WCAP-18002-NP (Ref. 4-11 ). b. The '!l.!T'fluence was calculated using the RG 1.99, Revision 2, correlation, and the.WF3 reactor vessel wall thicknes$ of 8.625 inches. For. intermediate and lower shell weld and plate locations, the maximum fluence value of 2.575 E+19 n/cm2. was applied for conservatism. For upper shell weld and plate locations (last 10 locations shown), the maximum fluence value of 0.035 E+19 n/cm2 was applied for conservatism. 4.0 Time-Limited Aging Analyses Page 4.2-8 Waterford Steam Electric Station, Unit 3 .
License Renewal Application Technical Information c. Unless otherwise noted, percentage USE decrease values are based on Position 1.2 of RG 1.99, Revision 2, and were 9etermined by plotting the XT fluence values on Figure 2 of RG 1.99 and using _the material-speCific Cu wt. % values. For any materials with Cu wt. % less than the lowest lirie delineated in RG 1.99, Revision 2 (0.05% for welds and 0.10% for base metal), the Cu wt. % values *were conservatively rounded up to the lowest line. d. Percentage USE decrease is based on Position 2.2 of RG 1.99, Revision 2, using data from Jable 5-10 of WCAP-17969-NP, Revision 0. Credibility Criterion 3 in the Discussion section of RG 1.99, Revision 2, indicates that even if the surveillance data are not considered credible for determination of aRT NDT (reference temperature, nil-ductility transition), "they may be credible for determining decrease in upper-shelf energy if the upper-shelf can be clearly determined, following the definition given in ASTM E 185-82." Thus, the surveillance data may be used for WF3 USE projections. RG 1 :99, Revision 2, Position 2.2 indicates that an upper-bound line drawn parallel to the existing lines (in Figure 2 of . RG 1.99) through the surveillance data should be used in preference to the existing graph lines for determining the decrease in USE. , .. 4.0 Time-Limited Aging Analyses Page 4.2-9 4.2.3 Pressurized Thermal Shock Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Rules are provided in 10 CFR 50.61 for protection against pressurized thermal shock for pressurized water reactors. Licensees must assess the projected values of reference temperature whenever a significant change occurs in projected values of the adjusted reference temperature for pressurized thermal shock (RT PTS) or upon request fo'r a change in the . expiration date for the operating license of the facility. In accordance with the screening criteria of 10 CFR 50.61, acceptable RT PTS values are less than 270°F for plates, forgings, and axial welds and less than 300°F for circumferential welds. (Ref. 4-13) * . . . . two methods are provided in 10 CFR 50.61(c) for determining RT PTS* Position 1 app!ies for material that does not have surveillance data available, and Position 2 applies for material wi.th . surveilJance data. Positions 1 and 2 are described in RG 1.99, Revision 2. Adjusted reference temperatures are calculated for both Positions 1 and 2 by following the guidance in RG 1.99, Sections 1.1. cind 2.1, respectively, using copper and nickel (Ni) content of beltline end-of-license fluence projections.
The WF3 limiting RT PTS value for base metal or longitudinal weld materials at 55 EFPY is 57°F (see Table 4.2-3) at the upper shell plate M-1002-2. The WF3 limiting RT PTS value for circumferentially oriented welds at 55 EFPY is 73°F (see Table 4.2.:.3) at upper to intermediate shell circumferential weld 106-12*1 (Heat# 3P4767). All of the beltline materials in the WF3 reactor vessel are below the RT PTS screening criteria values of 270°F for plates, axial welds, and forgings and 300°F for circumferentially oriented welds through 55 EFPY. Therefore, the WF3 reactor vessel RT PTS TLAA has been projected to . .<. the end of the period of extended operation in accordance with 1 O CFR 54.21 (c)(1)(ii). 4.0 Time-Limited Aging Analyses Page 4.2-10 Table 4.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY Wt.% Wt.% CF(c) Fluence(d) RT NDT(U) (e) .6RTNDT a u(e) a ll.(f) Margin RTPTS RPV Material(a)(b) Cu (c) Ni (cl (oF) (x 1019 n/cm2) FF(d) (oF) (oF) (oF) (oF) (oF) (oF) Intermediate Shell 0.02 0.71 20 4.32 1.3726 -25.1 27.5 0 13.7 27.5 30 Plate M-1003-1 Intermediate Shell 0.02 0.67 20 4.32 1.3726 -20 27.5 0 13.7 27.5 35 Plate M-1003-2 Intermediate Shell 0.02 0.70 20 4.32 1.3726 -20 27.5 0 13.7 27.5 35 Plate M-1003-3 Lower Shell Plate 0.03 0.62 20 4.32 1.3726 -37.6 . 27.5 0 13.7 27.5 17 M-1004-1 Lower Shell Plate 0.03 0.58 20 4.32 1.3726 0 27.5 0 13.7 27.5 55 M-1004-2 Lower Shell Plate M-1004-2 (using ----13.4 4.32 1.3726 0 18.4 0 9.2 18.4 37 non-credible WF3 surveillance data)(g) Lower Shell Plate 0.03 0.62 20 4.32 1.3726 -20 27.5 0 -13.7 27.5 35 M-1004-3 Intermediate Shell Longitudinal Weld 0.02 0.96 27 4.32 1.3726 -60 37.1 0 18.5 37.1 14 101-124A (Heat# BOLA & HODA) Intermediate Shell Longitudinal Welds 0.02 0.96 27 4.32 1.3726--60 37.1 0 18.5 37.1 14 101-1248 & c (Heat# HODA) 4.0 Time-Limited Aging Analyses Page 4.2-11 Table (Continued} Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RTPTS Values Cfad/Base Metal Interface for 55 EFPY (Continued} Wt.% Wt.% CF(c) Fluence<d) RT NDT(U) (e) ARTNDT a u(e) C1 li.(f) RTPTS RPV Materia1<a)(b) (c) Ni. (c) (oF) (x 1019 n/cm2) FF(d) (oF) . (<>F) (oF) (oF) (OF) (oF) Lower Shell Longitudinal Welds 0.03 < 0.20 35 4.32 1.3726 -80 48.0 0 24.0 48.0 16 101-142A, B & C .. (Heat # 83653) ... to *-Lower Shell Circumferential Weld 0.05 0.16 44.4 4.32 1.3726 -70 . 60.9 *. 0 28.0 56.0 47 101"-171 . (Heat# 88114) Intermediate to Lower Shell Circumferential Weld 101-171 ----14.8 4.32 '1.3726 -70 20.3 0 10.2 20.3 -29 (Heat #,88114) (using credible WF3 surveillance data)(g) *. Upper Shell Plate 0.13 0.64 92 0.0582 0 .. 3174 -15.4 29.2 0 14.6 ;29.2 43 M*1002-1 ' . Upper Shell Plate 0.13 0.61 91.3 0.0582 0.3174 . -1'.4: 29.0 0 14.5 29.0 57 M-1002-2 . Upper Shell Plate 0.10 . 0.65 65.5 0.0582 0.3174 . ; :-20. 20.8 *o *. 10.4 . 20.8 22 M-1002-3 .. *. 4.0 Time-Limited Aging Analyses Page 4.2c12 Table 4.2-3 (Continued), Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY (Continued) Wt.% Wt.% CF(c) Fluence(d) RT NDT(U) (e) .6RTNDT a u(e) C1 l!J. (f) Margin RTPTS RPV Material(a)(b) Cu (c) Ni (c) (oF) (x 1019 n/cm2) FF(d) (oF) (oF) (oF) (oF) (oF) (oF) Upper Shell Longitudinal Welds 0.23 0.27 125.1 0.0582 0.3174 _55(h) 39.7 17(h) 19.9 52.3 36 101-122 A, B & C (Heat# 606L40) Upper Shell Longitudinal Welds 0.02 0.98 27 0.0582 0.3174 -30 8.6 0 4.3 8.6 -13 101-122 A, B & C (Heat # FOCA) Upper Shell Longitudinal Welds 0.03 0.97 41 0.0582 0.3174 -40 13.0 0 6.5 13.0 -14 101-122 A, B & C (Heat# JBHA) Upper Shell Longitudinal Welds 0.02 0.96 27 0.0582 0.3174 -60 8.6 0 4.3 8.6 -43 101-122A, B & C (Heat# HODA) Upper to Intermediate Shell Circumferential Weld 0.16 1.00 199 0.0582 0.3174 _55(h) 63.2 17(h) 28.0 65.5 73 106-121 (Heat# 3P4767) 4.0 Time-Limited Aging Analyses Page 4.2-13 Waterford. Steam Electric Station, Unit 3 License Renewal Application Technical Information . Table 4.2-3 (Continued) Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY (Continued) Wt.% Wt.% Cf(c) Fluenceld) RT NDT(U) (e) a u(e) a 11(f) Margin RTPTS RP\rMaterial(a)(b) -Cu (c) Ni (c) (Of) (x 1019 n/cm2) ff(d) (of) (of) (Of) (Of) (Of) (of) Upper to Intermediate Shell -CircumferentialWeld 0.03 0.98 41 0.0582 0.3174 -30 13.0 0 6.5 13.0 -4 106-121 (Heat # IAGA) I ---Upper to ' --Intermediate Shell *. Circumferential Weld 0.03 0.93 41 0.0582 _. 0.3174. -30 13.0 0 6.5 13.0 -4 106-121 " (Heat# KOHA) a. Table is derived from Table 4-1 of WCAP-18002-NP(Ref. 4-11). . b. Due to industry and regulatory interest in the methods of BTP 5-3, initial RT NDT and initial,1,JSE values for all of the beltline plate materials were re-evaluated. The initial RT NDT and initial USE values for the WF3 plate materials no longer utilize BTP 5-3 as their determination methodology. c. Chemical composition values and chemistry factors (CFs) provicjed in (Ref. 4-11) .. d. Clad/base metal interface fluence values taken from (Ref. 4-11). *FF= fluence factor= f(o.2a-o.1o*iog(f))_ e. Initial RT NDT values are based on measured data unless otherwise noted in WCAP-18-002-NP (Ref. 4-11 ). f. Per Appendix D of WCAP-17969-NP, Revision 0 (Ref. 4-14), and WCAP-18002-NP (Ref. 4-11), the sur\teillance data for the plate were deemed non-credible, whereas the sun/eillance data for the weld material were deemed credible. Per*the guidance of 1 O CFR 50.61, the base metal 01:;. = 17°F for Position 1.1. .and !or Position 2.1 yvith r:ion-credible surveillance data; the weld metal o /:;. = 28°F for Position 1.1 and, with credible surveillance data, 01:;. = 1_4°F for Position 2.1., However, 01:;. need not exceed NDT* g. Used RG 1.99, Rev. 2 Position 2.1; all others.used Position 1.1.
h. Initial RT NDT value is generic for Linde 0.091 flux type welds 10*CFR 50.61 as identified in WCAP-18002-NP (Ref. 4-11). Therefore, Ou= 17°F. 4.0 Time-Limited Aging Analyses Page 4.2-14 4.2.4 Pressure-Temperature Limits Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Appendix G of 1 O CFR 50 (Ref. 4-6) requires operation of the reactor pressure vessel within established pressure-ternperature (P-T) limits.* These limits are established by calculations that utilize the fluence and material property data obtained through the Reactor Vessel Surveillance Program. The P-T limits are valid for an established period of time. The provisions of 10 CFR 5Q Appendix G require the P-T limit curves be maintained and updated as necessar)f. The WF3 P-T limits for reactor coolant system are described in Technical Specifications (TS) 3.4.8.1. Technical Specification Figure 3.4-2, Reactor Coolant System Pressure-Temperature Limits,* identifies the WF3 heatup* limits for up to 32 EFPY. Technical Specification Figure 3.4-3, Reactor Coolant System Pressure-Temperature Limits, identifies the WF3 cooldown limits for up to 32 EFPY. Technical Specification 4.4.8.1.2 indicates that the reactor vessel material irradiation surveillance specimens shall be removed and examined at the intervals specified in the Reactor Vessel Material Surveillance Program withdrawal schedule in FSAR Table 5.3-10. The schedule is in accordance with 10 CFR Part 50 Appendix H. The examinations are performed to determine changes in material properties; and the results are used to update Technical Specifiqation Figures 3.4-2 and 3.4-3. Surveillance specimen capsule 83° was removed at approximately 24.7 EFPY. (Ref. 4-14) The analyses used to determine the P-T limit curves in the associated WCAP supporting documentation are considered TLAAs. The WF3 P-T limit curves included in the Technical Specifications are valid through 32 EFPY. Prior to exceeding 32 EFPY, WF3 will generate new P-T limit curves to support plant operation beyond 32 EFPY.
P-T limits will be updated as necessary through the period of extended operation in .conjunction with the Reactor Vessel Surveillance Program (Section B.1.34). Under the current license term and during the period of extended operation, the P-T limits will be updated prior to the end of their applicability period in accordance with the 10 CFR 50.90 process. Therefore, the Reactor Vessel Surveillance Program (Section B.1.34) will adequately manage the effects of aging associated with the P-T limit curves TLAAs for the period of extended operation in accordance. with 10 CFR 54.21 ( c)(1 )(iii). 4.2.5 Low-Temperature Overpressure Protection <LTOPl Setpoints The WF3 Technical Specification Bases 3/4.4.2 states that an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. This is accomplished by a low-temperature overpressure protection (LTOP) relief valve located in each shutdown cooling loop as identified in FSAR Section 5.28.3. In addition, the overpressure protection system provides a diverse means of protection against 4.0 lime-Limited Aging Analyses Page 4.2-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RCS overpressurization at low temperatures. Each time the P-T limit curves are revised, the LTOP relief setpoints are reevaluated. Therefore, the LTOP limit calculations are considered part of the analyses of P-T curves for WF3. The P-T limit curves are updated prior to exceeding EFPY applicability limits. See Section 4.2.4 for further information on the P-T limit curves. Therefore, the Reactor Vessel Surveillance Program (Section B.1.34) will adequately manage the effects of aging associated with the LTOP setpoints TLAA for the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.2-16 4.3 METAL FATIGUE; Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fatigue analyses are considered TLAAs for Class 1 and non-Class 1 mechanical components. Fatigue is an age-related degradation mechanism caused by cyclic stressing of a component by either mechanical or thermal stresses. The aging management reviews in Section 3 identify mechanical components that are within the scope of license renewal and subject to aging management review. When TLAA -metal fatigue is identified in the aging management program column of the. tables in Section 3, the associated fatigue arialyses are evaluated in this section. Evalu.13tion of TLAAs per 10 CFR 54.21(c)(1) determines whether (i) The analyses remain valid for the period of extended operation, (ii) The analyses have been projected to the end. of the period of extend operation, or (iii) The effects of aging on the intended function(s) will be adequately managed for the period of extended operation. Documentation of the evaluation of WF3 Class 1 metal fatigue analyses is provided in Section 4.3.1. Fatigue analysis of non-Class 1 mechanical components is discussed in Section 4.3.2. Evaluation of environmental fatigue effects is discussed in Section 4.3.3. 4.0 Time-Limited Aging Analyses Page 4.3-1 4.3.1 Class 1 Fatigue ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The major Class 1 components at WF3 include the reactor vessel, pressurizer, reactor coolant pumps, steam control rod drives, and associated piping and valves. As identified in
FSAR Section. 5.2.1,. the construction permit application for Waterford 3 was filed in December 1970. Major components for the nuclear steam supply system were ordered consistent with the application date and anticipated schedule. The reactor vessel, steam generators, pressurizer and piping were ordered in March 1971 and the reactor coolant pumps in March 1972. The construction permit was received in November 197 4. An isometric view of the reactor coolant system is shown in FSAR Figure.4.4-7. The following systems and associated LRA drawings that include Class 1* components. System (System Code) Reactor Coolant System (RC) Safety l!'ljection System (SI) Chemical and Volume Control System (CVC) LRA Drawinq(s) LRA-G172 LRA-G179
LRA-G 160 sh 4 LRA-G167 sh 2 LRA-G167 sh 4 LRA-G168 sh 1 LRA-G168 sh 2 Fatigue evaluations performed in the design of WF3 Class 1 components in accordance with ASME Section Ill requirements are documented in the equipment stress reports and associated, analyses. The fatigue evaluations calculate a cumulative usage factor (CUF) for each component or subcomponent based on a specified number of design cycles for that component. Because the design cycles may be the nu.mber of transient cycles that were assumed for a 40-year license term, these calculations of CUFs are considered TLMs. Design cy,clic loadings and thermal conditions for the Class 1 components are defined by the. applicable design specifications for each component. The original design specifications established the initial set of transients that were used in the design of the components and are included as part of each component stress report. FSAR Table 3.9-1, "Transients Used in Stress Analysis of Code Class 1 Components," lists the transients that were used for the stress analyses of the RCS components. FSAR Table 3.9-3, "Transients and Operative Conditions for Code Class 1 Non-NSSS Piping," identifies _the transients that were used as input to the piping stress analyses. Some component-specific locations such as the pressurizer and safety injection nozzles were also analyzed for design transients* beyond the original set of transients in response to thermal stratification and component-specific stresses that are identified in the individual stress analyses. . ( 4.0 Time-Limited Aging Analyses Page 4.3-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The WF3 Technical Requirements Manual (TRM) 5.7-1 contains the requirement to maintain the reactor coolant system components within the component cyclic or transient limits of TRM Table 5.7-1. In preparation for license renewal, an evaluation was performed to determine the cycles that required tracking. Then a review of plant operating history identified the number of cycles as of April 5; 2014. The rate of transient occurrence was utilized to estimate the number of cycles through 60 years of operation as shown in Table 4.3-1 As described in Appendix B, the WF3 Fatigue Moniforing Program will monitor transient cycles that contribute to fatigue usage.
Cycle monitoring ensures the continuing validity of fatigue TLAAs (calculations of CUFs) for various WF3 components. The Fatigue Monitoring Program (Section B.1.11) will monitor the necessary operating transients and assure action is taken prior to the analyzed riumpers of transients being exceeded. The WF3 Fatigue Monitoring Program will manage the aging effects due to fatigue of the affected components in accordance with* 10 CFR 54.21(c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.3-3

/ \ { i ,_ ' . Table 4.3-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Projected and Analyzed Transient Cycles Number of . Cycles as of 60-year Projected Analyzed Number Transient Description ' 4/5/14 Number of Cycles(a) of Cycles RCS heatup , 70 144 300 Pressurizer heatup 70 144 200 RCS cooldown

69 144 300 cooldown 69 144 :. 200 Reactor trip 91 187 400 I. Loss of reactor. coolant flow 0 4(b) 40 . Loss .of load 0 4(b) 40 Operating basis earthquake 0 1(1J) 5 8o1Uunbolt (RV head) 23 47 50 ' PZR Spray Transients: 81: Aux. spray, :> 1. pump, > 350°F . 18 37 ., 140 82: Aux. spray,*> 1 pump, s 350°F *7 14 160 ., C1 :*Aux. spray, < 2 pumps, > 350°F 151 '. 310 41Q C2: Aux. spray, < 2 pur;nps, s 350°F . 129 .. 265 240 D: Stop 3rd RCP, no aux. spray 124 254 400
E: Start 2nd RCP, s 392 psia 124 254 400 Tube leak tests (for replacement steam generators) Tube leak test (at 200 psig) 0 4q(b) 400 Tube leak. test (at 400 psig) " 2o(bl '* 0 200 ' -Tube leak test (at 600 psig), 0 12(b) " 120 Tube leak test (at 840 psig) 0 8(bl 80 Containment integrated leakage rate 1 4(b) 20 test (ILRT) Loss of charging 4 8 200 Loss of letdown 25 51 100 Extended loss *of letdown 131 .. 269 600 Safety valve release 0 4(b) 40 Safety injection at full temperature 0 4(b) 10 4.0 Time-Limited Aging Analyses Page 4.3-4 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information a. The original operating license term ends on 12/18/2024 and the renewed operating license term would end on 12/18/2044. The 4/5/2014 data date "is at 29.3 years of operation. Unless otherwise identified by a footnote, the projected values are determined by using a multiplier of 60/29.3 = 2.05 times the number of occurrences as* of 4/5/2014. b. Although none of these cycles have occurred, a projected value is conservatively listed. These projected values have not been used to replace the original analyzed .numbers of cycles. Cycles will continue to be tracked by th.e Fatigue Monitoring Program (Section B.1.11 ). . . 4.3.1.1 Reactor Vessel FSAR Table 5.2-.1, "Codes and Addenda Applied to Reactor Coolant Pressure Boundary," identifies the codes and addenda applied to the design of the reactor coolant pressure boundary. The reactor vessel was designed to ASME Section Ill, Class 1 through Summer 1971 Addenda .. The original .reactor vessel head has been replaced. The replacement reactor vessel head was designed to ASME Section Ill, Class 1 1998 edition through summer 2000 addenda. . . The calculated CUFs for the reactor vessel and replacement head are less than 1. The reactor vessel design transients that require tracking are included in Table 4.3-1. WF3 will monitor transient cycles using the Fatigue Monitoring Program and assure that corrective action specified in the program is taken if any of the actual cycles approach their analyzed nu.mbers. As such, the Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging due to fatigue on the reactor vessel and reactor vessel head in accordance with 1 O CFR 54.21 (c)(1)(iii). 4.3.1.2 Reactor Vessel Internals The WF3 reactor vessel internals are not pressure boundary components. As described in FSAR Section 3.9.5, in the design of critical reactor vessel internals components that are subject to fatigue, the stress analysis was performed utilizing the design fatigue cunle of Figure *1-9.2 of Section Ill of the ASME Boiler and Pressure Vessel Code. Stress reports were generated for several specific reactor vessel internals locations to support component replacement or reanalysis. The calculated CUFs for the reactor vessel internals are less than 1. The transients iqentified in Table 4.3-1 include the transients that require tracking for the reactor vessel internals. WF3 will monitor transient cycles using the Fatigue Monitoring Program and assure _that corrective action specified in the program is taken if any of the actual cycles approach their. analyzed numbers. As such, the Fatigue Monitoring Program will manage the effects of aging due to fatigue on the reactor vessel internals in accordance with 1 O CFR 54.21 (c)(1 )(iii). 4.0 Time-Limited Aging Analyses Page 4.3-5 4.3.1.3 Pressurizer Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The pressurizer is described in-FSAR Section 5.4.10 and is shown in FSAR Figure 5.4:..6. As identified in FSAR Table 5.2-1, the pressurizer was to ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, through Summer 1971 Addenda. Structural weld overlays have been installed on the pressurizer surge nozzle, the pressurizer safety valve nozzles, and the pressurizer spray nozzle. The heater sleeves that remain in service were repaired. The pressurizer side shell temperature measurement nozzle arid upper and lower head instrument nozzles were replaced.

the .calculated CUF=s for the pressurizer are less than 1. The transients identified in Table 4.3-1 include the transients that require tracking for the pressurizer. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the pressurizer in accordance with 10 CFR 54.21 (c)(1 )(iii).
4.3.1.4 Steam Generators Replacement steam generators have been installed at WF3 as identified in FSAR Section 5.4.2 and shown in FSAR Figure 5.4-5. As identified in FSAR Table 5.2-1, the replacement steam generators were designed to ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, 1998 Edition through 2000 Addenda. In addition to the RCS. transients identified.in FSAR Section \ 3.9.1.1, the replacement steam generators*fatigue analysis evaluation of c9mponent . : -specific transients such as the tube leak tests. -The calculated CUFs for the replacement steam generators are less -than 1. The transients identified in Table 4.3-1 include the transients*that require tracking for the replacement steam generators. The Fatigue Monitoring Program will manage the effects of agi_r:ig due to fatigue on . the steam generators in accordance with 10 CFR 54.21(c)(1)(iii). 1.5 Control Element Drive Mechanisms As described in FSAR Section 4.1, the control element drive mechanisms have been replaced. The control element drive mechanisms are described in FSAR Sections 3.9.4 and 4.1 and shown in FSAR Figure 3.'9-13. As described in FSAR Table 5.2-1, the replacement control element drive mechanisms are designed to.ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, 1.998 Edition and 2000 Addenda. The calculated CUFs for the control element drive mechanisms are less than 1. The transients identified in Table 4.3-1 include the transients that require tracking for the control element drive mechanisms. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the control element drive mechanisms in accordance with 10 CFR 54:21{c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.3-6 .

4.3.1.6 Reactor Coolant Pumps Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The reactor coolant pumps are described in FSAR Sections 3.9.1 and 5.4.1 and are shown in FSAR Figures 5.4-1 and 5.4-2. As identified in _FSAR Table 5.2-1, the pump casings were de.signed to.ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, through Winter 1971 Addenda.

The calculated CUFs for the reactor coolant pumps are less than 1. The transients identified _in Table 4.3-1 include the transients that require tracking for the reactor coolant pumps. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the reactor coolant pumps in accordance with 10 CFR 54.21(c)(1)(iii). 4.3.1.7 *Reactor Coolant System Class 1 Piping* The reactor coolant loop piping is in FSAR Section 5.4.3. The hot legs, cold legs and *pressurizer surge piping was supplied by the nuclear stearn system supplier (NSSS), ABB
Combustion Engineering, and controlled by project specifications. The Class 1 tributary lines
analyses include consideration of location specific transients such as loss of charging and loss of
Structural weld overlays (SWOL) have been installed on piping *for the hot leg surge nozzle,, hot leg two-inch drains;* and the hot leg shutdown cooling nozzles. The calculated piping CUFs are less than* 1. The transients identified in Table 4.3-1 include the transients that require tracking for the Class 1 piping. The Fatigue Monitoring Program will manage the effects of aging due to fatig1,.1e on the reactor coolant system Class .1 piping in accordance with 10 CFR54.21(c)(1)(iiif 4.0 Time-Limited Aging Analyses Page 4.3-7 4.3.2
Non-Class 1 Mechanical Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.3.2.1 Non-Class 1 Pressure Boundary Piping Using Stress Range Reduction Factors The impact of thermal cycles on non-Class 1 piping and in-line components is reflected in the reduction of the allowable stress range if projected cycles exceed 7000. The design of ASME 111 Code Class 2 and 3 or 831.1 piping systems incorporates a stress range reduction factor for determining acceptability of piping design with respect to thermal stresses. In general, a stre§ls range reduction factor of 1.0 in the stress analyses applies for up to 7000 thermal cycles. The allowable stress range is reduced by the stress *range reduction factor if the number of thermal cycles exceeds 7000 (ASME Boiler and Pressure Vessel Code, Division 1, Subsection NC, Class 2 For the systems that are subjected to elevated temperatures above the fatigue. threshold, thermal cycles have been projected for 60 years of plant operation for the.piping and: in-line components. These projections indicate that 7000 cycles will not be exceeded during 60 years of operation. Therefore, the non-Class 1 pipe stress calculations are valid for the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(i). 4.3.2.2 Flexible Connections and.Expansion Joints As part of the review of the WF3 documentation for fatigue, a search was performed for * *of mechanical flexible connectors and expansion joints that are within the scope of license renewal. TLAAs were identified for emergency diesel generator intake air.and exhaust expansion joints ineluded in LRA tables in Section 3. The of these analyses determined. flexible connectors were qualified for at least 15,000 cycles, which are more cycles than are expected from the starting of the diesels for the period of extended operation. The design analyses were determined to.remain valid for the period of operation in accordance with 10 CFR 54.21(c)(1)(i). . . 4.3.2.3 Non-Class 1 Heat Exchangers with Fatigue Analysis. Although the letdown and regenerative heat exchangers are in the Class 2 portion of the system, a fatigue analysis was completed for the design of these components. The cycle limits are represented in Table 4.3-1. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the letdown and regenerative heat exchangers in accordance with 10 CFR 54.21(c)(1)(ii.i). * *
4.0 Time-Limited Aging Analyses Page 4.3-8 Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information 4:3.3 Effects of Reactor Water Environment on Fatigue Life Industry test data inc:jicate that certain environmental effects (such as temperature and dissolved oxygen content) in the primary systems of light water reactors could result in greater susceptibility to fatigue than would be predicted by fatigue analyses based on the ASME Section Ill design fatigue curves. The ASME design fatigue curves were based on laboratory tests in air and at low temperatures. As reported in SECY-95-245, the NRC believes that no immediate staff or licensee-action is necessary to deal with the environmentally assisted fatigue issue. In addition, the staff concluded that it could not justify requiring a backfit of the environmental fatigue data to operating plants. However, the NRC concluded that, because metal fatigue effects increase with service life, environmentally assisted fatigue should be evaluated as aging management programs are formulated in support of license renewal. NUREG/CR-6260 (Ref. 4-18) addresses the application of-environmental factors to fatigue analyses (CUFs) and identifies locations of interest for consideration of environmental effects. NUREG/CR-6260 identified the following component locations to be.the most sensitive to environmental effects for Combustion Engineering (CE) plants. (1) Reactor vessel shell and'lower head * ; . . (2) Reactor vessel inlet and outlet nozzles '(3). Surge line . (4) Charging system nozzle (5) Safety injection system .nozzle * (6) Shutdown. cooling line Table 4.3-2 shows the results of a screening evaluation for these locations. Environmentally Assisted Fatigue (EAF) Summary NUREG-1801, Section X.M1 says the applicant addresses the effects of the coolant environment on component fatigue life by assessing the impact of the reactor coolant environment on a sample of critical components for the plant. There is no analysis of EAF under the current basis. Rather, the effect on fatigue life of the reactor water environment is a new consideration for license renewal. Applying the environmentally assisted fatigue correction factqrs <Fens) identified in Table 4.3-2 is not required during the initial 40 years of operation, consistent with the closure of Generic Safety Issue (GSI) 190. (Ref. 4-3) 4.0 Time-Limited Aging Analyses Page 4.3-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As shown in Table 4.3-2, using bounding environmental correction factors, two locations have environmentally adjusted projected CUFs greater than 1.0 at the end of the period of extended operation. The WF3 Fatigue Monitoring Program (Section 8.1.11) wili manage the effects of aging due to fatigue, including EAF, for the period of extended operation iri accordance with 10 CFR 54.21(c)(1)(iii). For locations with projected CUFs greater than 1.0, refined EAF evaluations will be completed for WF3 prior to the period of extended operation as identified by the enhancement to the Fatigue Monitoring Program (Section B.1.11 ). Original design basis fatigue calculations typically include conservatism meant to simplify the analyses, such as lumping transients together and considering them to be as severe as the worst transient for a particular location. As a part of incorporating the effects on fatigue of the reactor water environment, the design basis fatigue analyses may be revised for locations that would exceed a GUF of 1.0. CUFs will be determined using an NRG-approved version of the ASME code or NRG-approved alternative_ (e:g., NRG-approved code case). WF3 will update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 whe*n. accounting for the effects of reactor water environment prior to the period of extended operation.* This includes applying the appropriate Fen factors to valid CUFs determined using an NRG-approved version of the ASME code or NRG-approved alternative (e.g., NRG-approved code case). WF3 will review design basis ASME Class 1 component fatigue evaluations to ensure the locations evaluated for the effects of the reactor coolant environment on fatigue include the most limiting components within.the reactor coolant pressure . boundary. Environmental effects on fatigue for these critical components will be evaluated using one of the following sets of formulae. Carbon and Low Alloy Steels (LAS)
Those provided in NUREG/CR-6583 (Ref. 4-19), using the applicable ASME Section Ill fatigue design curve.
Those provided in Appendix A of NUREG/CR-6909 (Ref. 4-20), using either the applicabl13 ASME Section Ill fatigue design curve or the fatigue design curve for carbon and low alloy steel provided in NUREG/CR-6909 (Figures A.1 and A.2, respectively, and Table A.1).
A staff-approved alternative. Austenitic Stainless Steels
Those provided in NUREG/CR-5704 (Ref. 4-17), using the applicable ASME Section Ill fatigue design curve. 4.0 Time-Limited Aging Analyses Page 4.3-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Those provided in NUREG/CR-6909, using the fatigue design curve for austenitic steel provided in NUREG/CR-6909 (Figure A.3 and Table A.2).
A staff-approved alternative. Nickel Allovs
Those provided in NUREG/CR-6909, using the fatigue design curve for austenitic stainless steel provided in NUREG/CR-6909 (Figure A.3 and Table A.2).
A alternative. If an acceptable CUF cannot be calculated, WF3 will repair or replace the affected locations before exceeding an environmentally adjusted CUF of 1.0. *Therefore, the WF=3 Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging due to fatigue, including EAF, for the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(iii). 4.0 Time-Limited Aging Analyses Page 4.3-11.

Table 4.3-2 EAF Screening Evaluation NUREG/CR-6260 Generic Plant-Specific M.aterial Location Location Type 1 Reactor vessel shell and Ves'sel shell LAS lower head transition 1 Reactor.vessel shell and Lower head at LAS lower head .-juncture with flow baffle 2 Reactor vessel inlet and Inlet nozzle LAS outlet nozzles 2 Reactor vessel inlet and Outlet nozzle LAs outlet nozzles ' ' 3 Pressurizer l)urge line 'Pressurizers urge LAS (including hot leg and. nozzle _, pressurizer nozzles)' 3 Pressurizer surge lihe Surge line tiot leg. SS r \ (including hot.leg and nozzle safe end pressurizer nozzles) ' 4 Charging system nozzle Charging nozzle SS 5 Safety injection systE!m Safety injection

SS nozzle nozzle loop 1A '.' 6 Shutdown cooling line SOC Line 2 SS 4.0 Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information EAF CUF Fen CUF 0.01 2.45 0.03 0.402 2.45 0.99 " 0.218 2.45 0.53 0.401 2.45 0.98 0.550 2.45 > 1 0.6'.49 15.36 > 1 0.0191 0.293 0.0285 15.36 0.438 0.0379 ' 15.36 0.582 Page 4.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.4 ENVIRONMENTAL QUALIFICATION (EQ) OF ELECTRIC.EQUIPMENT All operating plants must meet the requirements of 10 CFR 50.49, which defines the scope of electrical components to be included in an EQ program and also provides the requirements the EQ program must meet. Qualification entails demonstrating the ability to withstand environmental and service conditions _during nornial plant operation and also those conditions postulated 'for plant accidents. A record of qualification for in-scope components must be prepared and maintained in auditable form, Equipment qualification evaluations for EQ 'components that specify a qualification of at least 40 years, but less than 60 years, are considered TLAAs for license renewal. The WF3 Environmental Qualification (EQ) of Electric.Components (WF3 EQ Program) manages the effects of aging due to component thermal, radiation, and cyclical aging, as applicable, through the use of aging evaluations t;>ased on 10 CFR S0.49(f) qualification methods. As required by 1 O CFR 50.49, EQ components are to be refurbished, replaced, or have their qualification extended prior to reaching the aging limits establ.ished in the evaluation. The WF3 1EQ Program ensures thatthe EQ components are maintainecj in accordance.with their *qualification bases. *' * . The WF3 EQ Program is.an existing program established to meet WF3 for 10 CFR 50.49. The program is consistent with NUREG-1801, Section X.E1, "Environmental Qµalification (EQ) of Electric Components." The WF3 EQ Program will man.age the effects of aging on the intended function(s) of EQ components that are the subject of EQ TLAAs for.the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.4-1 4.5 CONCRETE CONTAINMENT TENDON PRESTRESS Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section is not applicable as WF3 does not have pre-stressed tendons in the containment structure, as identified in FSAR Sections 1.8.1.35 and 3.8. ) 4.0 Time-Limited Aging Analyses Page 4.5-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATIONS FATIGUE ANALYSIS As identified in, FSAR Section 3.8.2.3, the containment vessel was designed to exhibit a general elastic behavior under accident and earthquake conditions of loading. No permanent deformations due to primary stresses have been permitted in the design under any condition of loading. A fatigue evaluation was not performed for the containment vessel design. ' WF3 has penetration bellows that are reviewed as part of the structural aging management reviews. As described in FSAR Section 3.6.2.4, these bellows are designed for a minimum of 7000 thermal cycles and 200 design seismic movements (cycles). This number of cycles is more than these expansion joints will experience through the period of extended operation. The analyses remain valid in accordance with 10 CFR 54.21 (c)(1)(i). 4.0 Time-Limited Aging Analyses Page 4.6-1

4. 7 OTHER PLANT-SPECIFIC TLAAS 4.7.1 Crane Load Cycle Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Cranes that were designed to Crane Manufacturer's Association of America Specification #70 (CMAA-70) have cycles specified as part of their design analysis. Even though crane analyses do not involve time-limited assumptions defined by the current operating term, for 40 years, crane cycle limits are nevertheless evaluated as a TLAA for cranes that were designed to CMAA-70. . CMAA-70 (1975 Edition) Table 3.3.3.1.3-1 identifies crane service classes with corresponding ranges of loading cycles .. According to CMAA-70, Service Class A 1 cranes are designed for up* to 100,000 loading cycles. A review of the cranes at WF3 determined that cranes that were . designed to CMAA-70 are the polar.crane, fuel handling building (FHB) crane, and the radwaste cask handling* bridge.crane (located in the auxiliary building). (Ref. 4-15) The* expected number of applicable crane cycles is below the top of the lowest cyclic loading range in CMAA-70of100,000 cycles, and the associated TLAAs remain valid for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(i): 4. 7.2 Leak-Before-Break An.alysis

FSAR Section 3.6.3 that a (LBB) analysis was used to eliminate from the structural design bases the dynamic effects of double-ended guillotine breaks and e,quivalent longitudinal breaks. LBB analyses consider the thermal aging of cast austenitic stainless steel (CASS) piping and fatigue transients that drive flaw growth. during plant operation. _Because these two analysis considerations could involve time-limited assumptions defined by the current term of operation, LBB analyses were further reviewed as potential TLAAs ,for W.F3. The applicable locations are the main coolant loop and the line. Thermal Aging of CASS Thermal aging results in an increase in the yield strength of CASS. and a decrease in its fracture toughness. Bounding fracture toughness values were used in the evaluation for the main coolant loop and the pressurizer surge line components (Ref. 4-5). Since LBB evaluations use saturated (fully aged) fracture toughness properties, the evah.,1ation of the thermal aging of CASS portion of the'analysis does not have a material* property and is not a TLAA. Fatigue Crack Growth The LBB analysis determined that fatigue crack growth effects will be very small when analyzing for the full set of design transients. The fatigue crack growth analysis is considered a TLAA. The basis of the evaluation of fatigue crack effects in the LBB analysis will remain unchanged 4.0 Time-Limited Aging Analyses Page 4.7-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information if the number of transient occurrences remains below the number assumed for the analysis of fatigue crack growth effects. Continued implementation of the WF3 Fatigue Monitoring Program provides reasonable assurance that the fatigue crack growth analysis will remain valid during the period of extended operation. Therefore, the Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging associated with the LBB fatigue crack growth analyses for the main coolant loops and pressurizer surge line piping for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iiif 4.7.3 Postulation of High Energy Line Break <HELBl Locations As described in FSAR Section 3.6.2.1.1.2, ASME Section Ill, Code Class 1 piping (excluding RCS loop and surge piping) rupture locations have been postulated in any piping run or brarich at terminal ends and other intermediate points in accordance with Regulat_or}t Guide 1.46, Protection Against Pipe Whip Inside Containment (May 1973) and Branch Technical Position MEB 3-1 issued with Genei-ic Letter 87-11, Relaxation in Arbitrary.Intermediate Pipe Rupture Requirements. Postulated rupture locations for Class 1 piping are as follows. (1) Terminal points,* * * (2) Any intermediate points between terminal ends where the CUF exceeds 0.1 (based upon normal and upse(plant conditions and operating basis earthquake [OBE]). (3) Any intermediate points between terminal ends where the primary plus secondary "stress intensities derived on an elastic basis is greater than* 2:0 Sm in ferritic and 2.4 Sm* in austenitic piping materials (based on normal and upset plant conditions and OBE). . A fatigue analysis to determine a CUF for the intermediate points* is considered a TLAA. The Fatigue Monitoring Program (Section B.1.11) identifies when the transients affecting high-energy piping systems are approaching their analyzed number of cycles. Therefore, the CUF
calculations used to determine HELB postulated break locations are considered TLAAs that will be managed for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iii). 4. 7 :4 Reactor Vessel Internals Evaluations (Other thari Fatigue) During service, reactor vessel internal (RVI) and core support component materials are exp-osed to a high-temperature aqueous environment, fast neutron *irradiation and applied loads. WF3
performed evaluations to assess the effect of the extended power Uprate (EPU) conditions on the potential for degradation of the RVI component materials. The evaluation addres$ed age-related
degradation mechanisms of materials that could be affected by the reactor coolant temperature and by neutron and gamma irradiation. The evaluations found that neutron and gamma flux are lower than considered in the original design: Therefore, the level of irradiation-induced enibrittlement was not expected to change significan!IY with the uprate. Also, embrittlement of 4.0 Time-Limited Aging Analyses Page4.7-2 Waterford Steam Electric Station, Unit 3 License Renewal Application -Technical Information -* CASS components as a result of thermal aging and neutron irradiation was not significantly affected by the power uprate. However, evaluations performed associated with the extended power uprate process to determine the -effects of flu'ence on RVI components are considered TLAAs as they were based on operation only until the end of the original 40-year operating term. (Ref. 4-16) -In development of MRP-227-A, the considered degradation mechanisms associated with irradiation during plant operation. The inspection and evaluation guidelines of MRP-227-A thus are designed to manage the effeets of aging of RVI. The WF3 Reactor Vessel lriternals-.Program incorporates the guidance of MRP-227-A. Therefore, the effects of aging associated with RVI TLAAs will be managed by the Vessel Internals Program for the period of extended operation in accordance with .10 CFR 54.21 (c)(1 )(iii). (Ret 4-21, 4-22). --4.0 Aging Analyses Page 4.7-3 )

4.8 REFERENCES

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4-1 NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR 54.., The License Renewal Rule, Revision 6, June 2005. 4-2 NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 2010. 4-3 NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, December 2010. 4-4 EPRI Report TR-105090, Guidelines to Implement the License Renewal Technical Requirements of 10 CFR 54 for Integrated Plant Assessments and Time-Limited Aging

Analyses, November 1995. 4-5 CEN-367-A, Revision 000, "Leak-Before-Break" Evaluation of Primary Coolant Loop.Piping .. in Combustion Engineering Designed Nuclear Steam Supply Systems," prepared for the C-E Owners' Group, February 1991. 4-6 10 CFR 50 Appendix G, Fracture Toughness Requirements. 4-7 10 CFR 50 Appendix H, Reactor Vessel Material Surveillance Program Requirements. 4-8 NRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Vessel Neutron Fluence,'*March 2001. 4-9 non-proprietary, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," J. D. Andrachek et al., May 2004, 4-1 O WCAP:..16083-NP-A, Revision 0, "Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry," S. L. Anderson, May 2006. 4-11 WCAP-18002-NP, "Waterford Unit 3 Time-Limited Aging Analysis on Reactor Vessel Integrity," July 2015. 4-12 NRC Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2. 4-13 1 O CFR Part 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock, D.ecember 1995, 4-14 WCAP-17969-NP, Analysis of Capsule 83° from the Entergy Operations, Inc. Waterford , Unit 3 Reactor Vessel Radiation Surveillance Program, Revisio!l 0, April 2015 .. 4.0 Time-Limited Aging Analyses Page 4.8-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4-15 CMAA-70, Crane Manufacturers Association of America Specification #70, Specifications for Electric Overhead Traveling Cranes, 1975 Edition. 4-16 W3F1-2003-0074, License Amendment Request NPF-38-249, Extended Power Uprate Waterford Steam E.lectric Station, Unit 3, November 13, 2003. 4-17 NUREG/CR-5704 (ANL-98/31), Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, April 1999. 4-18
NUREG/CR-6260 (INEL 95/0045), Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, February 1995. 19 NUREG/CR-6583 (ANL-97/18), Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, February 199.8. 4-20 NUREG/CR-6909 (ANL-06/08), Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, February 2007. 4-21 LTR-Cl-03-63*, 3716 MWt Power Uprate Waterford 3 Reactor Vessel Internals Materials Evaluation, Revision 1 (from Westinghouse Proprietary Class 2). ,* 4-22 CWTR3-15-16*, Fluence for Reactor Vessel Internals Aging Management, July 30, 2015. *Document is a proprietary document. 4.0 Time-Limited Aging Analyses Page 4.8-2 LICENSE RENEWAL APPLICATION WATERFORD STEAM ELECTRIC STATION, UNIT 3 FACILITY OPERATING LICENSE NPF-38 MARCH 2016

( "" .. PREFACE Waterford Steam Electric Station, Unit 3 . License Renewal Application .The following describes the information location, layout, and editorial conventions in the Waterford steam Electric Station, Unit 3 (Waterford 3 or WF3) License Renewal Application (LRA) (hereinafter referred to as "this application" or "the application"). Abbreviated names and acronyms used throughout the application are defined at the end of this preface. Commonly understood terms (such as U.S.) and terms used only in referenced document numbers may not be identified in this table. Regulatory documents such as NUREG-1801, Generic Aging Lessons Learned (GALL) Report, and 10 CFR 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants, may be referred to by the documel')t number, i.e., NUREG-1801 and 1 O CFR 54, respectively. References to tre FSAR are to the updated Waterford 3 Final Safety Analysis Report, Revision 308. Section 1 provides administrative inforrnation required by 1 O CFR 54.17 and 1 O CFR 54.19. Section 2 describes and justifies the methods used to determine the systems and structures within the scope of license renewal and the structures and components subject to aging management review. The results of the system and structure scoping are provided in Tables 2.2-1 through 2.2-5. Tables 2.2-1, 2.2-2 and 2.2-4 list mechanical systems, electrical and instrumentation and controls (l&C) systems, and structures, respectively, within the scope of . . license renewal. Tables 2.2-3 and 2.2-5 list the systems and stn.ictures, respectively, not within *the scope of license renewal. Section 2* also provides descriptions of in-scope systems and structures and their intended functions with tables* identifying components and commodities requfring aging management review and their component intended functions. References are provided to the results of the aging management reviews in Section 3.

The descriptions of systems in Section 2 identify license renewal drawings that depict the components subject to . aging management review for mechanical systems. The drawings are provided in a separate
submittal. Section 3 describes the results of aging management reviews of mechanical, electrical and structural components*requiring agir:ig management review. Section 3 is divided into sections that address (1) the reactor vessel, internals, and reactor coolant system, (2) engineered_ safety features, (3) auxiliary systems, (4) steam and power conversion systems, (5) containments, structures and component supports, and (6) electrical and l&C. The tables in Section 3 provide a summary of information concerning aging effects requiring management and applicable aging management prpgrams for component and commodity groups subject to aging management review. The information presented in the tables is based on the format and content of NUREG-1800, Standard Review Plan [SRP] for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U.S. Nuclear Regulatory Commission (NRG), December 2010, as modified by applicable NRG Interim Staff Guidance (ISG) documents for license renewal. The tables include comparisons with the evaluations documented in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, U.S. NRG, December 2010, as modified by applicable NRG ISG documents for license renewal.

Waterford Steam Electric Station, Unit 3 License Renewal Application Section 4 addresses time-limited aging analyses, as defined by 1 O CFR 54.3. It includes identification of the component or subject and an explanation of the time-dependent aspects of the calculation or analysis. Section 4 demonstrates whether (1) the analyses remain valid for the period of extended operation, (2) the analyses have been projected to the end of the period of extended operation, or (3) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation. Section 4 also documents the determination that no plant-specific exemptions granted pursuant to 1 O CFR 50: 12 that are based on time-limited aging analyses as defined in 10 CFR 54.3 will remain in effect. Appendix A, Final Safety Analysis Report Supplement; provides a summary description of programs and activities for managing the effects of aging for the period of extended operation. A summary description of the evaluation of time-limited aging analyses for the period of extended operation is also included. Following issuance of the renewed license, the material contained in this appendix will be incorporated into the updated.FSAR. The information in Appendix A fulfills the requirements in 10 CFR 54.21 (d). Table 3.0-1, "FSAR Supplement for Aging Management of Applicable Systems," from Revision 2 of NUREG-1800 was used as guidance.for the content of the applicable management program summaries. Appendix B; Aging Management Programs and Activities, describes aging management programs and activities that will manage aging effects on components and structures within the scope of license renewal slich that they will continue to perform their intended functions consistent with the current licensing basis for the period of extended .operation. Appendix B contains a comparison of site programs to the programs* evaluated in NUREG-1801. *The information in Section 2, Section 3, and Appendix B fulfills the*Tequirements of 10 CFR 54.21 (a). . \. Appendix C, Response to Selected Applicant/Licensee.Action Items for Inspection and Evaluation Guidelines for PWR Internals, provides the Waterford 3 response to applicant action items identified in the Nuclear Regulatory Commission (NRC) safety evaluation (SE) of MRP-227, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines." Appendix D, Technical Specification Changes, documents that no technical specification changes are necessary to manage the effects of aging during the peribd of extended operation. The information in Appendix D fulfills the requirements in 1 O CFR 54.22. Appendix E is the environmental information that fulfills the requirements of 1 O CFR 54.23 and 10 CFR 51.53(c). ii \ ) Abbreviation or Acronym AC ACC ACI ACSR ADG AE AEM Al AMP AMR ANSI ANP ARM ARR AS ASME ASTM ATWS BAM BO BM BTP BWR c CAP CASS Waterford Steam Electric Station, Unit 3 License Renewal Application ABBREVIATIONS AND ACRONYMS Description alternating current auxiliary component cooling water American Concrete Institute aluminum conductor steel reinforced auxiliary diesel generator air evacuation aging effect/mechanism aluminum aging management program aging management review American National Standards Institute annulus negative pressure area radiation monitoring airborne radioactivity removal auxiliary steam American Society of Mechanical Engineers American Society for Testing and Materials anticipated transient without scram boric acid makeup blowdown boron management Branch Technical Position boiling water reactor centigrade containment atmosphere purge cast austenitic stainless steel iii Abbreviation or Acronym CAR CB cc ccs ccws CD CE CEA CED CEDM CF CFR Cll CLB CMU cs CSP Cu CUF CVAS eve CVR cw DC OCT EAF Description Waterford Steam Electric Station, Unit 3 License Renewal Application containment atmosphere release containment building component cooling water containment cooling HVAC system component cooling water system condensate conducts electricity, Combustion Engineering control element assembly control element drive control element drive mechanisms chemical feed, chemistry factor Code of Federal Regulations containment inservice inspection current licensing basis condensate makeup and storage containment spray, core shroud condensate storage pool copper cumulative usage factor controlled ventilation area system chemical and volume control containment vacuum relief circulating water direct current dry cooling tower reference temperature change environmentally assisted fatigue iv Abbreviation or Acronym EBA ECCS EOG EFPY EFW EN EPRI .' , . EQ ESF ext FAC FB FC FD Fen FHS FLB FP FS FSAR ft-lb FW GALL GL GSI GWM Description Waterford Steam Electric Station, Unit 3 License Renewal Application emergency breathing air emergency core cooling system emergency diesel generator

effective full power years emergency feedwater enclosure protection Electric Power*Research Institute environmental qualification engineered safety feature external flow-accelerated corrosion fire barrier flow control flow distribution environmentally assisted fatigue correction factor fuel handling and storage flood barrier fire protection fuel pool cooling and purification Final Safety Analysis Report foot-pound main feedwater Generic Aging Lessons Learned [NUREG-1801 report] Generic Letter Generic Safety Issue gaseous .waste management v Abbreviation or Acronym H&V HOPE HELB HEPA HPSI HRA HS HVAC HVC HVD HVF HVR HVT l&C IA ICI ICl/HJTC-CET ILRT IN INPO int IPA ISG ISi ksi KV or kV Description heating and ventilation high density polyethylene high-energy line break high efficiency particulate air Waterford Steam Electric Station, Unit 3 License Renewal Application high pressure safety injection hydrogen recombiners and analyzers heat sink heating, ventilation, and air conditioning control room heating, ventilation, and air conditioning hot machine shop and decontamination facility ventilation fuel handling building HVAC reactor auxiliary building HVAC turbine building ventilation instrumentation and control instrument air incore instrumentation I Cl/heated junction thermocouple-core exit thermocouples integrated leakage rate test insulation; [NRG] Information Notice Institute of Nuclear Power Operations internal integrated plant assessment Interim Staff Guidance inservice inspection kilo-pounds per square inch kilo-volt vi

'-._ _ __,Jr Abbreviation or Acronym LAS LLRT LOCA LPSI LR LRA LREH LRT MB MEB MeV MIC MS MSIV MSL MSLB MWe MWt NA n/cm2 NOE NEI NFPA NG Ni NPIS NPS. Description

low alloy steel local leakage rate test . loss of coolant accident Waterford Steam Electric Station, Unit 3 License Renewal Application low pressure safety injection system license renewal license renewal. application License Renewal Electrical Handbook leak rate testing missile barrier metal enclosed bus million electron-volts microbiologically induced corrosion main steam; Mississippi main steam isolation valve mean sea level * , main steam line break" megawatts-electrical megawatts-thermal neutron absorption; not applicable neutrons per square centimeter nondestructive examination Nuclear Energy Institute National Fire Protection Association nitrogen nickel nuclear plant island structure nominal pipe size vii Abbreviation or Acronym NRC NSSS OBE OE OVHLL PB PCSR pH PH PM PMP PMU PRM PSL PSPM P-T PVC PW PWR PWST QA RAB RC RCC RCP Waterford Steam Electric Station, Unit 3 Description Nuclear Regulatory Commission r nuclear steam supply system operating basis earthquake operating experience Overhead Heavy Load and Light Load pressure boundary permanent cavity seal ring potential of hydrogen precipitation-hardened preventive maintenance probabl_e maximum precipitation primary makeup * -process radiation monitoring primary sampling License Renewal Application .. _ / periodic surveillance and preventive maintenance pressure-temperature polyvinyl chloride potable water pressurized water reactor primary water storage tank quality assurance reactor auxiliary building reactor coolant reactor cavity cooling reactor coolant pump viii Abbreviation or Acronym RCPB RCS RG RPV RTNDT RWSP SA *s&PC SBO SBV SCBA sec SE SER SG SI SIS
SIT SNS S02 SP SRE SRP SS SSC SSR STAMR svs Description Waterford Steam Electric Station, Unit 3 License Renewal Application reactor coolant pressure boundary reactor coolant system Regulatory Guide
reactor pressure vessel (synonymous with reactor reference temperature (nil-ductility transition) refueling water storage pool service air steam and power conversion station blackout shield building ventilation self-contained breathing apparatus supplementary chiller condensing; stress corrosion cracking Safety Evaluation Significant Event Report steam generator safety injection safety injeCtion system safety injection tank support for Criterion (a)(2) equipment sulfur dioxide sump pump support for Criterion (a)(3) equipment [NUREG-1800, License Renewal] Standard Review Plan site security; stainless steel system, structure, or component support for Criterion (a)(1) equipment subject to aging management review cable vault and switchgear ventilation ix Abbreviation or Acronym TC TGB TLAA, TLAAs TRM TSP TW USE v yr Zn Description turbine b.uilding cooling water turbine generator building Waterford Steam Electric Station, Unit 3 License Renewal Application time-limited aging analysis, time-limited aging analyses Technical Requirements Manual trisodium phosphate dodecahydrate treated water upper-shelf energy volt year zinc one-fourth of the way through the vessel wall measured from the internal surface of the vessel x TABLE OF CONTENTS Waterford Steam Electric Station, Unit 3 License Renewal Application 1.0 ADMINISTRATIVE INFORMATION ............................... 1-1 1.1 GENERAL INFORMATION ............................................... 1-1 1.1.1 Name of Applicant .................................................... 1-1 1.1.2 Address of Applicant .................................................. 1-1 1.1.3 Description of Business of Applicants ..................................... 1-2 1.1.4 Legal Status and Organization .......................................... 1-2 1.1.5 Class and Period of License Sought ...................................... 1-5 1.1.6 Alteration Schedule ...................... , ............................ 1-5 1.1. 7 Regulatory Agencies with Jurisdiction ..................................... 1-5 1.1.8 Local News Publications ............................................... 1-6 1.1.9 Conforming Changes to Standard Indemnity Agreement ...................... 1-6 1.1.10 Restricted Data Agreement ............................................. 1-7 1.2 PLANT DESCRIPTION .................................................. 1-7 2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RES UL TS ................................. 2.0-1 2.1 SCOPING AND SCREENING METHODOLOGY .............................. 2.1-1 2.1.1 Scoping Methodology ................................................. 2.1-1 2.1.1.1 Application of Safety-Related Scoping Criteria ............................ 2.1-3 2.1.1.2 Application of Criterion for Nonsafety-Related SSCs Whose Failure Could Prevent the Accomplishment of Safety Functions ... , ..................... 2.1-5 2.1.1.3 Application of Criterion for Regulated Events ............................. 2.1-7 2.1.2 Screening Methodology ................................................ 2.1-11 2.1.2.1 Screening of Mechanical Systems ..................................... 2.1-12 2.1.2.2 Screening of Structures ............................................. 2.1-17 2.1.2.3 Electrical and Instrumentation and Control Systems ....................... 2.1-19 2.1.2.4 Consumables ..................................................... 2.1-20 2.1.3 Interim Staff Guidance Discussion ....................................... 2.1-21 2.1.4 Generic Safety Issues ................................................. 2.1-23 xi Waterford Steam Electric Station, Unit 3 License Renewal Application 2.1.5 Conclusion .......................................................... 2.1-24 2.1.6 References ......................................................... 2.1-25 / 2.2 PLANT LEVEL SCOPING RESULTS ....................................... 2.2-1 2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS .........*... 2.3-1 2.3.1 Reactor Coolant System .................................. * ........... *. 2.3-1 2.3.1.1 Reactor Vessel .................................................... 2.3-3 2.3.1.2 Reactor Vessel Internals ............................................. 2.3-8 2.3.1.3 Reactor Coolant Pressure Boundary ............ : ...................... 2.3-12 2.3.1.4 Steam Generators ................................................. : 2.3-18 2.3.1.5 RCS Systems in Scope for 1 O CFR 54.4(a)(2) ........................... : 2.3-24 2.3.2 Engineered Safety Features ....................... * .................... 2.3-29 2.3.2.1 Containment Spray ..... '. .... _ ........ : ....... ,, ................ *, . ,. ... 2.3-30 2.3.2.2 Safety Injection ..................................................... 2.3-33 2.3.2.3 Containment Penetrations ........................................... 2.3-37 2.3.2.4 ESF Systems in Scope for 10 CFR 54.4(a)(2) ..................... * ....... 2.3-42 Auxiliary Systems ................................................... 2.3-47 2.3.3.1 Chemical and Volunie Control ...... * ........................... * ....... *2.3-48 2.3.3.2 Chilled Water .......................................... : .......... 2.3-52 2.3.3.3 Component Cooling and Auxiliary Component Cooling Water ...... * .......... *2.3-55 2.3.3.4 Compressed Air ....................... * ......................... -... 2.3-61 2.3.3.5 Containment Cooling HVAC ... ; ....... '.: .... :* ...................... .'. 2.3-66 2.3.3.6 Control Room HVAC .. _ ........................................... : .. 2.3-69 2.3.3.7 Emergency Diesel Generator ................ ; ........................
2.3.3.8 fire Protection: Water ........... , .................................... 2:3-77 2.3.3.9 Reactor Coolant Pump Oil_ Collection ................................... 2.3-82 2.3.3.1 O Fuel Pool Cooling and Purification ..................................... 2.3-85 2.3.3.11 Nitrogen ......................................................... 2.3-89 2.3.3.12 Miscellaneous HVAC ............................................... 2.3_-93 2.3.3.13 Auxiliary Diesel Generator ........................................... 2.3-102 2.3.3.14 Plant Drains ...................................................... 2.3-105 2.3.3.15 Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2) ......................... 2.3-110 2.3.4 Steam and Power Conversion Systems ................................. 2.3-169 2.3.4.1 Condensate Makeup and Storage ..................................... 2.3-170 xii _j I_ Waterford Steam Electric Station, Unit 3 License Renewal Application 2.3.4.2 Emergency Feedwater ........................ , ........... * .......... 2.3-174 2.3.4.3 Main Feedwater ................................................... 2.3-177 2.3.4.4 Main Steam ....................................................... 2.3-180 2.3.4.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) ........ 2.3-185 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES .................. ... 2.4-1 2.4.1 Reactor Building ..................................................... 2.4-2 2.4.2 Nuclear Plant Island Structure ........................................... 2.4-11 2.4.3 Turbine Building and Other Structures .................................... 2.4-20 2.4.4 Bulk Commodities ........................... : ........................ 2.4-29 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND . INSTRUMENTATION AND CONTROL SYSTEMS ............................. 2.5-1 3.0 AGING MANAGEMENT REVIEW RES UL TS ...........*............ 3.0-1 3.1 REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM .......... 3.1-1 3.1.1 Introduction .............................. -........................... 3.1-1 3.1.2 Results .............................................................. 3.1-1 3.1.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs ........................................ 3.1-2 3.1.2.2 Further Evaluation of Aging *Management as Recommended by NUREG-1800 .. 3.1-7 3.1.2.3 Time-Limited Aging Analyses ................... * ...................... 3.1-11 3.1.3 Conclusion ..................................... -...................... 3.1-11 3.2 ENGINEERED SAFETY FEATURES .................... ................ ; . 3.2-1 3.2, 1 Introduction .......................................................... 3.2-1 3.2.2 Results .... _ .............. :* ..................... : .............. * ...... 3.2-1 3.2.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs ........................................ 3.2-1 3.2.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.2-6. 3.2.2.3 Time-Limited Aging An_alyses ......................................... 3.2-7 3.2.3 Conclusion .......................................................... 3.2-7 xiii Waterford Steam Electric station, Unit 3 License Renewal Application \ / 3.3 AUXILIARY SYSTEMS .................................................. 3.3-1 3.3.1 Introduction ............ *. : ........................................... 3.3-1 3.3.2 Results ............................................................. 3.3-1 3.3.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Managen:ient Programs ........................................ 3.3-5 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.3-22 3.3.2.3 Time-Limited Aging Analysis .......................................... 3.3-24 3.3.3 Conclusion ......................................................... : 3.3-24 3.4 STEAM AND POWER CONVERSION SYSTEMS ............................. 3.4-1 3.4.1 Introduction ......................................................... 3.4-1 3.4.2 Results ............................................. * ....... * .......... 3.4-1 3.4.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs ............. _ ......... : ....... : ......... 3.4-2 3.4.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.4-7
3.4.2.3 Time-Limited Aging Analysis .......................................... 3.4-8 . 3.4.3 Conclusion .......................................................... 3.4-8 3.5 CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS .............. 3.5-1 3.5.1 Introduction ........ : ................................................. 3.5-1 3.5.2 Results ...................................... : ...................... 3.5-1 3.5.2.1 Materials, Environments, Aging Effects Requiring Management.and Aging Management Programs ........................................ 3.5-1 3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.5-6 3.5.2.3 Time-Limited Aging Analysis ...........................*........ , ..... 3.5-17 3.5.3 Conclusion ......................................................... _. 3.5-17 . 3.6 ELECTRICAL AND INSTRUMENTATION AND CONTROLS .................. : . 3.6-1 3.6.1 Introduction .......................................................... 3.6-1 3.6.2 Results .............................................................. 3.6-1 3.6.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs ........................................ 3.6-1 3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 .. 3.6-3 3.6.2.3 Time-Limited Aging Analysis ........................ : ................. 3.6-9 3.6.3 Conclusion ............ : ............................................. 3.6-9 xiv Waterford Steam Electric Station, Unit 3 License Renewal Application 4.0 TIME-LIMITED AGING ANALYSES .............................. 4.1-1 4.1 IDENTIFICATION OF TIME-LIMITED AGING ANALYSES ...................... 4.1-1 4.1.1 Identification of TLAAs ................................................. 4:1-2 4.1.2 Identification of Exemptions .......................................... _ .. *. *. 4.1-3 4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT * ........................... 4.2-1 4.2.1 Reactor Vessel Fluence ........ : ....................................... 4.2-1 4.2.2 Upper-Shelf Energy ................................................... 4.2-6 4.2.3 Pressurized Thermal Shock ............................................ 4.2-10 4.2.4 Pressure-Temperature Limits ........................................... 4.2-15 4.2.5 Low-Temperature Overpressure Protection (L TOP) Setpoints .................. 4.2-15 4.3 METAL FATIGUE ...................................................... 4.3-1 4.3.1 Class 1 Fatigue ............... * ....................................... 4.3-2 4.3.1.1 Reactor Vessel .... ............................................... 4.3.1.2 ReactorVessel Internals ....................................... , ...... 4.3-5 4.3.'1.3 Pressurizer ....................................................... 4.3.1.4 Steam Generators .................................................. 4.3-6 4.3.1.5 Control Element Drive Mechanisms .................................... 4.3-6 4.3.1.6 Reactor Coolant Pumps ............................................. 4.3-7 4.3.1.7 Reactor Coolant System Class 1 Piping ........... ._ ............... * ...... 4.3-7 4.3.2 Non-Class 1 Mechanical Systems ........................... , ............ 4.3-8 4.3.2.1 Nori-Class 1 Pressure Boundary Piping Using Stress Range Reduction Factors . 4.3-8 4.3.2.2 Flexible Connections and Expansion Joints .............................. 4.3-8 4.3.2.3 Non-Class 1 Heat Exchangers with Fatigue Analysis ....................... 4.3-8 4.3.3 Effects of Reactor Water Environment on Fatigue Life ........................ 4.3-9 4.4 ENVIRONMENTAL QUALIFICATION (EQ) OF ELECTRIC EQUIPMENT ........... 4.4-1 4.5 CONCRETE CONTAINMENT TENDON PRESTRESS .......................... 4.5-1 4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATIONS FATIGUE ANALYSIS ................................................... 4.6-1 xv Waterford Steam Electric Station, Unit 3 License Renewal Application 4.7 .OTHER PLANT-SPECIFIC TLAAS ......................................... 4.7-1 4.7.1 Crane Load Cycle Analysis ............................................. 4.7-1 4.7.2 Leak-Before-Break Analysis ............................................ 4.7-1 4.7.3 Postulation of High Energy Line Break (HELB) Locations ...................... 4.7-2 4.7.4 Reactor Vessel Internals Evaluations (Other than Fatigue) ..................... 4.7-2

4.8 REFERENCES

......................................................... 4.8-1 xvi LIST OF APPENDICES Appendix A: Final Safety Analysis Report Supplement Appendix B: Aging Management Programs and Activities Waterford Steam Electric Station, Unit 3 License Renewal Application Appendix C: Response to Selected Applicant/Licensee Action Items for Inspection and Evaluation Guidelines for PWR Internals Appendix D: Technical Specification Changes Appendix E: Applicant's Environmental Report, Operating License Renewal Stage xvii Waterford Steam Station, Unit 3 License Renewal Application _ .. _, LIST OF TABLES Table 2.0-1 Component Intended Functions: Abbreviations and Definitions ................... 2.0-2 Table 2.2-1 Mechanical Systems Within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . 2.2-3 Table 2.2-2 Mechanical Systems Not Within the Scope of License Renewal ................... 2.2-7 Table 2.2-3 Plant Electrical and l&C Systems Within the Scope of License Renewal. ............ 2.2-9 Table 2.2-4 Structures Within the Scope of License Renewal ............... *.-............... 2.2-11 Table 2.2-5 Structures Not Within the Scope of License Renewal ........................... 2.2-12 Table 2.3.1-1 Reactor Vessel Components Subject to Aging Management Review ............................ 2.3-6 Table 2.3.1-2 Reactor Vessel Internals Components Subject to Aging Management Review ................ , ........... 2.3-10 Table 2.3.1-3 Reactor Coolant Pressure Boundary Components Subject to Aging Management Review ............................ 2.3-15 Table 2.3.1-4 Steam Generators Components Subject to Aging Management Review ............................ 2.3-21 Table 2.3.1-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-.27 Table 2.3.1-5-2

Steam Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-28 xviii Table 2.3.2-1 Containment Spray System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review .................... '. : ...... 2.3-32 Table 2.3.2-2 Safety Injection System Components Subject to Aging Review .................... * ........ 2.3-36 Table 2.3.2-3 Containment Penetrations Components Subject to Aging Management Review ........... : . : .............. 2.3-41 Table 2.3.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-45 Table 2.3.2-4-2 Safety Injection System . Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-46 Table 2.3.3-1 Chemical and Volume Control System Components Subject to Aging Management Review ............................ 2.3-51 Table 2.3,3-2 Chilled Water System Components Subject to Aging Management Review ............................ 2.3-54 Table 2.3.3-3 Component Cooling and Auxiliary Component Cooling Water Systems Components Subject to Aging Management Review ......................... _ ... 2.3-60 Table *2.3.3-4 Compressed Air Systems Components Subject to Aging Management Review .......................... , . 2.3-65 Table 2.3.3-5 Containment Cooling HVAC System Components Subject to Aging Management Review ............................ 2.3-68 Table 2.3.3-6 Control Room HVAC System Components Subject to Aging Management Review ............................ 2.3-71 xix Table 2.3.3-7 Emergency Diesel Generator System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review ............................ 2.3-75 Table 2.3.3-8 Fire Protection: Water System Components Subject to Aging Management Review ............................ 2.3-81 Table 2.3.3-9 RCP Oil Collection System Components Subject to Aging Management Review ............................ 2.3-84 Table 2.3.3-10 Fuel Pool Cooling and Purification System Components Subject to Aging Management Review ............................ 2.3-88 Table 2.3.3-11 Nitrogen System Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-92 Table 2.3.3-12 Miscellaneous HVAC Systems Components Subject to Aging Management Review ............................ 2.3-101 Table 2.3.3-13 Auxiliary Diesel Generator System Components Subject to Aging Management Review ............................ 2.3-104 Table 2.3.3-14 Plant Drains Components Subject to Aging Management Review ............................ 2.3-109 Table 2.3.3-15-1 Air Evacuation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-133 Table 2.3.3-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-134 . xx Table 2.3.3-15-3 Annulus Negative Pressure System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review ............................ 2.3-135 Table 2.3.3-15.-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .................. : .. ...... 2.3-136 Table 2.3.3-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review, ........................... 2.3:.137 Table 2.3.3-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......................... ' .. * .. 2.3-138 Table 2.3.3-15-7 Chemical and Volume Control System Nonsafety-Relate.d Components Affecting Safety-Related Systems* Components Subject to Aging Management Review .................... *:* ....... 2.3-139 Table 2.3.3-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-140 . Table 2.3.3-15-9 Chilled Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-.141 Table 2.3.3-15-10 Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-142 Table 2.3.3-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-143 xxi Table 2.3.3-15-12 Compressed Air System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-144 Table 2.3.3-15-13 Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-145 Table 2.3.3-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-146 Table 2.3.3-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-147 Table 2.3.3-15-16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-148 Table 2.3.3-15-17 Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Subject to Aging Management Review ............................ 2.3-149 Table 2.3.3-15-18 Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-150 Table 2.3.3-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-151 Table 2.3.3-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-152 xxii Table 2.3.3-15-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Hot Machine Shop and Decon Facility Ventilation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......... -................... 2.3-153 Table 2.3.3-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-154 Table 2.3.3-15-23 Liquid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-155 Table 2.3.3-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-156 Table 2.3.3-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-157 Table 2.3.3-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-158 Table 2.3.3-15-27 Primary Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-159 Table 2.3.3-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-160 Table 2.3.3-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-161 xxiii Waterford Steam Electric Station, Unit 3 License Renewal Application '* "' Table 2.3.3-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .......... ; ................. 2.3-162 Table 2.3.3-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ................. * ........... 2.3-163 Table 2.3.3-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .... ; ........................ 2.3-164 Table 2.3.3-15-33 Secondary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review* ............................ 2.3-165 Table 2.3.3-15-34 Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ................... ; ........ 2.3-166 Table 2.3.3-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......... ., .................. 2.3-167 Table 2.3.3-15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting. Safety-Related Systems Components Subject to Aging Management Review .......................... * .. 2.3,.168 2.3.4-1 Condensate Makeup and Storage System Components Subject to Aging Management Review ............................ 2.3-173 Table 2.3.4-2 Emergency Feedwater System Components Subject to Aging Management Review ....................... * ...*. 2.3-176 xxiv

' I I Table 2.3.4-3 Main Feedwater System Waterford Steam Electric Station, Unit 3 License Renewal Application Components Subject to Aging Management Review ............................ 2.3-179 Table 2.3.4-4 Main Steam System Components Subject to Aging Management Review ............................ 2.3-184 Table 2.3.4-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-190 Table 2.3.4-5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ......................... , .. 2.3-191 Table 2.3.4-5-3 Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review." ........................... 2.3-192 Table 2.3.4-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-193 Table 2.3.4-5-5 Main Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review ............................ 2.3-194 Table 2.3.4-5-6 Main Steam System Nonsafety-Related Components Affecting Components Subject to Aging Management Review ............................ 2.3-195 Table 2.4-1 Reactor Building Components Subject to Aging Management Review ............................ 2.4-7 Table 2.4-2 Nuclear Plant Island Structure Components Subject to Aging Management Review ............................ 2.4-17 xxv Waterford Steam Electric Station, Unit 3 J' License Renewal Application Table 2.4-3 . Turbine Building and Other Structures Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-27 Table 2.4-4 Bulk Commodities Components Subject to Aging Management Review ............................ 2.4-31 Table 2.5-1 Electrical and Instrumentation and Control Systems Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-5 Table 3.0-1 Service Environments for Mechanical Aging Management Reviews ................ 3.0-7 Table 3.0-2 Service Environments for Structural Aging Management Reviews ... * ............. . 3.0-10 Table 3.0-3 Service Environments for Electrical Aging Management Reviews .................. 3.0-12 Table3.1.1 Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801 .. : .................................. 3.1-12 Table 3.1.2-1 Reactor Vessel Summary of Aging Management Evaluation Table 3.1.2-2 Reactor Vessel Internals 3.1-49 Summary of Aging Management Evaluation .................................. 3.1-57 Table 3.1.2-3 Reactor Coolant Pressure Boundary Summary of Aging Management Evaluation Table 3.1.2-4 Steam Generators Summary of Aging Management Evaluation Table 3.1.2-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems 3.1-76 3.1-98 Summary of Aging Management Evaluation ................... " . . . . . . . . . . . . . . 3.1-113 xxvi Waterford Steam Electric Station, Unit 3

License Renewal Application Table 3.1.2-5-2 Steam Generators Nonsafety-Related Components Affecting Safety-Related *systems Summary of Aging Management Evaluation .................................. 3.1-118 Table 3.2.1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801 ..................................... 3.2-9. Table 3.2.2-1 Containment Spray System Summary of Aging Management Evaluation 3.2-33 Table 3.2.2-2 Safety Injection System Summary of Aging Management Evaluation 3.2-40 Table 3.2.2-3 Containment Penetrations Summary of Aging Management Eva I uation ................................. . 3.2-46 Table 3.2.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.2-49 Table
Safety Injection System Nonsafety-Related *components Affecting Safety-Related Systems Summar-Y of Aging Management Evaluation .................................. 3.2-51 Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 .................................... 3.3-25 Table 3.3.2-1 Chemical and Volume Control System Summary of Aging Management Evaluation .................................. 3.3-78 Table 3.3.2-2 Chilled Water System Summary of Aging Management Evaluation .................................. 3.3-88 xxvii Table 3.3.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Component Cooling and Auxiliary Component Cooling Water System Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-97 Table 3.3.2-4 Compressed Air System Summary. of Aging Management Evaluation .................................. 3.3-108 Table 3.3.2-5 Containment Cooling HVAC System Summary of Aging Management Evaluation .................................. 3.3-113 Table 3.3.2-6 Control Room HVAC System Summary of Aging Management Evaluation .................................. 3.3-117 Table 3.3.2-7 Emergency Diesel Generator System Summary of Aging Management Evaluation .................................. 3.3-123 Table 3.3.2-8 Fire Protection -Water System Summary of Aging Management Evaluation : ................................. 3.3-138 Table 3.3.2-9 Fire Protection RCP Oil Collection System Summary of Aging Management Evaluation .................................. 3.3-148 Table 3.3.2-10 Fuel Pool Cooling and Purification System Summary of Aging Management Evaluation .................................. 3.3-152 Table 3.3.2-11 Nitrogen System Summary of Aging Management Evaluation .................................. 3.3-156 Table 3.3.2-12 Miscellaneous HVAC Systems Summary of Aging Management Evaluation .................................. 3.3-159 Table 3.3.2-13 Auxiliary Diesel Generator System Summary of Aging Management Evaluation .................................. 3.3-167 xxviii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.3.2-14 Plant Drains Summary of Aging Management Evaluation Table 3.3.2-15-1 Air Evacuation System Nonsafety-Related Components Affecting Safety-Related Systems 3.3-170 Summary of Aging Management Evaluation .................................. 3.3-176 Table 3.3.2-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-177 Table 3.3:2-15-3 Annulus Negative Pressure System Nonsafety-Related Components Affecting Safety-Related Systems. Summary of Aging Management Evaluation ............. * ................ ' ..... 3.3-178 Table 3.3.2-15-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-180 Table 3.3.2-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation ......... *"* ..................... * .. 3.3-184
Table 3.3.2-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-186 Table 3.3.2-15-7 Chemical and Volume Control System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-191 Table 3.3.2-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ............. * ..................... 3.3-195 xx ix Table 3.3.2-15-9 Chilled Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-198 Table 3.3.2-15-10 Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-202 Table 3.3.2-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-205 Table 3.3.2-15-12 Compressed Air System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-209 Table 3.3.2-15-13 Containment Atmosphere Purge .System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-212 Table 3.3.2-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-214 Table 3.3.2-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-215 Table 3.3.2-15".'16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3,..216 Table 3.3.2-15-17 Emergency Diesel Generator*system Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-218 )()()(

Table 3.3.2-15-18 Fuel Handling Building HVAC System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-220 Table 3.3.2-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related' Systems Summary of Aging Management Evaluation ............... : .................. 3.3-222 Table 3.3.2-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-225 Table 3.3.2-15-21 Hot Machine Shop and Decon Facility Vent System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ................................... 3.3-228 Table 3.3.2-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ........ : ......................... 3.3-229 Table 3.3.2-15-23 Liquid Waste Management System

Nonsafety-Related Components Affecting Safety-Related Systems* Summary of Aging Management Evaluation .................................. 3.3-231 Table 3.3.2-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-235 Table 3.3.2-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation .................................. 3.3-237 Table 3.3.2-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-240 xxxi Table 3.3.2-15-27 Primary Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-242 Table 3.3.2-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems. Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-244 Table 3.3.2-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-248 Table 3.3.2-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ................................... 3.3-251 . Table 3.3.2-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-253
Table 3.3.2-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-254 Table 3.3.2-15-33 Secondary Sampling System Nonsafety-Related Co.mponents Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-257 Table Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Agirig Management Evaluation ....... : ....... : .................. 3.3-262 Table 3.3.2-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-264 xxxii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.3.2--15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.3-266 Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801 .................... * ................ *3.4-10 Table 3.4.2-1 Condensate Makeup and Storage System Summary of Aging Management Evaluation Table 3.4.2-2 Emergency Feedwater System 3.4-32 ' Summary of Aging Management Evaluation ............................. .... 3.4-35 Table 3.4.2-3 Main Feedwater System Summary of Aging Management Evaluation Table 3.4.2-4 Main Steam System Summary of Aging Management Evaluation Table 3.4.2-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems 3.4-38 3.4-43 Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-54 Table 3.4.2-5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-60 Table 3.4.2-5-3 Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-62 Table 3.4.2-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation .................................. 3.4-64 xxxiii Waterford Steam Electric Station, Unit 3 License Renewal Application Table 3.4.2-5-5 Feedwater System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ............................... : ... *3.4-65 Table 3.4.2-5-6 Main Steam System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-66 Table 3.5.1 Sur:nmary ofAging Management Programs for Containments, Structures and Component Supports
Evaluated in Chapters II and Ill of NUREG-1801 ............................... 3.5-18 Table 3.5,2-1 Reactor Building Summary of Aging Management Evaluation .................................. 3.5-50 Table 3.5.2-2 Nuclear Plant Island Structure Summary of Aging Management Evaluation .................................. 3.5-61 Table 3.5.2-3 Turbine Building and Other Structures Summary of Aging Management Evaluation Table 3.5.2-4 Bulk Commodities Summary of Aging* Management Evaluation Table 3.6.1 Summary of Aging Management Programs for the EiC Components 3.5-67 3.5-73 Evaluated in Chapter VI of NUREG-1801 ..................................... 3.6-10 Table 3.6.2-1 Electrical and l&C Components Summary of Aging Management Evaluation 3.6-20 Table 4.1-1 List of TLMs .......................................................... 4.1-4 Table 4.1-2 Comparison ofWF3 TLMs to NUREG-1800 Potential TLMs .................... 4.1-6 xxxiv Table 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Calculated Maximum Fast Neutron Fluence (E+19 n/cm2, E > 1.0 MeV) Projections for the WF3 Vessel Welds and Plates at 55 EFPY .............................. 4.2-5 Table 4.2-2 Predicted USE Values at 55 EFPY for WF3 RPV Beltline Materials ................ 4.2-7 Table 4.2-3 Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY ......... 4.2-11 Table 4.3-1 Projected and Analyzed Transient Cycles .................................... 4.3-4 Table 4.3-2 EAF Screening Evaluation ................................................ 4.3-12 xx.xv

( 1.0 ADMINISTRATIVE INFORMATION Waterford Steam Electric Station, Unit 3 License Renewal Application Pursuant to Part 54 of Title 10 of the Code of Federal Regulations (1 O CFR Part 54), this application seeks renewal for an additional 20-year term of the facility operating license for Waterford Steam Electric Station, Unit 3 (Waterford 3). The facility operating license for Waterford 3 (Docket Number 50-382, License Number NPF-38) expires at midnight on December 18, 2024. The application also applies to renewal of those Nuclear Regulatory Commission (NRC) source material, special nuclear material, and by-product material licenses that are subsumed ot combined with the facility operating license. The application is based on guidance provided by the U.S. Nuclear Regulatory Commission in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 201 O, and Regulatory Guide (RG) 1.188, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," Revision 1, September 2005, and guidance provided by the Nuclear E11ergy Institute (NEI) in NEI 95-10, Industry Guidelines for Implementing the. Requirements of 1 O CFR 54 -The License Renewal Rule, Revision 6, Ju.ne 2005. *

The license renewal application is intended to provide sufficient information for the NRC to *complete its tec:hnical and environmental reviews. pursuant tc:> 1 O CFR Parts 54 and 51, respectively. The license renewal application is designed to allow the NRC to make the findings required by 1 O CFR 54.29 in support of the issuance of a renewed facility operating license for. Waterford 3.* 1.1 GENERAL INFORMATION The following is the general information required .bY 1 O CFR 54.17 and 10 CFR 54.19. .. 1.1.1 Name of Applicant Entergy Operations, Inc. Entergy Louisiana, LLC 1.1.2 Address of Applicant Entergy Operations, Inc. 1340 Echelon Parkway Jackson, Mississippi 39213 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, Louisiana 70121 1.0 Administrative Information Page 1-1 Address of Nuclear Facility Waterford Steam Electric Station, Unit 3 Entergy Operations, Inc. 17265 River Road Killona, Louisiana 70057-3093 1.1.3 Description of Business of Applicants Waterford Steam Electric Station, Unit 3 License Renewal Application Entergy Louisiana, LLC, is the owner of Waterford 3, located in St. Charles Parish, Louisiana. Entergy Operations, Inc. (EOI) is the licensed operator of Waterford 3. Entergy Louisiana, LLC, and EOI (hereafter referred to as Entergy) are the holders of Waterford 3 operating license NPF-38 and for purposes of this application are considered the applicant. Entergy Utility Holding Company, LLC, a Texas limited liability company, is an intermediary holding company for Entergy Corporation and the direct parent company of Entergy Louisiana, LLC. Entergy Louisiana, LLC, is one of Entergy Corporation's five retail electric utility subsidiaries. These companies generate, transmit, distribute and sell electric power to retail and wholesale customers in Arkansas, Louisiana, Mississippi, and Texas. EOI is engaged principally in the business of operating nuclear power facilities. Entergy Corporation is an integrated energy company engaged primarily in electric power production and retail distribution operations. 1.1.4 Legal Status and Organization EOI, a Delaware limited liability company, is *a wholly owned subsidiary of Entergy Corporation. The principal office is located in Jackson, Mississippi. EOI is not owned, controlled or dominated by an alien, a foreign corporation, or foreign government. The names and addresses for EOI directors and principal officers are listed below. All are U.S. citizens. Timothy G. Mitchell Director President and Chief Executive Officer Donna Jacobs Director Chief Operating Officer-South 1.0 Administrative Information Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Page 1-2 J /

William F. Maguire Director Vice President, Operations Support Marcus V. Brown Executive Vice President and General Counsel Jeremy G. Browning Vice President, Operations (Arkansas Nuclear One) Michael R. Chisum Vice President, Operations (Waterford 3) Vincent Fallacara Vice President, Operations Support William J. James, Jr. Vice President, Major Fleet Projects Steven C. McNeal Vice President and Treasurer Kevin J. Mulligan Vice President, Operations (Grand Gulf Nuclear Station Eric W. Olson Vice President, Site (River Bend Station) Waterford Steam Electric Station, Unit 3 License Renewal Application Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy* Operations, Inc. 1340 Echelon Parkway Jackson, MS 39213 Entergy Louisiana, LLC is the owner of Waterford 3. As discussed in Section 1.1.3, Entergy Utility Holding Company, LLC is the direct parent company of Entergy Louisiana, LLC. The principal office of Entergy Louisiana, LLC is located in Jefferson, Louisiana. Entergy Louisiana, LLC is not owned, controlled or dominated by an alien, a foreign corporation, or foreign government. 1.0 Administrative Information Page 1-3 Waterford Steam Electric Station, Unit 3 License Renewal Application The names and addresses for Entergy Louisiana, LLC, directors and principal officers are listed below. All are U.S. citizens. Phillip R. May Director and Chairman of the Board President and Chief Executive Officer Theodore H. Bunting, Jr. Director Group President, Utility Operations Paul D. Hinnenkamp Director Andrew S. Marsh Director Executive Vice President and Chief Financial Officer Marcus V. Brown Executive Vice President and General Counsel Joseph T. Henderson

Senior Vice President and General Tax Counsel
Timothy G. Mitchell Senior Vice President and Chief Nuclear Officer Alyson M. Mount Senior Vice President and Chief Accounting Officer Dennis P. Dawsey Vice President, Customer Service John P. Hurstell Vice President, System Planning 1.0 Administrative Information Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, *LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC
4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121
Page 1-4

/ I Waterford Steam Electric Station, Unit 3 License Renewal Application. Mark D. Kleeharnmer Vice President, Regulatory and Public Affairs Steven C. McNeal Vice President and Treasurer Jody Montelaro Vice President, Public Affairs 1.1.5 Class and Period of License Sought . Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 Entergy Louisiana, LLC 4809 Jefferson Highway Jefferson, LA 70121 The applicant requests renewal of the facility operating license for Waterford 3 (facility operating license Docket Number 50-382, License Number NPF-38) for a period of 20 years. The license was issued under Section 103 of the Atomic Energy Act of 1954 as amended. License renewal would extend the Waterford 3 facility operating license from midnight, December 18, 2024, to December 18, 2044. This application also applies to renewal of thoseNRC source material, special nuclear material, and by-product material licenses that are subsumed or combined with the facility operating license. *

1.1.6 Alteration Schedule Entergy does not propose to construct or alter any production or utilization faCility in connection with this renewal application. *
1.1.7 Regulatorv Agencies with Jurisdiction Regulatory agencies with jurisdiction over the station are listed below. Federal Energy Regulatory Commission* 888 First St. N. E. * *
Washington, DC 20426 Department of Environmental Quality-(DEQ) P.O. Box 4313 Baton Rouge, Louisiana 70821-4313 1.0 Administrative Information Page 1-5 Louisiana Public Service Commission P.O. Box 91154 Baton Rouge, Louisiana 70821-9154 Parish President Council St. Charles Parish P.O. Box 302 Hahnville, Louisiana 70057 1.1.8 Local News Publications St. Charles Parish Herald Guide 14236 U.S. 90 Boutte, LA 70039 The Times-Picayune 365 Canal St. New Orleans, LA 70130 The New Orleans Advocate 1010 Common Street Suite 3030 New Orleans, LA 70112 Waterford Steam Electric Station, Unit 3 License Renewal Application 1.1.9 Conforming Changes to Standard Indemnity Agreement 10 CFR 54.19(b) requires that license renewal applications include "conforming changes to the standard indemnity agreement, 1 O CFR 140.92, Appendix B, to account for the expiration term of the proposed renewed license." The current Indemnity Agreement (No. B-92) for Waterford Steam Electric Station, Unit 3, states in Article VII that the Agreement shall terminate at the time of expiration of the license specified in Item 3 of the Attachment (to the Agreement), which is the last to expire. Item 3 of the Attachment to the Indemnity Agreement, as revised through Amendment No. 7, lists Waterford 3 facility operating license number NPF-38. Entergy has reviewed the original Indemnity Agreement and the Amendments. Neither Article VII nor Item 3 of the Attachment specifies an expiration date for license number NPF-38. Therefore, no changes to the Indemnity Agreement are deemed necessary as part of this application. Should the license number be changed by NRC upon issuance of the renewed license, Entergy requests that NRC amend the Indemnity Agreement to include conforming changes to Item 3 of the Attachment and other affected sections of the Agreement. 1.0 Administrative Information Page 1-6 1.1.10 Restricted Data Agreement Waterford Steam Electric Station, Unit 3 License Renewal Application This application does not contain restricted data or national security information, and the applicant does not expect that any activity under the renewed license for Waterford 3 will involve such information. However, if such information were to become involved, the applicant agrees to secure such information appropriately and not to permit any individual to have access to, or any facility to possess, such information until the individual or facility has been approved under the provisions of 1 O CFR Parts 25 or 95, respectively. 1.2 PLANT DESCRIPTION The Waterford 3 site is located on the west (right descending) bank of the Mississippi River near Taft, Louisiana, in the northwest portion of St. Charles Parish. About 3 miles westward is the eastern boundary of St. John the Baptist Parish. The coordinates for the reactor are 29° 59' north latitude and 90° 28' 16" west longitude. Kenner, the nearest population center, is 13 miles east of the site. Approximately 25 miles east-southeast of the site is the city of New Orleans, and approximately 50 miles north-northwest is the city of Baton Rouge. The exclusion radius is taken as 915 meters, and the low population zone is a 2-mile radius. The Nuclear Steam Supply System (NSSS) is a pressurized water reactor designed by Combustion Engineering; Incorporated. The containment structure, designed by Ebasco Services Incorporated, is comprised of a steel containment vess*e1 surrounded by a reinforced concrete shield building. * . WF3 is a pressurized-water reactor plant of the Combustion Engineering design. Since March 1985, WF3 has had two increases in reactor core power level, which has resulted in an increase in design net electrical output from 1, 104 megawatts electric (MWe) to 1, 188 MWe. The first reactor core power level increase from 3,390 megawatts thermal (MWt) to 3,441 MWt occurred in March 2002 and resulted in an increase in design net electrical output of approximately 16 MWe. The second reactor core power level increase from 3,441 MWt tq 3,716 MWt, starting with* Operating Cycle 14, resulted in another increase in design net electrical output of approximately 68 MWe. The principal structure at th.e site is the Nuclear Plant Island Structure (NPIS), which is a reinforced concrete box structure with solid exterior walls. All safety-related components are housed in the NPIS, which is flood protected up to El. +29.27 ft. mean sea level (MSL) (see Section 2.1.1.1 for further information). The NPIS provides a common structure for the reactor building, reactor auxiliary building (which includes the* control room), fuel handling building, and component cooling water system structures (cooling tower areas), as well as a common foundation mat for support of these structures. 1.0 Administrative Information Page 1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Main structures outside the NPIS are the turbine building, water treatment building, condensate polisher building, fire pump house, radioactive material storage building, chiller building, service building, administration building, maintenance support building, and intake and discharge structures, as well as the independent spent fuel storage installation (ISFSI) and various nonsafety-related storage_ tanks (fuel oil, fire water, demineralized water, condensate; and primary water). 1.0 Administrative Information Page 1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RESULTS This chapter describes the process for identification of structures and components subject to aging management review (AMR) in the Waterford 3 integrated plant assessment (IPA). For those_ systems, structures, and components (SSCs) within the scope of license renewal, 1P CFR 54.21 (a)(1) requires the license renewal applicant to identify and list structures and components subject to AMR. Furthermore, 10 CFR 54.21 (a)(2) requires that methods used to identify these structures and components be described and justified. Technical information in this section serves to satisfy these requirements. The scoping and screening method is described in Section 2.1. This method is implemented in accordance with NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR 54 -The License Renewal Rule, Revision 6, June 2005. The results of the _assessment to ** identify the systems and structures within the scope of license renewal (plant level scoping) are in S!3ction 2.2. The results of the identification of the cor:nponents and structural components subject to aging management review (screening) are in Section 2.3 for mecha11ical systems,: Section 2.4 for structures, and Section 2.5 for eleCtrical and instrumentation and control (l&C)'. systems. ' Table 2.0-'1 gives the definitions of component intended functions used in this application for components and structural components. Tables in the application may refer to either the intended function name or to the abbreviation. The term "piping" in component lists includes.pipe and pipe fittings (such as elbows, flued heads and reducers). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results 2.0-1 Abbreviation CE EN FB FC FD FLB FLT HS HT IN MB NA PB Table 2.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Intended Functions: Abbreviations and Definitions Intended Function Definition Conducts electricity Provide electrical connections to specified sections of an electrical circuit to deliver voltage, current or signals. Enclosure protection Provides enclosure, shelter or protection for in-scope equipment (including high-energy line break [HELB], radiation shielding, pipe whip restraint, and thermal shielding). Fire barrier Provide rated fire barrier to confine or retard a fire from spreading between adjacent areas. Flow control Provide control of flow rate or establish a pattern of spray. Flow distribution Provide distribution of flow. Flood barrier Provide flood :Protection barrier. for internal or external flooding events. Filtration Provide removal of unwanted material. Heat sink Provide heat sink during station blackout (SBO) or design basis accidents (includes source of cooling Water for plant shutdown). Heat transfer Provide ability to transfer heat. Insulation Insulate and support an electrical conductor (electrical) or provide insulating characteristics to reduce transfer (structural). Missile barrier Provide barrier against internally or externally generated missile. Neutron absorption Absorb neutrons. Pressure boundary Provide pressure boundary integrity such that adequate flow and pressure can be delivered or provide fission product barrier for containment pressure boundary. This function includes maintaining structural integrity and preventing leakage or spray for 10 CFR 54.4(a)(2) (mechanical). Provide pressure boundary or essentially leak-tight barrier (structural). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.0-2 .r J _,; Abbreviation SNS SRE SSR STR STRSP Table 2.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Intended Functions: Abbreviations and Definitions Intended Function Definition Support for Criterion Provide structural or functional support to nonsafety-related (a)(2) equipment equipment whose failure could prevent satisfactory accomplishment of required safety functions (includes II/I considerations) [10 CFR 54.4(a)(2)]. Support for Criterion Provide structural or functional support to equipment required (a)(3) equipment to meet the Commission's regulations for any of the five regulated events in 10 CFR 54.4(a)(3). Support for Criterion Provide structural or functional support for safety-related (a)(1) equipment equipment. Structural integrity Maintain structural integrity of reactor vessel internals components such that loose parts are not introduced into the system. Structural support Provide structural or functional support for reactor coolant system components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.0-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1 SCOPING AND SCREENING METHODOLOGY 2.1.1 Scoping Methodology The license renewal rule, 10 CFR 54 (Ref. 2.1-1 ), defines the scope of license renewal. Section 54.4(a) requires systems, structures, and components (SSCs) to be included in the license renewal process if they are-( 1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions-* (i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or * (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in§ 50:34(a)(1), § 50.67(b)(2), or § 100.11 of this chapter, as applicable. (2) All nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of any of the functio11s identified in paragraphs (1 )(i), (ii), or (iii) of this section. (3) All systems, structures, and components relied on in safety analyses or plant evaluations to perform a function that demonstrates complian*ce with the Commission's regulations for fire protection (10 CFR 50.48), . environmental qualification (1 O CFR 50.49), pressurized thermal shock (10 CFR 50.61), anticipated transients without scram (10 CFR 50.62), and station blackout (1 O CFR 50.63). NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule (Ref. 2.1-8), provides industry guidance for determining what SSCs are within the scope of license renewal. The process used to determine the systems and structures within the scope of license renewal for Waterford 3 followed the recommendations of NEI 95-10. Consistent with NEI 95-10, the scoping process developed a list of plant systems and structures and identified their intended functions. Intended functions are those functions that are the basis for including a system or structure within the scope of license renewal (as defined in 10 CFR 54.4(b)) and are identified by comparing the system or structure function with the criteria in 10 CFR 54.4(a). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-1 *. J Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The Waterford 3 equipment database was used to identify the system codes in use at the plant. The equipment database is a controlled list of plant components, with each component assigned to one plant system code. The list of plant systems for license renewal scoping was then developed based on the plant system* codes, flow diagrams, and system functions as identified in maintenance rule scoping documents and design basis documents. Systems described in the FSAR do not necessarily correspond to equipment database system codes or the system names used for license renewal: The system descriptions in Section 2.3 explain as needed how the system names relate to system descriptions in the FSAR. For mechanical system scoping, a system is defined as the collection of components required to perform the system's functions. These components are identified in the equipment database, on flow diagrams, and in descriptions of the systems in maintenance rule scoping documents, design basis documents, and system training material. While structural commodities, such as supports, are included in the equipment database and assigned system codes, these components are evaluated with the structural bulk commodities. Component numbers on flow diagrams do not always correlate with component identifications in the equipment database. On some flow diagrams, the original Ebasco component identification numbers are used. Other diagrams show the Entergy component identification that is used in Entergy's Asset Suite, which is the software product used by the Entergy operating fleet for work management, document management, engineering changes, etc. Stiil other diagrams show both component identifications, the Ebasco number and the Entergy-number. For the purposes of system level scoping, plant electrical and l&C systems as well as electrical and l&C components in mechanical systems* are included within the scope of license renewal. Intended functions for electrical and l&C systems are not identified since this bounding scoping approach (i.e., all electrical and l&C components are included in scope by default) makes it unnecessary to determine if an electrical and l&C system has an intended function. Switchyard equipment, which is not part of the plant's electrical and l&C systems, was reviewed for station blackout (SBO) intended functions based on NRC guidance. For further discussion of Waterford 3 scoping for SBO, see Section 2.1.1.3.5. See Section 2.5 for additional information on electrical and l&C scoping. As the starting point for structural scoping, a list of plant structures was developed from a review of plant layout drawings, the FSAR, maintenance rule documentation, and relevant design basis documents. The structures list includes structures that potentially support plant operations or could adversely impact that support plant operations (i.e., seismic II/I). In addition to buildings and facilities, the list of structures includes other structures that support plant operation (e.g., electrical manholes and foundations for freestanding tanks). See Section 2.4 for the results of structural scoping. Intended functions for structures and mechanical systems were identified based on reviews of applicable plant licensing and design documentation. Documents reviewed included the FSAR, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information design basis documents, maintenance rule scoping documents, the post-fire safe shutdown analysis, and, as necessary, system training materials and various station drawings. Each mechanical system and structure function was evaluated against the criteria of 1 O CFR 54.4 as described in the following sections. Section 2.1.1.1 discusses the evaluation of the safety:-related criteria *in 1 O CFR 54.4(a)(1 ). Section 2.1.1.2 discusses the of the criteria of 1 O CFR 54.4(a)(2). Section 2.1.1.3 discusses the evaluation of the *in 1 O CFR 54.4(a)(3). The results of these evaluations for pfant system and structures are presented in Section 2.2.
2.1.1.1 Application of Safety-Related Scoping Criteria '.* A system or structure is within .the scope of iicense 'renewal if it performs a safety function during.* and following a design basis event as defined in 10 CFR 54.4(a)(1). Design basis events are defined in 1 O CFR 50.49(b)(1 )(ii) as conditions of normal operation, including anticipated operational occurrences, design basis accidents, exterilai events, and hatural phenomena for which the plant must be. designed to ensure functions identified in 10 'CFR 54.4(a)(1 )(i) through (iiij. . An Entergy corporate procedure and a site engineering staildard provide control of component and structure quality classification. The procedures design basis events consistent with 10 CFR 50.49 (b)(1 )'and define the ql!alify assurance classification of "safety-related" as follows: -Those structures, systems and components that are relied upon to remain functional during and following design basis events to assure:.* 'I ' * (1) The integrity of the reactor coolant pres&ure boundary. (2) The capability to shut down the reactor and maintain it in a safe shutdown
condition. .. * ' (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the, applicable guideline exposures set forth. in 10 CFR 50.34(a)(1), 10 5.0:67, or 10 CFR 100.11. This is the sa.me definition used for safety-related SSC used in *1 O CFR 54.4(a)(1), with a slight difference in wording: where Entergy procedures use "the applicable guideline.exposures set forth in ... .,;' 10 CFR 54.4(a)(1)(iii) uses the phrase, ... those referred to in ....... The two phrases are equivalent. The original specifications for Waterford 3 used a somewhat different definition for Safety Class 3 for equipment whose failure would "result in significant release of radioactivity to the environment." Use of the term "significant release" instead of the requirements of
50.34(a)(1 ), 50.67(b)(2), or 100.11 resulted in components that are classified as Safety Clas.s 3 at Waterford 3 but do not meet the criteria of 10 CFR 54.4(a)(1). Waterford 3 Safety Class 3 components "Yere evaluated to determine if they supported system functions meeting the 2:0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-3

\. --Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information requirements of1 O CFR 54.4(a)(1 ). Those that did not were further evaluated for the criteria of 1 O CFR 54.4(a)(2) and (a)(3). The Waterford 3 equipment database maintains the controlled component level list of quality classifications. Mechanical system safety functions were obtained from the FSAR, maintenance rule scoping documents, and design criteria documents. Mechanical systems whose only safety-related components are electrical and l&C components or structural components are not included in scope for this criterion; however, the electrical and l&C portions of the system are included in scope by default, and structural components are included in the structural evaluations. Structural safety functions include providing containme'nt or isolation to mitigate post-accident site doses and providing support or protection to safety-related equipment. Structures with *safety functions are identified in the maintenance rule scoping documents. All structures with a safety function or that support or protect a safety.,.related component are included within the scope of license renewal on the basis of 10 CFR 54.4(a)(1). Structures ar:id structural components that provide protection to safety-related equipment from external events and natural phenomena are included in the scope of license renewal on the .basis of 10 CFR 54.4(a)(1 ). As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. *

At Waterford 3, all safety-related equipment is housed within the nuclear plant island structure* .(NPIS). The NPIS is a reinforced concrete box structure with solid walls that provide flood protection up to El. +29.?7 feet MSL. The NPIS is th.e common structure of the reactor building, reactor auxiliary building, fuel handling building, and component cooling. water system
All exterior doors and penetrations be.low +29.27 feet MSL that lead to areas containing-safety-related equipment are watertight. * *
The original design flood level of the NPIS was El. 30.0 ft. MSL During the initial phase of_ construction from 1975 to 1978, the plant settled approximately 9 inches. therefore; the -estabiished *elevations of the plant on design drawings are higher by approximately 9 inches than the actual elevations. The top of the exterior walls (flood walls) of the NPIS were surveyed in . 1991 to be at El. 29.27 ft. MSL. The design flood level of the NPIS is reduced to El. 29.25 ft. MSL from El. 30.0 ft. MSL, a 9-inch*difference. The safety;-related equipment housed within the NPIS is still protected from disastrous floods. since the highest level the-water wilr teach at the NPIS is. El. 27.6 ft. f\!JSL in the. most severe conditions. Several site documents (including the FSAR and descriptions ir:i this application) still use the original design flo.od level of +30 feet correction for the 9-inch discrepancy. *
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1.1.2 Application of Criterion for Nonsafety-Related SSCs Whose Failure Could Prevent the Accomplishment of Safety Functions This review identified nonsafety-related systems and structures containing components whose failure could prevent satisfactory accomplishment of a safety function. The guidance of NEI 95-10 Appendix Fis used to define the SSCs included in scope for physical interaction. Consideration of hypothetical failures that could result from system interdependencies that are
not part of the current licensing basis and that have not been previously experienced is not required. The impact of nonsafety-related SSC failures on safety functions can be either functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of a nonsafety-related SSC in physical proximity to a safety-related SSC. 2.1.1.2.1 Functional Failures of SSCs At Waterford 3, with few exceptions, systems and structures required to perform a function to support a safety function are classified as safety-related and* have been included in the scope of license renewal per Sectipn 2.1.1.1. For the few exceptions where nonsafety-related equipment is required to remain functional to support a safety function (e.g., the dry cooling tower sump* pumps, makeup to spent fuel pool), the system containing the equipment has been included in scope, and the function is listed as an intended function.for 10 CFR 54.4(a)(2) for the system. Flooding analyses were reviewed to determine systems with functions credited to mitigate effects of external or internal flooding. 2.1.1.2.2 Physical Failures of Nonsafety-Related SSCs Some nonsafety-related components co.uld affect safety-related components due to their physical proximity; that is, their physical location can result in interaction between the components should the nonsafety-related component fail. Based on the license renewal rule and the guidance in NEI 95-10 (Ref. 2.1-8), physical failures of nonsafety-related SSCs in scope based on 10 CFR 54.4(a)(2) fit into the following two categories. (1) Nonsafetv-Related SSCs [)irectly Connected to Safetv-Related SSCs For nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems), components within the scope of license renew;;:il include the nonsafety-related piping, components and supports up to and including the first seismic or equivalent anchor or base-mounted component beyond the safety-to-nonsafety interface such that the safety-related portion of the piping will be able to perform its intended function. *See Section 2.1.2.1.2 for further discussion of screening these components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-5 Waterford Steam Electric Station, Unit3 License Renewal Application Technical Information (2) Nonsafety--RelatedBSCs with the Potential for Spatial Interaction with Safetv-Related SSCs Spatial interactions can occur as (a) physical impact or flooding; (b) pipe whip, jet impingement, or harsh environments (such as caused by a HELB); or (c) leakage or spray. (a) Physical Impact or Flooding This category concerns potential spatial interaction of nonsafety-related SSCs falling on or otherwise physically impacting safety-related SSCs (e.g., by causing flooding) such that safety functions may not be accomplished. Structural components that meet the criterion of 10 CFR 54.4(a)(2) include missile barriers, flood barriers, HELB protection, and nonsafety-related supports for seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safefy-related equipment. This.also includes seismic Category I supports provided for nonsafety-related components, such as ducting. Structural compo_nents that protectsafety-related equipment are within the scope of license renewal and are evaluated in the structural aging management review for the structure in which they are located-or *in the bulk commoditiE;!S aging management review (Section 2.4). (b) Pipe Whip, Jet Impingement, or Harsh Environments Nonsafety-related portions of high-energy lines were evaluated against the criterion of 10 CFR 54.4(a)(2). Documents reviewed included the FSAR and other relevant site documentation. High-energy systems were evaluated to ensure identification of components that are part of nonsafety-related high-energy lines that can affect safety-related equipment. If a HELB analysis assumes that a nonsafety-related piping system does not fail or assumes failure only at specific locations, then that piping system is within the scope of license renewal per 1 O CFR 54.4(a)(2) and subject to aging management review in order to provide reasonable assurance that those assumptions remain valid through the period of extended *operation.-(c) Leakage or Spray Moderate-and low-energy systems have the potential for spatial interactions of leakage or spray. Nonsafety-related systems and nonsafety-related portions of safety-related systems with the potential for leakage or spray that _could prevent safety-related SSCs from performing their required safety function are in the scope of license renewal and subject to aging management review. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Operating experience indicates that nonsafety-related components containing only air or gas have experienced no failures due to aging that could impact the ability of safety-related equipment to perform required safety functions. There are no aging effects for these components when the environment is a dry gas. Therefore, a system containing only air or gas is not in the scope of license renewal based on the potential for spray or leakage. The review used a spaces approach for scoping of nonsafety-related systems with potential spatial interaction with.safety-related SSCs. The spaces approach focuses on the interaction between nonsafety-related and safety-related SSCs that are located in the same space. A "space" is defined as a room or cubicle that is separated from other spaces by substantial objects (such as wall, floors, *and ceilings). The space is defined such that any potential interaction between nonsafety-related and safety-related SSCs, including flooding, is limited to the space. Nonsafety-related systems that contain water, oil, or steam with components located inside structures containing safety-related SSCs are potentially in scope for possible spatial interaction under criterion 10 CFR 54.4(a)(2). These systems were evaluated further to determine if system components were located in a space such that safety-related equipment could be affected by a component failure. Equipment that has been retired in place and is no longer functional was included in this evaluation. The retired equipment was evaluated for potential spatial interaction. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. 2.1.1.3 Application of Criterion for Regulated Events The scope of license renewal includes those systems, structures, and components relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48), environmental qualification (10 CFR 50.49), pressurized thermal shock (10 CFR 50.61), anticipated transientswithout scram (to CFR 50.62), and station blackout (10 CFR 50.63). This section discusses the approach used to identify the systems and structures within the scope of license renewal based on this criterion. The systems and structures that perform intended functions in support of these regulated events are identified in the descriptions in Sections 2.3, 2.4, and 2.5. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1.1.3.1
Commission's Regulations for Fire Protection (1 O CFR 50.48) On July 16, 2004, the NRC amended 10 CFR 50.48 to add a new subsection, 10 CFR 50.48(c), that established acceptable fire protection requirements. The change to 1 O CFR 50.48 endorses with exceptions the National Fire Protection Association's (NFPA) Standard 805, Based Standard forFire Protection for Light. Water Reactor Electric Generating Plants, 2001 Edition, as a voluntary alternative for demonstrating compliance with 10 CFR 50.48 Sections (b) and (f). Waterford 3 is in the process of transitioning to the NFPA 805 risk-informed, performance-based fire protection program. However, as this process has not been completed, this license renewal application is based on the site's requirements under 10 CFR 50.48 and Appendix R.-Systems and structures in the scope of lice*nse rene\Yal for fire protection include those r_equired for compliance with 1 O CFR 50.48 and Appendix R. Equipment relied on for fire protection includes SSCs credited with fire prevention, detection, and mitigation in areas containing equipment important to safe operation of the plant as Well as systems that contain plant components credited for safe shutdown following a fire. To identify this equipment, Waterford 3 fire protection documents were reviewed. * *
FSAR Section 9.5 the fire protection program and fire protection systems for the . *current licensing basis, including a detailed comparison to Appendix A of the Branch Technical Position APCSB 9.5-1, Rev. 0. Section 9.5.1.3.2 provides a fire area-by-fire area analysis of the fire hazards in each area, including a listing of equipment located in the fire area/zone which may be used to athieve and maintain safe shutdown following a fire elsewhere in the plant and a of measures provided for fire control. The Waterford.3 post:-fire safe shutdown is documented in a site calculation. This calculation was performed in the context of the post-fire safe shutdown system separation requirements defined by Branch Technical Position (BTP) CMEB 9.5.1 and 1 d CFR 50, Appendix R, and with Section 111.G and 111.L of Appendix R to 1 o CFR 50. The calculation also incorpo"rates analyses performed in preparation for the transition to NFPA 805. A site administrative procedure describes responsibilities, controls and implementing requirements for the Waterford 3 Fire Protection Program. The Fire Protection Program assures that a defense-in-depth program is. provided to (1) prevent fires from starting, (2) detect rapidly, control, and extinguish fires that do occ.ur, and (3) provide protection for structures, systems and components important to safety so that a fire that ls not promptly extinguished by the fire
suppression activities will not prevent the safe shutdown of the plant.
Based on the review of the Waterford 3 current licensing pases for fire protection, the system intended functions performed in support of the fire protection program requirements were determined. Section 2.3 contains the results of the review for the Waterford 3 mechanical 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information systems and identifies systems that contain passive mechanical components that are required for fire protection and safe shutdown of the plant. Structures required to provide support, shelter or protection to equipment meeting the criterion of 1 O CFR 54.4(a)(3) based on the requirements of 10 CFR 50.48 are considered to be within the scope of license renewal based on 1 O CFR 54.4(a)(3). Structural commodities credited as fire barriers are included in the structural aging management reviews. Section 2.4 contains the results of the scoping review for the Waterford 3 structures. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. 2.1.1.3.2 Commission's Regulations for Environmental Qualification (10 CFR 50.49) Electric equipment important to safety that is required to be environmentally qualified to mitigate certain accidents that result in harsh environmental condition*s in the plant is defined in 1 O CFR. 50.49. The Waterford 3 Environmental Qualification Program controls the maintenance of the EQ Component List (EQCL), which is contained within the equipment database. The EQCL identifies electrical equipment and components that are required to function during and subsequent to design basis events. As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. This includes equipment relied upon to perform a function that demonstrates compliance with the Commission's regulations for environmental qualification. 2.1.1.3.3 Commission's Regulations for Pressurized ThermaLShock (10 CFR 50.61)
The pressurized thermal shock (PTS) rule, 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," requires that licensees of pressurized water reactors evaluate the reactor vessel beltline materials against specific criteria to ensure protection from brittle fracture. 10 CFR 50.61 specifiesJhe calculation method to determine an analytical reference temperature, RT PTS* which is compared to PTS screening criteria specified
in the rule. RT PTS values have been extrapolated through the period of extended operation, or 55 effective full power years (EFPY). The limiting reference temperature after 60 years of operation is. below the screening criteria. As a result, no flux reduction programs or modifications to equipment, systems or operation are.necessary to prevent potent!al failure of the reactor vessel. The only system currently relied upon to meet the PTS regulation is the reaCtor coolant system, which contains the reactor vessel. There are no electrical systems or structures relied upon to meet the PTS regulation. For further information on PTS evaluation, see Section 4.2.3. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-9 2.1.1.3.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Commission's Regulations for Anticipated Transients without Scram C10 CFR 50.62) An anticipated transient without scram (ATWS) is an anticipated operational occurrence that is accompanied by a failure of the reactor trip system to shut down the reactor. The ATWS rule, 10 CFR 50.62, requires specific improvements in the design and operation of commercial nuclear power facilities to reduce the probability of failure to shut down the reactor following anticipated transients and to mitigate the consequences of an ATWS event. FSAR Section 7.8 describes the ATWS mitigation systems. The ATWS mitigation systems are designed to mitigate the consequences of anticipated operational occurrence (AOO's) such as a loss of feedwater, loss of condenser vacuum, or loss of offsite power coupled with a failure of the reaCtor protection system to trip the reactor. The A TWS mitigation systems are comprised of two essentially independent subsystems: the Diverse Reactor Trip System (ORTS) and the Diverse Emergency Feedwater Actuation System (DEFAS). ORTS has the function of tripping the reactor, and DEFAS has the function of initiating emergency feedwater (EFW) to the steam generators when required by an ATWS condition.* Inherent to ORTS design is a turbine trip independent and diverse from the plant protection system, which is initiated by undervoltage conditions sensed in the control element assembly (CEA) drive control system. This arrangement, which is the diverse turbine trip system in FSAR Section 7.8, satisfies ATWS rule requirements for a diverse turbine trip. Based on Waterford 3 current licensing bases for ATWS, system intended functions performed in support of ATWS requirements were determined. System scoping evaluations in Section 2.3 contain the results of the review for Waterford 3 systems. There are no mechanical systems with an intended function in support of ATWS requirements. The structure scoping evaluations in Section 2.4 contain the results of the review for the Waterford 3 structural systems. Structures providing support, shelter or protection to equipment meeting the criterion of 10 CFR 54.4(a)(3) based on the requirements of 10 CFR 50.62 are considered to be within the scope of license renewal based on 10 CFR 54.4(a)(3). As described in Section 2.1.1, plant electrical and l&C systems are included in the scope of license renewal by default. Consequently, electrical and l&C equipment that supports the requirements of 10 CFR 50.62 is included in the scope* of license renewal. 2.1.1.3.5 Commission's Regulations for Station Blackout (10 CFR 50.63) 1 O CFR 50.63, "Loss of All Alternating Current Power," requires that each light-water-cooled nuclear power plant be able to withstand and recover from an SBO. As defined by 10 CFR 50.2, an SBO is the loss of offsite power and on-site emergency alternating current (AC) electric power to the essential and non-essential switchgear buses in a nuclear power plant. It does not include the loss of AC power fed from inverters powered by station batteries or by alternate AC sources, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.1-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information nor does it assume a concurrent single failure or design basis accident. The objective of this requirement is to assure that nuclear power plants are capable of withstanding an SBO and maintaining adequate reactor core cooling and appropriate containment integrity for a required duration. FSAR Appendix 8.1A summarizes the licensing bases for SBO at Waterford 3. Waterford 3 has developed a four-hour coping analysis to address the requirements of 10 CFR 50.63. Based on the current licensing bases for SBO, system intended functions performed in support of 10 CFR 50.63 requirements were determined. System scoping evaluations in Section 2.3 contain the results of the review for Waterford 3 systems. Based on NRC guidance in NUREG-1800, Section 2.5.2.1.1 (Ref. 2.1-2); certain switchyard components required to restore offsite power are conservatively included within the scope of license renewal even though those components are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for SBO (10 CFR 50.63).
The indiv.idual structure scoping evaluations in Section 2.4 contain the results of the review for the Waterford 3 structural systems. Structures providing support, shelter or protection to equipment meeting the criterion of 1 O CFR 54.4(a)(3) based on the requirements of 10 CFR 50.63 or the restoration of offsite power are considered to be within the scope of license renewal based on*10 CFR 54.4(a)(3). r As described in Section 2.1.1, plant electrical and l&C are included in the scope of license renewal by default. Consequently, electrical equipment that supports the requirements of 10 CFR 50.63 is included in the scope of license renewal. Section 2.5 contains the results of the review for electrical and l&C systems. 2.1.2 Screening Methodology Screening is the process for determining which components and structural elements require aging management review. Screening is governed by 10 CFR 54.21(a), which reads as follows: (1) For those systems, structures, and components within the scope of this part, as delineated in § 54.4, identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components-* (i) That perform an intended function, as described in § 54.4, without moving parts or without a change in configuration or properties [i.e., passive components]. These structures and components include, but are not limited to, the reactor vessel, the reactor coolant system pressure boundary, steam generators, the pressurizer, piping, pump casings, valve bodies, the core shroud, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-11

\ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (2) (3)' component supports, pressure retaining boundaries, heat exchangers, ventilation ducts, the containment, the containment

liner, electrical and mechanical penetrations, equipment hatches, seismic Category I structures, electrical cables and connections, cable trays, and electrical cabinets, excluding, but not limited to, pumps (except casing), valves (except body), motors, diesel generators, air compressors, snubbers, the control rod drive, ventilation dampers, pressure transmitters, pressure indicators, water level indicators, switchgears, cooling fans, transistors, batteries .. breakers, relays, switches, power inverters, circuit boards, battery charg.ers, and power supplies; and (ii) That are not subject to replacement based .on a qualified life or specified time period [i.e., long-lived components]. Describe and justify the methods used in paragraph (a)(1) of this section. For each struc.ture and component identified in paragraph (a)(1) of this section, demonstrate that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. NEI 95-10 (Ref. 2.1-8) provides industry guidance for screening structures and components to identify the passive, long-lived structures and components that support an intended function. The screening process for Waterford 3 followed the recommendations of NEI 95-10. Within the group of systems and structures that are in scope, passive long-lived corriponents or structural elements that perform intended functions require aging management review. Components or structural elements that support an intended function do not require aging *. management review if they are either active or subject to replacement based on a qualified life. Although the requirements for the integrated plant assessment are the same for each system and structure, in practice the screening process differed for mechanical systeD-is, electrical systems, and structures. The three separate screening processes are described below. 2.1.2.1 Screening of Mechanical Systems As required by 10 CFR 54.21 (a); tlie screening process identified those components that are subject to aging management review for each mechanical system within the scope of license renewal. Section 2.3 presents the results for mechanical systems. Mechanical component intended functions are included in Table 2.0-1. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-12 2.1.2.1.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Identifying Components Subject to Aging Management Review Within the system, components are subject. to aging.management review if they perform an intended function without moving parts or a change in configuration or properties and if they are not subject to replacement based on a qualified life or specified time period. In making the determination that a component performs an intended function without moving parts or a change in configuration or properties, it is not necessary to consider the piece parts of the component. However, in the case of valves, pumps,. and housings for fans and dampers, the valve bodies, pump casings, and housings may perform an intended function by maintaining the pressure boundary and may therefore be subject to aging management review. Replacement programs are based on vendor recommendations, plant experience, or any means establishes a specific service life, qualified life, or replacement frequency under a controlled program. Components that are subject to replacement based on qualified life or specified time period are not subject to aging management review. Where flexible elastomer hoses/expansion joints or other components are periodically replaced, these components are not subject to aging management review. Safety-related instrument air solenoid valves that open to relieve pressure and fail to a* safe position upon loss of pressure boundary do not require aging management review because maintaining a pressure boundary is not a component intended function for these valves. 2.1.2.1.2 Identifying Components Subject to Aging Management Review Based on Support of an Intended *Function for 1 O CFR 54.4(a)(2) As discussed in Section 2.1.1.2, systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function could impact a safety function. A physical failure is one where a safety function could be. impacted by the loss of structural or mechanical integrity of an SSC. For systems with a function identified as meeting the criteria for 1 O CFR 54.4(a)(2) basec{ on a functional failure, components supporting the function are subject to aging management review. As. discussed in Section 2.1.1.2, physical interactions of nonsafety-related systems in scope based on 10 CFR 54.4(a)(2) fit into the following two categories:
Nonsafety-related systems or components directly cbnne.cted to safety-related systems (typically piping systems); or
Nonsafety-related systems or components with the potential for spatial interaction with safety-related SSCs. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-13 /

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Appropriate flow diagrams for the systems were reviewed to identify safety-to-nonsafety interfaces. Piping isometrics were also used to identify seismic anchors and equivalent anchors (restraints or supports) when required to establish scope boundary. For each interface, the boundary was* determined by one of the following: * (1) The first seismic anchor, which is defined as a device or structure that ensures thatforces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in _each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted *component. (4) An endpoint of a plant-specific piping design analysis to ensure that forces and moments are restrained in three orthogonal directions.

This is consistent with the guidance in, NEI 95-10, Appendix F. All component types required or conservatively considered to provide structural support for safety-related portions of systems are included in aging management reviews.
The following modes of spatial interaction, described in Section 2.1.1.2, were considered in the
screening process .. Physical Impact or Flooding Nonsafety-re!ated supports for non-seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safety-related structures or components (SCs) are subject to aging management review based on the criteria of 10 CFR 54.4(a)(2) and 54.21 (a). These supports and components are addressed in a commodity fashion with the structural evaluations in Section 2.4. Reviews of earthquake experience identified no occurrences of welded steel pipe segments falling due to a strong motion earthquake. Falling of piping segments is extremely rare and only occurs when there is a failure of the supports. This conclusion applies for new and aged pipe. Therefore, as long as the effects of aging on the supports for piping systems are managed, falling of piping sections is not credible except due to flow-accelerated corrosion, and the piping section itself is not in scope for 10 CFR 54.4(a)(2) due to a physical impact hazard (but may be in scope due to the potential for leakage or spray). (Ref. 2.1-8) 2.0 Scoping and Screening Methodology for Identifying Structures and Componerits Subject to Aging Management Review and Implementation Results Page 2.1-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Missiles can be generated frorn internal or external events such as failure of rotating equipment. Nonsafety-related design features that protect safety-related equipment from missiles are subject to aging management review based on the criteria of 1 O CFR 54.4(a)(2) and 54.21 (a). These features are addressed.with the structural evaluations in Section 2.4. Overhead-handling systems (e.g., cranes) whose failure could result in damage to a system that could prevent the accomplishment of a safety function are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Specific co*mponents in these systems are subject to aging management review. These features are addressed with the structural evaluations for the structure in which the components are.located. Walls, curbs, doors, etc., that provide flood barriers to safety-related equipment are subject to aging management review based on the criteria of 1 O CFR 54.4(a)(2) and 54.21 (a). These structural components have been included in the evaluation of the building in which they are located or in the evaluation of structural bulk commodities. Structures and structural components are reviewed in Section 2.4. Pipe Whip. Jet Impingement. or Harsh Environments To ensure the nonsafety-related portions of high-energy lines were included in the 1 O CFR 54.4(a)(2) the Waterford 3 FSAR and associated site documentation were reviewed. Many high-energy lines are safety-related components in systems that are already within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(1 ). During review of the Waterford 3 systems for 10 CFR 54.4(a)(2), high energy systems were considered. If a HELB analysis assumes that a nonsafety-related piping system does not fail or assumes failure only at specific locations, then that piping system is within the scope of license renewal per 10 CFR Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. Nonsafety-related components in high-energy lines are included in the appropriate system table for the 10 CFR 54.4(a)(2) review (Sections 2.3.1.5, 2.3.2.4, 2.3.3.15 and 2.3.4.5). Leakage or Spray Screening nonsafety-related components for a potential impact to safety functions due to leakage or spray is performed using three steps:. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-15 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 1. Determine if the components only contain air or gas. For these systems, a review of operating experience is performed to confirm that there have been no failures of air/gas' systems that could have adversely impacted the ability of equipment to perform required safety functions. The operating experience review performed for WF3 confirmed that there have been no failures of air/gas systems that could have adversely impacted the ability of equipment to perform required safety functions. Based on this review, components containing only air or gas do *not have a potential impact to safety functions due to leakage or spray an.d are therefore not subject to aging . management review for 1 O CFR for leakage or spray. 2*. Using a "spaces" approach. determine if the system has components in a safetv-related structure. *
Structures containing safety-related components were identified. and systems reviewed to verify the locations of components in the.system. 3. Determine if components in safety-related structures have the* potential for
spatial interaction with a safety-related component from leakage or spray. For structures that contain safety-related SCs, there may be selected rooms (spaces) that do not contain safety-related components .. Nonsafety-related components in such spaces not have the potential for leakage or spray onto .. safety-r,eJated components. However, no such spaces were identified for WF3. ---' -*Therefore, nonsafety-related components containing water, oil, or steam and located.in structures containing safety-related equipment were subjectto aging management review . . The following. structures contain safety-related components,
Component Cooling Water System Structure (Cooling Tower A and B)
Fuel Handling Building
Manholes and duct banks
Nuclear Plant Island Structure
Plant Stack
Reactor Auxiliary Building
Reactor Building
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-16 2.1.2.1.3 Waterford Steam Electric Station, Unit 3 License Renewal Application _,.* Technical Information Abandoned equipment that has not been verified to be isolated and drained that is located in a space with safety-related equipment is included within the scope of license renewal in accordance with 1 O CFR 54.4(a)(2). The scope of abandoned equipment was determined from discussions with *site. personnel and from reviews of the site equipment database and relevant documents, such as design change notices, system and structure scoping results, and piping and instrumentation diagrams that denote abandoned equipment using hash marks and notes. Mechanical System Drawings License renewal drawings were prepared to indicate portions of systems that support system intended functions within the scope of license renewal. Components subject to aging management' review (i.e., passive, long-.lived components that support system intended functions) are highlighted using color coding to indicate which aging management review evaluated the components. Flexible elastomer hoses/expansion joints and other components that are periodically replaced and therefore not subject to aging management review are indicated as such on the drawings. Safety-related instrument air solenoid valves that open to relieve pressure and fail to a safe position upon loss of pressure boundary do not require aging management review and thus are not highlighted. *
2.1,2.2 Screening of Structures For each structure within the scope of license renewal, the structural components and commodities *were evaluated to determine those subject to aging management review. This evaluation (screening process) for structural components and commodities involved a review of design and licensing basis documents (FSAR, design basis documents, design specifications, site drawings, etc.) to identify specific structural components and commodities that make up the . structure. Structural components and commodities subject to aging management review are those that (1) perform an intended function without moving parts or a change in configuration or properties, and (2) are not subject to replacement based on qualified life or specified time period. Section 2.4 presents the results for structures. 2.1.2.2.1 structural Component and Commodity Groups structurai components and commodities often have no unique identifiers such as those given to mechanical components. Therefore, grouping structural components and commo.dities based on materials of construction provided a practical means of categorizing them for aging management reviews. Structural components and commodities were categorized by the following groups based on materials of construction.
steel and other metals
Bolted connections 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.1-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Concrete .
Other materials (e.g., fire barrier material, elastomers, wood) 2.1.2.2.2 Evaluation Boundaries Structural evaluation boundaries were established as described below. ASME and Non-ASME Component Supports-Mechanical Components The evaluation boundaries for mechanical component were established in accordance with rules governing inspection of component supports (i.e., American Society of Mechanical Engineers (ASME) Section XI, Subsection IWF). Component support examination boundaries for integral and non-integral (i.e.; mechanically attached) supports are defined in*Article IWF-1300, Figure IWF-1300-1. In general, the support boundary extends to the surface of the building structure, but does not include the building structure. Furthermore, the support boundary extends to include integral attachments to piping and equipment, but does not include integral attachments to the same.
Compone_nt Supporls-_:Electrical Components 2.1.2.2.3 Supports for electrical components inClude cable trays, conduits, electrical panels, racks, cabinets and other enclosures. The evaluation boundary for these items includes supporting elements, including integral attachments to the building structure. Other Structural Members Evaluation boundaries for other structural members whose function is to carry dynamic loads caused by postulated design basis events are consistent with the.method for establishing boundaries for supports specified above. That is, the boundary includes the structural component and the associated attachment to the building structure. The portion of the attachment embedded in the building structure is considered part of the *
structure. Intended Functions Structural components and commodities* were evaluated to determine intended functions as they relate to license renewal. NEI 95-10 (Ref. 2.1-8) provides guidelines for determining the .intended functions of structures, structural components and commodities. Structural component and commodity intended functions include providing protection and providing structural or functional support. structural components either _have the potential for spatial interaction with safety-related equipment (e.g., cranes, hoists) or serve as mitigating features for potential spatial interactions. Mitigating features include missile barriers, flood . . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review ahd Implementation Results Page 2.1-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information barriers, HEL8 protection, and nonsafety-related supports for non-seismic (including seismic II/I) piping systems and electrical conduit and cable trays with potential for spatial interaction with safety-related equipment. Structural component intended functions are included in Table 2.0-1. 2.1.2.3 Electrical and Instrumentation and Control Systems The electrical and l&C aging management review evaluates com'modity groups containing components with similar characteristics. Screening applied to commodity groups determines* which electrical and l&C components are subject to aging management review. An aging management review is required for commodity groups that perform an intended function, as described in 1 O CFR 54.4, without moving parts or without a change in configuration or properties (passive) and that are not subject to replacement based on a qualified life or specified time period (long-lived). Section 2.5 presents the results for electrical systems. Electrical and l&C component intended functions are included in Table 2.0-1. 2.1.2.3.1 Passive Screening NEI 95-10, Appendix 8, "Typical Structure, Component and Commodity Groupings and Active/ Passive Determinations for the Integrated Plant Assessment," identifies electrical commodities considered to be passive. Waterford 3 electrical commodity groups were compared to the NEI 95-10, Appendix 8 electrical and l&C commodity groups. Waterford 3 passive electrical commodity groups correspond to Item 77 of the NEI 95-10 passive electrical and l&C commodity groups. Item 77 of NEI 95-10, Appendix 8 meets the 10 CFR 54.21 (a)(1)(i) criterion (i.e., components that perform* an intended function without moving parts or without a change in. configuration);
Cables and connections, bus, electrical portions of electrical and l&C penetration assemblies, fuse holders outside of cabinets of active electrical components. The 230 kV switchyard commodities are not included in the Waterford 3 equipment database because Transmission and Distribution is responsible for their maintenance. However, the following additional switchyard 'commodities meet the 10 CFR 54.21(a)(1)(i) screening criterion:
High voltage insulators (corresponds to Item 87 of NEI 95-10, Appendix 8).
Switchyard bus and connections.
Transmission conductors and connections. All of these commodity groups were subdivided as shown in Table 2.5-1. Other Waterford 3 electrical and l&C commodity groups are active and do not. require aging management review. Electrical and l&C components whose primary function is electrical can also have a mechanical pressure boundary function. These components may include items such as elements, resistance temperature detectors, sensors, thermocouples, transducers, solenoid valves, heaters, and 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-19 _)

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information dryers. According. to Appendix B of NEI 95-10, the .electrical portions of these components are active per 10 CFR 54.21 (a)(1)(i) and are therefore not subject to aging management review. Only the pressure boundary of such an componen(is subject to aging management review, and the pressure boundary function for electrical and l&C components is addressed iri the mechanical review. Electrical components are supported by structural commodities (e.g., cable trays, electrical conduit, or cable trenches.),_which are included in the structural aging management reviews. 2.1.2.3.2 Long-Lived Screening Electrical components and electrical and l&C penetration assemblies included in the Ea'*program per 1 O CFR 50.49 are subject to replacement based on their qualified life.* Therefore, in accordance with* 10 CFR 54.21 (a)(1 )(ii), EQ electrical and l&C compor:ients are not subject fo 'aging management review. EQ electrical and. l&C components are covered by analyses or . calculations that may be time-limited aging analyses (TLAAs) as defined in 1 O CFR Only .that are not in EQ_prog-ram are subject to aging management review-.. 2.1.2.4 Consumables Consumables incluc;te'-such items as packing, gaskets, component sea.ls, 0-rings, structural sealants, oil, grease, component filters, system filters, fire extinguishers, fire hoses, and air. packs. Con.sumables have been evaluated consistent with the information presented in Table 2.1-3.of NUREG-1800. Consumables have t::>een divided into the following four categories for the purpose of license renewal: (a) packing, gaskets, component seals; and 0-rings; (b) structurarsealants; (c)'oil, grease, ;;1nd component filters; and (d) $YStem filters, fire . extinguishers, fire hoses, and air packs. . -: -. . 2.1.2.4.1 Packing. 'Gaskets. Component Seals. and 0-Rings Packing, gaskets, component mechanical seals, and 0-rings are typically used*to-provide a proof seal when components are mechanically joined together. These items are commonly found in components suc_h as valves, pumps, heat exchangers, ventilation *lJni_ts or ducts, and piping segments. * * * ---In accordance with American National Standards Institute (ANSI) 831.1 and the ASME Boiler and Pressure Vessel Co<;le Section Ill, the subcomponents of pressure' retaining components as shown above are not considered pressure-retaining parts. Therefore, these subcomponents not relied on to perform a llcense renewal intended function and are not subject to aging management review. --2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results

Page 2.1-20 2.1.2.4.2 Structural Sealants Waterford Steam E:lectric Station, Unit 3 License Renewal Application Technical Information Elastomers and other materials used as structural sealants are subjeCt to aging management review if they are not periodically replaceq and they perform an intended function, tYpically supporting a pressure boundary; flood barrier, o"r rated fire barrier. Seals and sealants are considered in the aging management review of bulk commodities (Section 2.4.4). 2.1.2.4.3 Oil. Grease. and Component Filters Oil, grease, and component filters have been treated as consumables because either (1) they _are periodically replaced or (2) they are monitored and replaced-based on condition. -_ 2.1.2.4.4 _ System Filters. Fire Extinguishers. Fire Hoses. and Air Packs Components such as system filters, fire hoses, fire extinguishers, self-contained breathing apparatus (SCBA), 'and SCBA cylinders are considered to be consumables and are routinely -tested, inspected, and replaced when* necessary. Fire protection equipment performance criteria at Waterford 3 comply with the applicable safety standards (e.g., 10 CFR 50, Appendix R/ Appendix A to Branch Technical Position BTP-APCSB 9.5. 1 or NFPA 805 (2001 Edition) in accordance with 10 CFR 48(c), NFPA 10 for fire extinguishers, fire hoses and SCBA air _ cylinders, and 29 CFR 1910.134 for respiratory protection), which specify performance and condition monitoring programs for the'se specific components. Fire hoses and fire extinguishers are inspected and hydrostatically periodically and must be_replaced if they do 'not pass test or inspection. SCBA and cylinders are inspeded and periodically tested and must be repaired or replaced if they do not pass the test or inspection. Fire protection and radiation protection procedures specify the replacement criterion of these components that are routinely checked by tests or inspections to assure operability. Therefore, while these consumables are in the scope of license re-newal, they do _not require an aging management review. -. -2.1.3 Interim Staff Guidance Discussion As discussed in NEI 95-10 (Ref. 2.1-8), the NRC has encouraged applicants for license renewal to address proposed interim staff guidance (ISGs) in the LRA. The majority of license related ISGs have been resolveq (Ref. 2.1-9, 2.1-10) with the issuance of revisions to the license renewal guidance documents (Ref. 2.1-2), NUREG-1801(Ref.2.1-3), RG 1.188 (Ref. 2.1:-4), RG 4.2 (Ref. 2.1-11), and NEI 95-10. The remaining ISGs are addressed as follows. LR-ISG-2011-01 Aging Management of Stainless Steel Structures and Compon_ents in Treated Borated Water (Revision 1) This ISG recommends guidance for aging management presented as revisions to selected tables of NUREG-1800 (Ref. 2.1-2) and NUREG-1801(Ref.2.1-3). The revised guidance has been \ 2.0. Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information considered in the integrated plant assessment and is reflected iri the aging management results presented in Section 3. LR-ISG-2011-02 Aging Management Program for Steam Generators This ISG recommends the use of guidance provided in Revision 3 of NEI 97-06, Steam
Generator Program Guidelines, issued after NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3). The ISG also updates NUREG-1800 to reference Revision 3 of Electric Power Research Institute (EPRI) 1019038, Steam Generator Integrity Assessment Guidelines. The Waterford 3 Steam Generator Integrity Program (Section B.1.37) is based on these current steam generator inspection program guidance documents. LR-ISG-2011-03 Generic Aging Lessons Learned (GALL) Report Revision 2 '[Aging Management Program] AMP Xl.M41, "[3uried and Underground Piping and Tanks" . This ISG provides expanded guidance for managing the effects of aging of buried and
underground piping and tanks within the scope of license renewal. This guidance is presented as revisionsto NUREG-1800 (Ref. 2.1-2) and (Ref. 2.1-3). The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program description presented in Appendix B, Section B.1.3, Buried and Underground Piping and Tanks Inspection: LR-ISG-2011-04 Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors *
This ISG updates the guidance for the aging_ management of reactor vessel internals presented in NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3) to be consistent with EPRI 1022863, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," and the associated NRG safety evaluation report. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 .and the aging management program descripti9n. presented in Appendix B, Section B.1.33, Reactor Vessel Internals. ' . . . . LR-ISG-2011-05 Ongoing Review of Operating Experience This ISG establishes a framework for the consideration of operating experience concerning aging management and age-related degradation during the term of a renewed operating license. The ISG provides interim revisions to NUREG-1800 (Ref. 2.1-2) and NUREG-1801 (Ref. 2.1-3) to *present new NRC review criteria for the operating experience review. program. Th.e revised guidance is reflected in the description of the process for the review of operating**experience presented in Appendix B, Section B.0.4, Operating Experierice. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation ResuJts Page 2.1-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LR-ISG-2012-01 Wall Thinning due to Erosion Mechanisms This ISG provides additional guidance for managing the effects of wall thinning due to aging mechanisms other than flow-accelerated corrosion (FAG). The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program descriptions presented in Appendix B. LR-ISG-2012-02 Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation This ISG provides guidance on a variety of topics as indicated by the title. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging
management results presented in Section 3 and the aging management program descriptions presented in Appendix B. LR-ISG-2013-01 Aging Management of Loss of Coating or Lining Integrity for Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks This ISG provides guidance related to. loss of coating integrity. The revised guidance has been considered in the integrated plant assessment and is reflected in the aging management results presented in Section 3 and the aging management program descriptions presented in Appendix B.
LR-ISG-2015-01 (Draft) Changes to Buried and Underground Piping and Tank Recommendations This ISG provides proposed guidance related to managing loss of mate.rial for the external of buried and underground piping and tanks. Due to the draft nature c:if the ISG and the. timing of its issuance, it was not feasible to include recommended activities from this ISG into the Waterford 3 LRA. 2.1.4 Generic Safety Issues In accordance with the guidance in NEI 95-10. (Ref. 2.1-8), review of _NRC generic safety issues * (GSls) as part of the license renewal process is required to satisfy the finding required by 1 O CFR 54.29. GSls designated as unresolved safety issues (US ls) and High-and Medium-priority issues in NUREG-0933, Append.ix B (Ref. 2.1-5), that involve aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations are to be *addressed in the LRA. A review of the version of NUREG-0933 current six months prior to the license renewal application submittal, including the applicable Generic Issue Management Control System Report (Ref. 2.1-6), determined that there were nq outstanding USls or High-or Medium-priority GSls. Two GSls designated as Active in NUREG-0933, Appendix B, 186 and 193, were reviewed to assure they did not involve aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.1-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Item 186, Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants, involves issues related to crane design and operation. Aging effects are not central to these issues. The issue does n*ot involve time limited aging analysis evaluations, including typical crane related TL:AAs such as cyclic loading analyses. This issue was closed on January 27, 2012. (Ref. 2.1-7) Item 193, [Boiling Water Reactor] BWR [Emergency Core Cooling System] ECCS Suction Concerns, addresses the possible failure of low presswe emergency core cooling systems due to unanticipated, large quantities of entrained gas in the suction piping from suppression pools in BWR Mark I containments. This issue is not applicable to Waterford 3. Therefore, there are_ no GSls involving aging effects for structures and components subject to an aging management review or time-limited aging analysis evaluations that are relevant to the Waterford 3 license renewal. process. 2.1.5 Conclusion The methods described in Sections 2.1.1 and 1.2 *were used at Waterford 3 to identify systems and structures that are within the scope of license renewal and to identify those
structures and components requiring _aging management review. The methods are -consistent with and satisfy the requirements of 1*0 CFR 54.4 and 10 CFR 54,.21(a)(1). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging .Management Review and Implementation Results 2.1.6 References . .* Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 2.1-1 10 CFR 54_, Re.newal of Operating Licenses for Nuclear Power Plants. 2.1-2 Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. NUREG-1800. U.S. Nuclear Regulatory Commission (NRC). Revision 2. December 2010. 2.1-3 Generic Aging Lessons Learned (GALL) Report. NUREG-1801. U.S. NRC. Revision 2 . . December 2010. 2.1-4 Standard Format and Content for Applications to Nuclear Power Plant Operating Licenses, Regulatory Guide 1.188. U.S. NRC. Revision 1. September.2005. 2.1-5 Resolution ofGeneric Safety Issues (Formerly entitled A Prioritization of Generic Saf(Jty Issues'?. NUREG-0933. (Appendix 8, Applicability of NUREG-0933 to Oper;;lting and Future Reactor Plants, Revision 25, September 30, 2011). U.S. NRC. December"2011, 2.1-6 Generic Issue Management Control System Report For Fiscal Year 2015 3rd Quarter, NRC Agencywide Documents Access and Management System [ADAMS] Accession* number ML 15175A059. 2.1-7 Leeds, E. J., Director, NRC Office of Nuclear Reactor Regulation, to R. W. Borchardt, NRC Executive Director for Operations, "Completion of Generic Issue 186, 'Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants."' Memorandum dated January 27, 2012. NRC ADAMS Accession number ML 113050589. 2.1-8 Industry Guideline on Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule. NEI 95-10. Nuclear Energy Institute. Revision 6. June 2005. 2.1-9 Kuo, P. T. (NRC) to A. Marion (NEI) and D. Lochbaum (Union of Concerned Scientists), Summary of the 2001-20.05 Interim Staff Guidance for License Renewal. Letter dated February 6, 2007. 2.1-10 Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800. NUREG-1950. Table A-8, Summary of Changes to the Updated License Renewal Documents as a Result of License Renewal Interim Staff Guidance (LR-ISG). U.S. NRC. April 2011. 2.1-11 Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications. Regulatory Guide 4.2, Supplement 1. U.S. NRC. Revision 1. June 2013. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation* Results Page 2.1-25 2.2 PLANT LEVEL SCOPING RESULTS Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Tables 2.2-1, 2.2-3, and 2*.2-4 list the mechanicc:il systems, electrical and l&C systems, and structures, that are within the scope of license renewal for Waterford 3. For mechanical systems, a reference is given to the section which describes the system. For electrical systems, no description is necessary since plant electrical systems are in scope by default (see Section 2.5), but a reference to the FSAR is provided where applicable. For structures, a reference is given to the section that includes the structure in the evaluation. Tables 2.2-2 and 2.2..:5 list the systems and structures, respectively, that do not meet the criteria specified in 10 CFR 54.4(a) and are therefore excluded from the scope* of license renewal. For each item on lists, the table also provides a reference (if applicable) to the section of the FSAR that describes the system or structure. For structures with no FSAR reference, a brief description of the building function is given. None of these structures house safety-related equipment nor are they situated such that a failure of the structure would impact a safety function. The list of systems used in these tables and determination of system boundaries is based on the Waterford 3 equipment database. The equipment database is a controlled list of plant systems and components, with each component assigned to one plant system. System intended functions are identified in the section referenced in Table 2.2-1. As needed, system components
are grouped functionally for the aging management review. For example,'ASME Class 1 components in various systems are evaluated with the ASME Class 1 reactor coolant pressure boundary in Section 2.3.1.3, and containment penetrations from various systems are grouped into one containment penetrations review in Section 2.3.2.3. For each system, the discussion under "Components Subject to Aging Management Review" provides further information.* The LRA section describing the system provides references to relevant sections of the FSAR. If the system is described in the FSAR with a different syste'm or under a different system name, an explanation is given. As described in the FSAR, safety-related piping and valves support the pressure boundaries between the containment vessel and the shield building (primary containment), through the . shield building (secondary containment) and across the auxiliary building secondary containment enclosure (secondary containment). For license renewal, these barriers are functionally equivalent and will be referred to as "containment pressure boundary." The safety-related piping and valves have a safety function to "support containment pressure boundary." Nonsafety-related components whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] due to the potential for a physical interaction (see Section 2.1.1.2) are evaluated together by system in the (a)(2) aging management reviews (AMRs). The (a)(2) AM Rs include nonsafety-related components with the potential for spatial interaction with safety-related components as well as components in safety-related systems outside the safety 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information class pressure boundary, such as piping, valves, pumps, and support elements, that are required to be structurally sound in order to maintain the integrity of safety class piping. That is, the system intended function, "Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function" includes the function of components that provide structural/seismic support to directly connected components. The (a)(2) system reviews are presented at the end of the mechanical system sections: Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2); Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2); Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2); and Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Components subject to aging management review are highlighted on license renewal drawings. A list of drawings is provided for each aging management review. For further discussion of license renewal drawings, see Section 2.1.2.1.3. The list of plant structures was developed from a review of plant layout drawings, the FSAR, maintenance rule documentation, and relevant design basis documents. Structure intended functions are identified in the section referenced in Table 2.2-4. Structural commodities associated with mechanical systems, such as pipe supports and insulation, are evaluated with the structural bulk commodities. Because of the bounding approach used for scoping electrical and l&C equipment, all plant electrical and l&C commodities contained in electrical and mechanical systems are in scope by default. Descriptions of each electrical system are not provided. In addition to plant electrical systems, certain switchyard components in the offsite power systems are in scope for support of offsite power recovery following a station blackout. For further information on electrical and l&C systems, see Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Control Systems. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-2 System Code AE ARR ANP ACC AS BD BAM BM svs eve .. CF CHW RFR SCH sec cw cc IA SA CD Waterford Steam Electric Station, Unit 3 License Renewal Application Technical lnformati9n
Table 2.2-1 Mechanical Systems Within the Scope of License Renewal .. System Name LRA Section Describing System *
Air Evacuation Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Airborne Radioactivity Removal Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Annulus Negative Pressure Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Auxiliary Component Cooling Water Section 2.3.3.3, Compon-ent Cooling and Auxiliary Component Coolif')g Water Auxiliary Steam Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Slowdown Section 2.3.4.4, Main Steam Boric Acid Makeup Section 2.3.3.1, Chemical and Volume Control Boron Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Cable Vault & Switchgear Ventilation Section 2.3.3.12, Miscellaneous HVAC * .Chemi.cal and Volume Control Section 2.3.3.1, CheniiC'.al and Volume Control Chemical Feed Section 2.3.3.15, Auxiliary Systems in-Scope for 10 CFR 54.4(a)(2) Chilled Water Section 2.3.3.2, Chilled Water Circulating Water SeCtion 2.3.3.3, Component Cooling and Auxili.ary Component Cooling Water Component Cooling Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water Compressed Air Section 2.3.3.4, Compressed Air Condensate . Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Page 2.2-3 Subject to Aging Management Review and Implementation Results
Waterford Steam Electric station, Unit 3 i License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Code . System LRA Section Describing System CMU Condensate Makeup and Storage Section 2.3.4.1, Condensate Makeup and DW Storage CAP *Containment Atmosphere Purge Section 2.3.3.15, Aµxiliary Systems in Scope for 10 CFR 54.4(a)(2) CAR . Containment Atmosphere Release Section 2.3.3.12, Miscellaneous I-WAC CB Containment Building Section 2.3.3.4, Compressed Air (mechanical components) ccs Containment Cooling heating, ventilation, Section 2.3.3.5, Containment Cooling HVAC and air condi_tioning (HVAC) cs Containment Spray Section 2.3.2.1, Containment Spray CVR Containment Vacuum Relief Section 2.3.2.3, Containment Penetrations CED Control Element Drive Section 2.3.1.1, Reactor Vessel CDC Control Element Drive Mechanism Section.2.3.3.3, Componeht Cooling and* Cooling Auxiliary Compone_nt Cooling Water . HVC Control Room HVAC Section 2.3.3.6, Control Room HVAC DF Decontamination Facility Section 2.3.3.15, Auxiliary Systems in Scope (mechanical components) for 10 CFR 54.4(a)(2) DFO Diesel Fuel Oil Section 2.3.3.8, Fire Protection: Water EBA Emergency Breathing Air Section 2.3.3.4, Compressed Air EFW Emergency Feedwater Section 2.3.4.2, Emergency Feedwater EG Diesel Generator Section 2.3.3.7, Emergency Diesel Generator EGA EGC E:GF EGL FW Feedwater Section 2.3.4.3, Main Feedwater _ FP Fire Protection Section 2.3.3.8, Fire Protection: Water OFP FHS Fuel Handling and Storage Section 2.3.2.3, Containment Penetrations 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-4 System Code HVF FS GWM HVD HRA LRT LWM MS NG PAS PW PMU PSL ARM PRM HVR RCC RC Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Name LRA Section Describing System Fuel Handling Building HVAC Section 2. 3.3.12, Miscellaneous HVAC Fuel Pool Cooling and Purification Section 2.3.3.10, Fuel Pool Cooling and Purification Gaseous Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Hot Machine Shop and Decon Facility Section 2.3.3.15, Auxiliary Systems in Scope Ventilation for 10 CFR 54.4(a)(2) Hydrogen Recombiner and Analyzer Section 2.3.2.3, Containment Penetrations Leak Rate Testing Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Liquio Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Main Steam Section 2.3.4.4, Main Steam Nitrogen Section 2.3.3.11, Nitrogen Post Accident Sampling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Potable Water Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Primary Makeup Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Primary Sampling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Radiation Monitoring Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Reactor Auxiliary Building HVAC Section 2.3.3.12, Miscellaneous HVAC Reactor Cavity Cooling Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Reactor Coolant Section 2.3.1, Reactor Coolant System Section 2.3.3.9, Reactor Coolant Pump Oil Collection 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-5 Waterford Steam Electric Station, Unit 3 ' License Renewal Application Technical Information Table 2.2-1 (Continued) Mechanical Systems Within the Scope of License Renewal System Code System Name LRA Section Describing System RS Reheat Steam Section 2.3.4.4, Main Steam RWM Resin Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) SI Safety Injection Sectiori 2.3.2.2, Safety Injection SAN Sanitation System S!3ction 2.3.3.14, Plant Drains SSL Secondary Sampling Section 2.3.3.15, Auxiliary Systems in Scope CTB for 10 CFR 54.4(a)(2) -SBV Shield Building Ventilation Section 2.3.3.12, Miscellaneous HVAC SS Site Security Section 2.3.3.13, Auxiliary Diesel Generator SWM Solid Waste Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) SG Steam Generator Section 2.3.1.4, Steam Generators PME Sump Pump Section 2.3.3.14, Plant Drains SP TW Treated Water Section 2.3.3.8, Fire Protection: Water BO TC Turbine Building Cooling Water Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) HVT Turbine Building HVAC . Section 2.3.3.12, Miscellaneous HVAC 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2*6 System Code AB ABC ABF ABS AFW co CHV CDP CP EH ES LOF 'FHD FHV FPV GG GS HG LOS HVP so HVS SB sew TSW TUR Table 2.2-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Mechanical Systems Not Within the Scope of License Renewal System Name FSAR Reference Auxiliary Boiler None Auxiliary Feedwater System Section 10.4.7 Carbon Dioxide None Chiller Building Ventilation None Condensate Polisher Section 10.4.6 (condensate clean-up system) Electro-Hydraulic Fluid Section 10.2.2.2. 7 Extraction Steam Section 10.2.2.2.6 Feed Pump Lube Oil None Feedwater Heater Drains and Vents Section 10.4.7 Fire Pump House Ventilation None Generator Gas None Gland Seal Section 10.4.3 Hydrogen Section 9.3.7 Lube Oil Storage and Transfer None Polisher Building HVAC None* Seal Oil None Service Building HVAC None Stator Coil Water None Traveling Screens and Wash Section 10.4.5 Turbine Section 10.2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-7 System Code LOG WHV Table 2.2-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Mechanical Systems Not Within the Scope of License* Renewal System Name FSAR Reference Turbine Generator Lube Oil None WaterTreatment Building Ventilation None 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-8 System Code DC . LVD 4KV SSD 7KV ANN ATS CHS CMF CMP CMR CMT COL CPC CRN ELV ESF EM ' ENI FPO GEN HT INI IC ID Table 2.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Plant Electrical and l&C Systems Within the Scope of License Renewal
System Name FSAR Reference 125V DC Distribution Section 8.3.2 208V/120V Low Voltage Distribution
Seetion 8.3.1 4.16KV Electrical Distribution Section 8:3.1 480V Station Service Distribution Section 8.3.1 6.9KV Electrical Distribution Section 8.3.1 Annunciator Section 7.5.1.9.2 / Anticipated Transients without Scram (ATWS) Section 7.8 Chiller Builqing None
Communication Systems Section 9.5.2 Core Operating Limit Supervisory System Section 7:7.1.5 Core Protection Calculator Section 7.2.1.1.2.5 Cranes and Hoists . None. Elevators None Emergency Lighting . Section 9,5.1.2.5 Eng Safety Features Actuation Section 7.3 .. Environmental (Meteorological) Monitoring Section 2.3.3.2 Excore Nuclear Instrumentation Section 7.2.1.1.2.3 Fire Protection Detection Section 9.5.1.2.2 Generator and 25.KV Distribution Section 8.2.1 Heat Tradng None In-Core Nuclear Instrumentation Section 7.7.1.7 Instrument Cabinets None Inverters and Distribution Section 8.3.1 2.0 Scoping and Screening Methodology for Identifying structures and Components
Subject to Aging Management Review and Implementation Results
Page 2.2-9 System Code MT MNl8 *LTN PMC PPS PAC RMS RMC RXC RR RF SM ST [None] UAT VLP WTB Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-3 (Continued) Plant Electrical and l&C Systems Within the Scope of License Renewal .. System Name FSAR Reference Main Transformer Section 8.2.1 Movable In-Core Nuclear Instrumentation None Normal Lighting Distribution Section 9.5.3 Plant Monitoring Computer Appendix7.5A Plant Protection Section 7. 1.1 . 1 Process Analog Control None Radiation Monitoring Section 11.5.2.1 . . Radiation Monitoring Computer Section 11.5.2.1 Reactor Power Cutback Section 7.7.1.9 Reactor Regulating Section 7.7.1.1.1 Refueling None .. Seismic Monitoring Section 3.7.4 Startup Transformer Section 8.2.1 Switchyard Section 8.2.1 Unit Auxiliary Transformer Section 8.2.1 Valve and Loose Parts Monitor Sect,ion 4.4.6.1 Water Treatment. Building None a. Although the MNI system has been abandoned in place, there are still a few electrical components not abandoned. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-10

\ Table 2.2-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical lnforrT)ation Structures Within the Scope of License Renewal Structure Name LRA Section Battery House.230kV Switchyard Section 2.4.3, Turbine Building and Other Structures Component Cooling Water System Structure Section 2.4.2, Nuclear Plant Island Structure Control House 230kv Switchyard. Section 2.4.3; Turbine Building and Other Structures Cranes, Trolleys, Monorails and Hoists Cranes, trolleys, monorails and hoists are evaluated as structural components or * . ' commodities of the structure in which they are located. Fire Pump House Section 2.4.3, Turbine Building and Other Structures '. Fire Water Storage Tank Section i4.3, Turbine Building arid Other. Structures Fuel Handling Building Section 2.4.2, Nuclear Plant Island Structure . . Manholes, Handholes, and Duct banks Section 2.4.3, Turbine Building and Other Structures Nuclear Plant Island .. Structure Section 2.4.2, Nuclear Plant Island Structure . Plant Stack Section 2.4.1, Reactor Building Reactor Auxiiiary Building Section 2.4.2, Nuclear Plant Island Structure Reactor Building Section 2.4.1, Reactor Building . Transformer and Switchyard Support Section 2.4.3, Turl;>ine Building and Other Structures and Foundations T1.,1rbine Building Section 2.4:3, Turbine Buildirig and Other Structures 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-11 Table 2.2-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Structures Not Within the Scope of License Renewal Structure Name Structure Function or FSAR Reference Administration Building Provide space for administrative and support personnel. Administration Building Access Facility Provide office space for security and access for personnel into the protective area. Auxiliary Boiler Foundation Provide support of the oil-fired boiler and accessories for supplying hot water to the plant for heating p_urposes. Batch Oil Tanks Foundation FSAR Section 9.5.1*.1.3 Bulk Chemical Storage Building Provide space for the site bulk chemicals. Chemical Storage Building Provide space for the site water treatment chemicals for the wet cooling tower. Chiller Building Provide space for heating, ventilation and electrical switchgear equipment. Condensate Polisher Building Provide support for the condensate polisher systems* six demineralizer vessels. Condensate Storage Tank Foundation FSAR Section 1.9.37, 9.2.6.2 Construction Support Building Provide office space for construction and various other station personnel. .. Demineralized Water Storage Tank . FSARSection 9.2.3.2 .. Foundation Discharge Structure Provide for a release for water from the condensers and the heat exchangers to be discharged into the Mississippi River downstream of the intake structure. ,Dress Out Building Provide support for personnel dress-out (anti-contamination) measures. Fuel Oil Storage Tank Foundation Provide support for one 100,000 gallon fuel oil storage tank. Generation Support 13uilding Provide space for office and support personnel. Independent Spent Fuel Storage FSAR Section 1.2.2.6, 9.1.5 Installation (ISFSI) Cask Storage Pad Intake Structure FSAR Section 2.4. 1.1, 10.4.5.2 Low-Level Radwaste Storage Facility FSARSection 11.4.10.5 ' Low Volume Waste Water Basin Hold wastewater containing wide ranges in pH and above-normal concentrations of heavy rnetais. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-12 . --- Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.2-5 (Continued) Structures Not Within the Scope of License Renewal Structure Name Structure Function or FSAR Reference Maintenance Building 230kV Switchyard Provide a work area and office space for the switchyard. Maintenance Support Building Provide space for the electronic repair facility, personnel equipment, and maintenance and storage space for spare parts. Mechanical Maintenance Impound Provide space for the storage of maintenance equipment Building and weld shop. Multiplexer Enclosures FSAR Appendix 7.5A Oil Separator and Separator Pit Provide support for the waste oil collection tank and associated equipment and provide a collection point for the site industrial waste.oil for separation of the oil. Primary and Back-up Meteorological FSAR Section 2.3.3.2 Tower Primary Water Storage Tank Foundation Provide support for a 260,000-gallon water storage tank, which supplies water for various makeup and flushing operations. Radioactive Material Storage Building FSAR_ Section 12.5.2.1 Secondary Make-up Water Degas and Provide support for the degas tank and the associated Transfer Pumps Foundation pumps. Service Building Provide office space and work area for administrative and support personnel. . *; Solidification Facility FSAR Section 11.4.4, 11.4.8 Switching Station Control House Provide a.protected area for the relay panels and batteries .w.hich control the switching station. Tool Room Provide storage area for tools and other equipment used for maintenance. Waste Oil Facility Provide support for the components related to waste oil collection. Water Treatment Building Provide support for the primary water treatment plant and portions of the demineralized water system. West Side Access Facility Provide access to the controlled access area and work space for' radiation protection personnel. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.2-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS 2.3.1 Reactor Coolant System System Description The reactor coolant system (RCS) is a pressurized wateneactor with tWo coolant loops. The reactor coolant system circulates coolant in a closed cycle, removing heat from the reactor core and internals and transferring it to the steam generators. In the equipment database, the reactor coolant (RC) system code encompasses the reactor vessel and internals, the reactor coolant loops and pumps, and the pressurizer and related equipment. The steam generators are included in a separate system code (SG). For the purposes of the renewal integrated plant assessment, the equipment in the RC system code will be described and evaluated in three parts: the reactor vessel, the reactor vessel internals, and the remaining reactor coolant system piping and components. The reactor coolant pump (RCP) oil collection system is reviewed in Section 2.3.3.9, Reactor Coolant Pump Oil Collection. The RC system has the following intended functions for 1 O CFR 54.4(a)(1 ).

Provide sufficient core cooling during normal plant evolutions and anticipated operational occurrences to preclude the occurrence of significant core damage. _
Provide a barrier against the release of fission products from the reactor core to the environment.
Support containment pressure boundary. The RC system has the followir:ig intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. -The RC system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (RCP oil collection) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Support the evaluation that demonstrates compliance with the Commission's regulations for pressurized thermal shock (10 CFR 50.61). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Perform functions (maintain pressure boundary and provide core cooling) that demonstrate compliance with the Commission's regulations for fire protection (1 O CFR 50.48) and for station blackout (1 O CFR 50.63). FSAR References Section 3.9.5 Section 4.1 Chapter 5 Section 9.5.1.2.6 (oil collection system) ComoonentS Subject to Aging Management Review The reactor coolant system is reviewed as the following subsystems. The fuel assemblies are periodically replaced based on burnup and are not subject to aging management review.
Section 2.3.1.1, Reactor Vessel
Section 2.3.1.2, Reactor Vessel Internals
Section 2.3.1.3, Reactor Coolant Pressure Boundary.
Section 2.3.1.4, Steam Generators -Norisafety.:.related components of the system not included in other review;:; whose failure could prevent satisfactory accompiishment of safety are reviewed in 2.3.1.5, RCS Systems in Scope for 1 O CFR 54.4(a)(2). * -* < '
r ' 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-2 2.3.1.1 Reactor Vessel Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The review of the reactor vessel includes the vessel (a component in the RC system code) and the control element drive system (system code CED). Reactor Vessel The purpose of the reactor vessel is to enclose and support the reactor vessel internals and the reactor core and to provide a barrier to the release of radioactive materials from the core. The reactor vessel forms part of the reactor coolant pressure boundary, containing the flow path of reactor coolant through the vessel internals and reactor core. The reactor vessel head provides penetrations for the control element assembly (CEA) extension and drive shafts, venting, and in-core instrumentation. The reactor vessel is a right circular cylinder with two hemispherical heads". The lower head is permanently welded to the lower end of the reactor vessel shell. The closure head (also known as the reactor vessel closure head) can be removed to provide access to the reactor vessel *internals. The head flange is drilled to match the vessel flange stud bolt locations. The stud bolts are fitted with spherical washers located between the closure nuts and the head flange. These washers m(3intain stud alignment during bolt-up when flexing of the head must be accommodated. The lower surface of the head flange is machined to provide a mating surface for the vessel closure seals. The vessel flange is a forged ring with a machined ledge on the inside surface to support the core support barrel, which in turn supports the reactor internals and the core. The flange is drilled and tapped to receive the closure studs and is machined to provide a mating surface for the reactor vessel closure seals. An externally tape.red transition section connects the flange to the cylindrical shell. Sealing is accomplished by using two silver-plated, nickel-chromium-iron (NiCrFe) alloy, self-energized 0-rings. Nozzles are provided in the closure head for nuclear instrumentation and control element drive mechanisms. The four inlet and two outlet nozzles are located radially on a common plane just below the vessel flange. Ample thickness in this vessel course provides most of the reinforcement required for the nozzles. Additional reinforcement is provided for the individual nozzle attachments. A boss located around the outlet nozzles on the inside diameter of the vessel wall provides a mating surface for the core support barrel and guides the outlet coolant flow. This boss and the outlet sleeve on the core support barrel are machined to a common contour to minimize reactor coolant bypass leakage. Shell sections are joined to the nozzle region by a transition section.
Snubbers built into the lower portion of the reactor vessel shell limit the amplitude of flow-induced vibration!? in the core support barrel. 2.0 Scoping and Screening Methodology for Identifying *structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The flow skirt (baffle) is a cylinder, perforated with flow holes, and reinforced at the top and bottom with stiffening rings. The flow skirt is used to reduce inequalities in core inlet flow distributions and to prevent formation of large vortices in the lower plenum. The skirt is welded to the bottom head of the pressure vessel. Reactor vessel intended functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. Control Element Drive The purpose of the CED system is to control the position of the control element assemblies as a means of controlling core reactivity and reactor power. The CED system code includes the control element drive mechanism control system components, the control element drive mechanisms (CEDM), and the CEAs. The CEDMs are reviewed as part of the reactor vessel. The CEDMs are magnetic jack type drives used to vertically position and indicate the position of the CEAs in the reactor core. The CEDM pressure housings are part of the reactor coolant pressure boundary. The motor housing assembly of the CEDM is attached to the reactor vessel head nozzle by means of a threaded joint and is seal welded. The upper pressure housing is threaded into the top of the motor housing assembly and seal welded. The upper pressure housing encloses the CEDM extension shaft and contains a vent. The upper pressure housing is threaded into the top of the motor housing assembly and seal welded. The upper pressure housing encloses the CEDM extension shaft and contains a vent. The top of the upper pressure housing is closed by means of a Versa-Vent tube. The CED system has the following intended function for 10 CFR 54.4(a)(1).
Support the reactor coolant pressure boundary. The CED system has no intended functions for 10 CFR 54.4(a)(2) or (a)(3). FSAR References Section 5.3 Section 3.9.4 Section 4.2.2.4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review The following subassemblies of the reactor vessel are subject to aging management review:
Vessel shell
Primary coolant nozzles and nozzle safe ends
Reactor vessel closure head and nozzles
CEDM assembly
lncore instrumentation/heated junction thermocouple-core exit thermocouples (ICl/HJTC-CET)
Interior and exterior attachments The CEAs are periodically replaced based on burnup; as short-lived components, the CEAs are not subject to aging management review. Table 2.3.1-1 lists the component types that require aging management review. Table 3.1.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G172 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-1 Reactor Vessel Componen.ts Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary ICl/HJTC-CET assemblies
Swageloc modified bodies
Compression collar
Hold down nuts Closure head Pressure boundary * .Center dome
Flange Closure head penetrations Pressure boundary
Vent pipe nozzle
CEDM and ICI nozzles Closure head bolting Pressure boundary
Studs
Nuts *Washers Control rod drive assembly Pressure boundary
CEDM motor housing (tube) and upper end fitting *Versa vent assembly
CEDM motor housing lower end fitting ICI assembly Pressure boundary
Flange adaptor *Seal plug
Swageloc* modified body
Compression collar/nut Flow skirt Pressure boundary Nozzles (including safe ends) Pressure boundary
Inlet/outlet 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-1 (Continued) Reactor Vessel Components Subject to Aging Management Review Component Type Intended Function Vessel external attachment Structural support
Vessel support pads Vessel external attachment Pressure boundary
Closure head lifting lugs Vessel internal attachments Structural support
Core stabilizing lugs
Core stop lugs Vessel flange (including core barrel Pressure boundary support ledge) Structural support* Vessel shell assembly (including Pressure boundary welds)
Bottom head -Torus -Dome *Upper shell
Intermediate shell *Lower shell 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-7

/ 2.3.1.2 Reactor Vessel Internals Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the reactor vessel internals is to properly distribute the flow of coolant delivered to the vessel, and to align, support and protect the fuel assemblies. The components of the reactor internals are divided into three major parts consisting of the core support structure assembly, the upper guide structure assembly, and the in-core instrumentation support structure. The flow skirt, although functioning as an integral part of the coolant flow path, is separate from the internals and is welded. to the bottom head of the pressure vessel.

The core support structure assembly consists of the core support barrel and the lower support structure. The core support structure assembly is supported at its upper end by the upper flange of the core 'support barrel, which rests on a ledge in the reactor vessel. The core support barrel has four alignment keys, which align the core support barrel assembly relative to the reactor vessel and reactor vessel head. The lower flange of the core support barrel supports, secures, and positions the lower support structure. The lower support structure provides support for the core by means of a core support plate supported by columns mounted on support beams that transmit the load to the core support barrel lower flange. The core support plate provides support and orientation for the lower ends of the fuel assemblies via alignment pins. The lower end of the core support barrel is restricted from excessive lateral and torsional movement by six snubbers interface with the pressure vessel wall. The core shroud, which provides a flow path for the coolant, is also supported and positioned by the core support plate. The core shroud provides an envelope for the core and limits the amount of coolant bypass flow. The shroud consists of two ring sections welded together and at the bottom to the core support plate. *The upper guide structure assembly consists of the upper guide structure support plate assembly, control element assembly shrouds, holddown spring, and fuel alignment plate. The upper guide structure assembly aligns and supports the upper end of the fuel assemblies, maintains the CEA spacing, holds down the fuel assemblies during operation, and supports the in-core instrumentation plate assembly. The upper end ofthe assembly is a structure consisting of a support flange welded to the top of.a cylinder. A support plate is welded to the inside of the cylinder approximately in the middle. The support plate aligns and supports the upper end of the CEA shrouds. The shrouds extend from the fuel alignment plate to an elevation above lhe upper guide structure support plate. The CEA shrouds consist of a cylindrical upper section welded to a base and a flow channel structure shaped to provide flow passage for the coolant through the fuel alignment plate. The shrouds are bolted to the fuel alignment plate. At the upper guide structure support plate, the shrouds are connected to the plate by spanner nuts. The fuel alignment plate is designed to align the upper ends of the fuel assem.blies and to support and align the lower ends of the* CEA shrouds. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The in-core instrumentation support system begins outside the reactor pressure vessel, penetrates the vessel head, and terminates at the lower end of the fuel assembly. The core instrumentation nozzles are located around the perimeter of the* reactor vessel head. Each instrumentation path is supported over its full length by the external guidance conduit, internal guide tubes, thimble support plate, and thimbles that extend down into selected fuel bundles. The in-core instrumentation is routed so that the detectors are located and spaced throughout the core. The guide tubes and the in-core thimbles are attached to and supported by the thimble support plate assembly. The thimble support plate assembly fits within the confines of the reactor vessel head and rests in the recessed section of the upper guide structure assembly. Above the thimble support plate, the guide tubes bend and are gathered to form stalks that extend into the reactor vessel head instrumentation nozzles. The thimble support plate assembly is raised and lowered during refueling to withdraw and insert all instruments and their thimbles simultaneously. The pressure boundaries for the in-core instrumentation is at the reactor vessel head instrument nozzle closure, where the external electrical connections to the in-core instruments are made. Reactor vessel internals intended functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. FSAR References Section 3.9.5 Components Subject to Aging Management Review The core support structure assembly, the upper guide structure assembly, and the incore instrument support structure are subject to aging management review. Table 2.3.1-2 lists the component types that require aging management review. Table 3.1.2-2 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying* Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-2 Reactor Vessel Internals Components Subject to Aging Management Review *component Type Intended Function Reactor vessel internal connector Structural support components
Bolts, studs, nuts, washers
Locking bars, caps and keys *Dowels *Cap screws .. Lower support structure-assembly Flow distribution
Core support plate Structural support Lower support structure assembly Structural support
Fuel alignment pins
Core support column welds
Deep core support beams
Core support beams * .. .. Core support barrel assembly Structural support
Upper cylinder, including welds
Lower cylinder girth welds .
Lower cylinder axial welds
Upper section flange
Upper section flange weld
Lower section flange
Lower section flange weld
Alignment keys
Snubber assembly shims and pins
Snubber assembly bolt Upper internals assembly ' *Structural support
Upper guide structure SUP,port plate assembly
Fuel alignment plate 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Res'ults Page 2.3-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-2 (Continued) Reactor Vessel Internals Components Subject to Aging Management Review Component Type Intended Function Core shroud assembly Structural support
Shroud vertical plates
Shroud former plates *Welds Core shroud lug and lug inserts Structural support Core shroud lug dowel pins Structural support Upper internals CEA shroud assembly Structural support
Peripheral instrument tubes
Non-peripheral instrument tubes Upper internals assembly Flow distribution
Flow bypass insert assembly Upper internals assembly Structural support
Socket head cap screw (also referred to as CEA shroud bolts) CEA shroud assembly Structural. support
Modified shroud ext. shaft guide sub-assembly -extension shaft *Tube CEA extension shaft guides Structural support Holddown spring Structural support ICI Structural support
Thimble -lower part Reactor vessel internal components not Flow distribution addressed in another line item Structural support 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-11 2.3.1.3 Reactor Coolant Pressure Boundary Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the RCS is to contain and circulate reactor coolant between the reactor core and steam generators and to provide a barrier to the release of radioactive materials from the core. The major components of the system include two parallel heat transfer loops, each containing one steam generator and two reactor coolant pumps; a pressurizer connected to one of the reactor vessel outlet pipes; and associated piping. Effluent discharges from the pressurizer safety valves are condensed and cooled in the quench tank. System pressure is controlled by the pressurizer, Where steam and water are maintained in thermal equilibrium. Steam is formed by energizing immersion heaters in the pressurizer or conden*sed by the pressurizer spray to limit pressure variations caused by contraction or expansion of the reactor coolant. The average temperature of the reactor coolant varies with power level and the fluid expands or contracts, changing the pressurizer water level. The charging pumps and letdown control valves in the chemical and volume control system are used to maintain the programmed pressurizer water level. A continuous but variable letdown purification flow is maintained to keep the RCS chemistry within prescribed limits. Two charging nozzles and a letdown *nozzle are provided on the reactor coolant piping for this operation. The charging flow is also used to alter the boron concentration or correct the chemistry of the reactor coofant. Other reactor coolant loop penetrations are the pressurizer surge line in one reactor vessel outlet pipe; the four safety injection inlet nozzles, one in each reactor vessel inlet pipe; one outlet no.zzle to the shutdown cooling system jn each reactor vessel outlet pipe; tWo pressurizer spray nozzles; vent and drain connections; and sample cor:mections and instrument connections. Overpressure protection for the reactor coolant pressure boundarY is provided .by two loaded safety valves connected to the top of the** pressurizer. These* valves discharge to the quench tank, where the steam is released under water.to be condensed and cooled. If the steam discharge exceeds the capacity of the quench tank, it is relieved to the containment atmosphere through a rupture disc. As stated in FSAR Section 5.2, the reactor coolant pressure boundary (RCPB) is defined in accordance with 10 CFR 50.2(v) to include all pressure* retaining components such as pressure
vessels, piping, pumps, and valves that are: a. Part of the RCS, or 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information b. Connected to the RCS, up to and including any and all of the following: 1. The outermost containment isolation valve in piping which penetrates primary reactor containment. 2. The second of the two valves normally closed during normal reactor operation in system piping which does not penetrate primary reactor containment. 3. The RCS safety valves. -The major Class 1 components of the reactor coolant pressure boundary addressed in this review include the reactor coolant pumps (RCP), reactor coolant piping, pressurizer, pressurizer safety valves, and the Class 1 portions (piping and valves) of systems connected to the RCS, which are the safety* injection system and the chemical and volume contrql system. This review also includes non-Class 1 components of the RCS that have an intended function for license renewal but were not included in another aging management review. RCPB intended -functions for license renewal are included in the RCS intended functions in Section 2.3.1, Reactor Coolant System. FSAR References Chapter 5 Components Subject to Aging Management Review . . . The non-Class 1 sections of the safety injection system and the chemical and volume control systems are reviewed In Section 2.3.2.2, Saf£;?ty Injection, and Section 2.3.3.1, Chemical and Volume Control; respectively., Nonsafety-related components of the RCPB not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2). Remaining RCPB components are reviewed as listed below.
Table 2.3.1-3 lists the component types that require aging management review Table 3.1.2-3 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-13 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for RCPB components subject to aging management review are provided in the following license renewal drawings. Reactor Coolant Svstem LRA-G172 LRA-G179 LRA-G160 sh 4 (RCP oil coolers, cooling air heat exchangers, and thermal barrier heat exchangers) Safetv Injection Svstem LRA-G167 sh 2 LRA-G 167 sh 4 Chemical and Volume Control Svstem LRA-G 168 sh 1 LRA-G168 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element (non-Class 1) Pressure boundary Heat exchanger coil Pressure boundary (RCP lower oil cooler) Heat exchanger water jacket Pressure boundary (seal heat exchanger) Heat exchanger (channel head) Pressure boundary (RCP upper oil cooler) Heat exchanger (shell) Pressure boundary . (RCP upper oil cooler) Heat exchanger (tube sheet) Pressure boundary (RCP upper oil cooler) Heat exchanger (tubes) Pressure boundary (RCP upper oil cooler) Heat exchanger (tubes) Pressure boundary (RCP motor air cooler) Heat exchanger (channel head) Pressure boundary (RCP motor air cooler) Heat exchanger (tube sheet) Pressure boundary (RCP motor air cooler) Orifice Flow control Pressure boundary Piping 4 inch nominal pipe Pressure boundary size (NPS) Piping < 4 inch NPS Pressure boundary Piping (non-Class 1) Pressure boundary Piping (non-Class 1) Pressure boundary (RCP lower oil cooler) Piping (non-Class 1) Pressure boundary (RV flange leak off lines) 2.0 Scoping and Screening Methodology for Identifying Structures and Components. Subject to Aging Management Review and Implementation Results Page 2.3-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 (Continued) Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Pressurizer heater sheath Pressure boundary Pressurizer heater sleeve end Pressure boundary caps Pressurizer heater plug, heater Pressure boundary sleeves and heater sheath to sleeve welds Pressurizer heater internal Structural support support structures Pressurizer instrument nozzle Pressure boundary Pressurizer lower head Pressure boundary Pressurizer manway cover Pressure boundary . Pressurizer manway gasket Pressure boundary' retainer plate Pressurizer nozzles (spray Pressure boundary_ nozzle, surge nozzle, safety nozzle) Pressurizer shell and upper Pressure boundary head Pressurizer spray head Flow control Pressurizer support skirt Structural support Pressurizer welds
Pressure boundary -Instrument.sleeve to instrument -Nozzle to safe-end weld overlays RCS piping hot leg -Overlay welds Pump casing (RCP) Pressure boundary Pump cover (RCP) Pressure boundary RCS cold leg Welds Pressure boundary 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-16 Waterford Steam El.ectric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-3 {Continued) Reactor Coolant Pressure Boundary Components Subject to Aging Management Review Component Type Intended Function Safe end (pressurizer spray, Pressure boundary , drain, pressurizer instrument nozzles) Safe end (hot leg and Pressure boundary pressurizer surge, shutdown cooling and pressurizer safety) Thermal sleeve (charging, Structural integrity safety injection, surge, pressurizer spray) Therm owe II Pressure boundary Tubing (hon-Class 1) Pressure boundary Valve body::, 4 inch NPS Pressure boundary Valve body < 4 inch NPS Pressure boundary Valve body (non-Class 1) Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.1.4 Steam Generators Description The purpose of the steam generator (SG) system is to transfer heat from the RCS to the* secondary system coolant. Feedwater heated in the steam generators is converted to steam that drives the main turbine generator. Each steam generator is a vertical, inverted U-tube heat exchanger. Reactor coolant flows through the tubes while the secondary system coolant is on the shell side. Reactor coolant enters at the bottom of each steam generator through the single inlet nozzle, flows upward throl1gh the U-tubes, and leaves through the two outlet nozzles. A vertical divider plate separates the inlet and outlet plenums in the lower head. enters the steam generator through the feedwater nozzle where it is distributed via a feedwater distribution ring. The feedwater ring is constructed with discharge nozzles which discharge at the top of the feedwater ring. The down comer in the steam generator is *an annular passage fanned by the inner surface of the steam generator shell and the cylindrical shell that encloses the vertical U-tubes, Upon exiting from the bottom .of the down comer, the secondary flow is directed upward over the vertical U-tubes. Heattrahsferred from the primary side converts a portion of the secondary flow into steam. Upon leaving the vertical U-tube heat transfer surface, the steam-water mixture enters the -* centrifugal-type separators. These impart a centrifugal motion to the mixture and separate the water particles from the steam. The water exits from the perforated separator housing and combines with the feedwater to repeat the cycle. Final drying of the is accomplished by passage of the steam *through the single-tier banked dryers. . . The steam. generators contain an integral flow limiting .device consisting of seven venturis installed in the steam outlet nozzle. This flow restr:ictor reduces energy release to containment and foads oh the steam generator internals during a postulated steam line break while also limiting the RCS cooldown rate.
Manways and handtioles are provided for access to the steam.generator internals. The SG system has the following intended fun.ctions for 10 CFR 54.4(a)(1). . .
Transfer heat from the reactor coolant system to the secondary system. 2.0 Scoping anc;I Screening Methodology for Identifying Structures and Components Subject to Af!ing Management Review and Implementation Results Page 2.3-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Limit steam release after a steam line guillotine break to reduce energy release to containment, reduce loads 'on the steam generator internals, and limit RCS cooldown following steam line rupture.
Maintain secondary system pressure boundary.
Provide a source of steam for the turbine-driven emergency feedwater pump.
Maintain the reactor coolant pressure boundary. The SG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SG system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 5.4.2 Components Subject to Aging Management Review Reactor coolant inlet and outlet piping and Class 1 instrumentation is reviewed in Section 2.3.1.3, Reactor Coolant Pressure Boundary. Other SG instrumentation components are reviewed in Section 2.3.4.3, Main Feedwater. SG blowdown and sampling components are evaluated in Section 2.3.4.4, Main Steam. Nonsafety-related SG components whose failure could prevent satisfactory accomplishment of safety functions not reviewed in other reports are reviewed in Section 2.3.1.5, RCS Systems in Scope for 10 CFR 54.4(a)(2). Remaining steam generator components are reviewed as listed below. Table 2.3.1-4 lists the steam generator components that require aging management review and their intended functions. Table 3.1.2-4 provides the results of the aging management review for steam generator components. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-19 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for steam generator components subject to aging management review are provided in the following license renewal drawings. Reactor Coolant Svstem LRA-G172 Main Steam Svstem LRA-G151 sh 1 LRA-G 164 sh 5 Main Feedwater Svstem LRA-G 153 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 Steam Generators Components Subject to Aging Management Review Cc;>mponent Type Intended Function Pressure boundary closure Pressure boundary bolting Tubesheet Pressure boundary Tube to tubesheet weld Pressure boundary Channel head Pressure boundary Partition plate Pressure boundary Primary inlet and outlet nozzle Pressure boundary transition pieces Primary side pressure nozzle Pressure boundary Inlet and outlet nozzle dam Pressure boundary rings Primary manway drain tube Pressure boundary Primary manway cover Pressure boundary Primary manway insert Pressure boundary Tubes Heat transfer Pressure boundary ' Tube plugs Pressure boundary Secondary shell (elliptical head Pressure boundary with integral steam nozzle, upper, intermediate and lower shells, transition cone) Flow limiter insert Pressure boundary Feedwater nozzle Pressure boundary Feedwater nozzle thermal Pressure boundary sleeve Instrument and sampling Pressure boundary nozzles Slowdown nozzle Pressure boundary 2.0 s'coping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-21
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 (Continued)
Steam Generators Components Subject to Aging Management Review Component Type Intended Function Secondary manway, handhole, Pressure boundary inspection port, and recirculation nozzles -* Seeondary manway, .. boundar-Y inspection port, and recirculation nozzle cover plates<a)
Handhole ancl inspection port cover plates(b) Pressure boundary Hand hole and inspection* port Pressure boundary diapnragmi; External shell attachments Pressure boundary Tube support plates, anti-Structural integrity vibration assembly bars Wrapper barrel, associated Structural integrity components Recirculation sleeve, Structural integrity wrapper plug seal plates Anti-vibration assembly end
Structural integrity caps, retaining rings, retaining bars, stayrod washer, tube support plate shim Stayrods, wedges, tube Structural integrity support components Feedwater header and support Structural integrity components Feedwater spray nozzles, Structural integrity nozzle caps, filler plates Primary separator assembly Structural integrity components Drain bucket assembly Structural integrity components 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-4 (Continued) Steam Generators Components Subject to Aging Management Review Component Type Intended Function Lower deck components StruCtural integrity Middle deck components Structural integrity Sludge collector assembly Structural integrity Secondary separator Structural integrity components Pedestal support Structural support Snubber lug, key bracket Structural support a. Cover plates in this line apply only to ones without seal welded diaphragms.
b. Cover plates in this line apply only to ones with seal welded diaphragms. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-23

\. 2.3.1.5 RCS Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Phvsical Failure This section summarizes the scoping and screening results for RCS systems based on 1 O CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.2 and 2.1.2.1.2. Phvsical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-24 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information criterion affected RCS. systems, those systems are within the scope of license renewal per 10 CFR 54.4(a)(2). Leakage or Spray Nonsafety-related portions o.f safety-related systems containing water, oil, or steam are considered within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. RCS systems meeting this criterion are within the scope of license renewal per 1 O CFR 54.4(a)(2). The RC system and the SG system are within the scope of licen_se renewal based on the criterion of 10 CFR 54.4(a)(2) for physical interactions. System Descriptions The RC system is described in Section 2.3.1, Reactor Coolant System and Section 2.3.1.3, Reactor Coolant Pressure Boundary. The SG system is described in Section 2.3.1.4, Steam Generators. ' Certain nonsafety-related components in these systems are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) because of the potential for physical interactions between nonsafety-related components and safety-:related equipment. FSAR References FSAR references are provided in the sections referenced above. Components Subject to Aging Management Review

For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-25
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (4) An endpoint of a plant-specific piping design analysis to ensure that forces and moments are restrained in three orthogonal directions. For spatial interaction, components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 1 O CFR 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in a system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 10 CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related SSCs directly connected to safety-related SSCs. Series 2.3.1-5-x tables list the RCS. component types that require aging management review for 1 O CFR 54.4(a)(2) based on potential for physical interactions. . . Series* 3.1.2-5-x tables provide the results of the aging management review for the RCS for 10 CFR 54.4(a)(2) based on potential for physical interactions. System Code System Name Component Types AMR Results RC Reactor Coolant Table 2.3.1-5-1 Table 3.1.2-5-1 SG Steam* Generators Table 2.3.1-5-2 Table 3.1.2-5-2 License Renewal Drawings Additional details for components subject tq aging management review are provided in the following license renewal drawings.
System Code System Name LRA Drawings RC Reactor Coolant LRA-G172 LRA-G179 SG Steam Generators LRA-G162 sh 2 LRA-G164 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-26 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-5-1 Reactor Coolant System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting_ Pressure boundary Filter housing Pressure boundary Flex hose Pressure boundary Orifice Pressure boundary Piping Pressure boundary . Pump casing Pressure boundary Rupture disc Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-27 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.1-5-2 Steam Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-28 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.2 Engineered Safety Features The following Engineered Safety Features systems are described in this section.
Section 2.3.2.1, Containment Spray
Section 2.3.2.2, Safety Injection
Section 2.3.2.3, Containment Penetrations
Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-29 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.2.1 Containment Spray System Description The purpose of the containment spray (CS) system is to remove heat from containment following an accident inside containment. In conjunction with the containment cooling heating, ventilation and air conditioning (HVAC) system, the CS system maintains the containment pressure and temperature within design limits and limits offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CS system also limits offsite radiation doses by the reduction of iodine in the post-accident containment atmosphere. The CS system consists of two independent and redundant loops, each containing a CS pump, shutdown cooling heat exchanger, piping, valves, spray headers, and spray nozzles. There are two headers, each with four spray rings. Each header conforms to the shape of the containment dome. When actuated following an accident, the system has two modes of operation: the injection mode and the recirculation mode. In the injection mode, the system pumps borated water from the refueling water storage pool (RWSP) into the spray headers and through the spray nozzles in the containment dome. When the water reaches the containment floors, it drains toward the safety injection system sump. After low level is reached in the RWSP, the recirculation mode is initiated in which suction for the CS pumps is aligned to the* safety injection system sump. During the recirculation mode, the spray water is cooled by the shutdown cooling heat exchangers prior to its discharge into the containment. The shutdown cooling heat exchangers are cooled by the component cooling water system. The pH of water that is circulated within the containment during the recirculation mode is controlled to minimize re-evolution of iodine scrubbed from the containment atmosphere by the spray. Trisodium phosphate dodecahydrate (TSP) is stored in the containment in multiple stainless steel baskets located on the-11 ft. MSL elevation. TSP is dissolved by the containment spray water and other water draining toward the safety injection system sump and thus raises pH of the recirculated water. The CS system has the following intended functions for 10 CFR 54.4(a)(1).
Remove heat to maintain the containment pressure and temperature within design limits and limit offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment.
Remove iodine from the containment atmosphere and retain it in solution to limit dose consequences. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Support containment pressure boundary. The CS system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory *accomplishment.of a safety function. The CS system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (shutdown cooling heat exchanger) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.2.2 Section 6.5.2 Components Subject to Aging Management Review The TSP baskets are evaluated as structural components in Section 2.4.1, Reactor Building. The RWSP is a structural component and is reviewed in Section 2.4.2, Nuclear Plant Island Structure. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.2.4, ESF Systems in Scope for 1 O CFR 54.4(a)(2). Remaining CS system components are reviewed as listed below.
Table 2.3.2-1 lists the_component types that require aging management review. Table 3.2.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 3 LRA-G163 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-1 Containment Spray System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Heatexchanger(channelhead) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heat exchanger (water jacket) Heat transfer Pressure boundary Nozzle Flow control Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Separator Filtration Pressure boundary Therm owe II Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-32 2.3.2.2 Safety Injection System Description Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information The purpose of the safety injection (SI) system is to provide core cooling following a design basis accident. The system is designed to inject borated water into the reactor coolant system to flood and cool the reactor core and to provide heat removal from the core for extended periods following a loss of coolant accident (LOCA). The system is also designed to inject borated water into the reactor coolant system to increase the shutdown margin following a rapid cooldown due to a main steam line break. In addition to its accident related functions, portions of the safety injection system are used as part of the shutdown cooling system, which removes heat from the RCS during norm.al plant cooldown and refueling. The safety injection system is comprised of.the following three separate subsystems:
High pressure safety injection system (HPSI)
tow pressure safety injection system (LPSI)
Safety injection tanks (SITs) The components of these subsystems are arranged ih two redundant, full-capacity trains; each functionally identical to the other. rhe major components of t!iis system are three HPSI pumps, two LPSI pumps, four safety injection tanks, high-pressure injection valves, low-pressure injection valves, and the refueling water storage pool (RWSP). In addition, the system uses the shutdown cooling heat *exchangers, which are part of the containment spray system. The SI system is in standby during normal operation: SI system operation is initiated by either low reactor coolant system pressure or high containment pressure. Actuation of the system starts the.HPSI and LPSI pumps and opens the valves that provide a flow path from the RWSP through these pumps to the reactor coolant system. When a low level is sensed in the RWSP,. the LPSI pumps are stopped, .and the HPSI pump suction is diverted to the safety injection sump in containment for recirculation of coolant. The safety injection tanks contain borated water pressurized by nitrogen cover gas. When RCS pressure drops below the SIT cover pressure, the SITs automatically discharge their contents into the RCS. The primary function of the HPSI system is to inject borated water into the RCS if a break occurs in the RCS boundary. For small breaks, the RCS pressure remains high for a long period of time following the accident, and the HPSI system ensures that the injected flow is sufficient to maintain core cooling. The HPSI system is also used to maintain a borated water cover over the core for extended periods during recir?ulation mode following a LOCA. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The HPSI system is arranged in two redundant trains. The HPSI pump in each train can supply water to the RCS from either the RWSP or the safety injection sump. From the HPSI pump discharge, each header splits into four RCS cold leg injection lines and one hot leg injection line.
Upon initiation of safety injection, the HPSI pumps will discharge to all four RCS cold legs. For long-term core cooling, the HPSI system is realigned for simultaneous hot and cold leg injection. A third HPSI pump, which may be aligned to either train, is provided as an installed spare. Each pump is also supplied with a recirculation flow path back to the RWSP to ensure minimum flow rates .through the pump when operating at shut-off head conditions. The LPSI system serves two functions. One is to inject large quantities of borated water into the RCS in the event of a large pipe rupture. The LPSI system delivers water from the RWSP to the RCS, via the RCS safety injection nozzles, when system pressure falls below pump shut..:off head. The other function is to provide shutdown cooling flow through the reactor core and shutdown cooling* heat exchanger for nornial plant shutdown cooling operation or as required for long-term core cooling for small breaks. During shutdown cooling, a portion of the reactor coolant from the RCS _hot legs is circulated by the LPSI pumps through the shutdown cooling
heat exchangers to the LPSI headers and is returned to the RCS cold legs through the safety injection nozzles. The HPSI and LPSI systems are similarly aligned to the RWSP and safety injection sump.* However, the discharge of each LPSI pump is directed to only two oHhe four RCS cold legs. The LPSI pumps are also supplied _with a minimum recirculation flow path to the RWSP. The four safety injection tanks used to flood the core with borated water following depressurization as a result of a LOCA or main steam line *break . Flow from each of the tanks is directed through a check valve and outlet valve to a single RCS cold leg via a safety
injection nozzle located on the RCS piping near the reactor vessel inlet. The SI system has the following intended functions for 10 CFR 54.4(a)(1).
Inject borated water into the reactor coolant system to flood and cool the reactor core and to provide heat removal from the core for extended periods following a LOCA.
Inject borated water into the reactor coolant system to increase the shutdown margin following a rapid cooldown due to an MSLB.
Provide shutdown cooling flow through the reactor core and shutdown cooling heat exchanger for normal plant shutdown cooling operation.
Maintain integrity of reactor coolant pressure boundary.
Support containment pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-34 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The SI system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SI system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (shutdown cooling mode) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.3 Section 9.3 .. 6 (shutdown cooling) Components Subject to Aging Management Review Class 1 components supporting the reactor coolant pressure boundary are reviewed in Section
2.3.-1.3, Reactor Coolant Pressure Boundary. The RWSP is a structural component and is reviewed in Section 2.4.2, Nucilear Plant Island Structure. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.2.4, ESF Systems in Scope for 10 CFR 54.4(a)(2).
Remaining SI system components are reviewed as listed below.
Table 2.3.2-2 lists the component types that require aging management review. Table 3.2.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 3 LRA-G 162 sh 1 LRA-G163 LRA-G 167 sh 1 LRA-G 167 sh 2 LRA-G167 sh 3 LRA-G 167 sh 4 LRA-G 168 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-35 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-2 Safety Injection System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Flow control Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-36 2.3.2.3 Containment Penetrations System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As described in FSAR Chapter 3, Section 3.8, the primary containment is a free-standing steel pressure vessel which is surrounded by a reinforced concrete shield building. The containment vessel is a cylindrical steel pressure vessel with hemispherical dome and ellipsoidal bottom that houses the reactor pressure vessel, the reactor coolant piping, the pressurizer, the quench tank, the reactor coolant pumps, the steam generators, and the safety injection tanks. It is completely enclosed by the reinforced concrete shield building. An annular space is provided between the walls and domes of the containment vessel and the concrete shield building to permit construction operations and in-service inspection. The containment vessel and shield building contain mechanical penetrations that provide openings for process fluids to pass through the containment boundaries and still maintain containment integrity. The mechanical penetrations, their associated isolation valves, and related design features that are not included in another aging management review are included in this review. The grouping of containment isolation valves from various plant systems into a consolidated review is appropriate for scoping as indicated in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Section 2.1.3.1. Systems described or referenced below have the following intended function for 10 CFR 54.4(a)(1 ).
Support containment pressure boundary .. With the exception of the containment vacuum relief (CVR) system, the systems described below. have no other system intended *functions. Systems described elsewhere in the application have additional intended functions included in other aging management reviews as referenced. Containment Vacuum Relief The purpose of the containment vacuum relief (CVR) system is used to prevent excess external pressure on the primary containment steel shell. The system consists of two redundant penetrations that connect the shield building annulus with the containment atmosphere. The penetrations provide a flow path for air to pass from the annulus to the containment. Each flow path is provided with its own set of isolation valves, which remain closed during normal operation. In the event that the air pressure inside containment drops below that of the annulus, system instrumentation opens the automatic isolation valves, which allow air pressure in the annulus to bleed into the containment. Pneumatic operated butterfly valves are installed on the annulus side of the containment penetrations. These valves serve as both automatic relief valves and containment isolation 2.0 Scoping and Screening rviethodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-37 i \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information valves. The valves are provided with backup air accumulators that will allow valve operation in the event of a loss of instrument air. Check valves are installed on the containment side of the penetrations and serve as containment isolation valves. The valves have magnetic latches that hold the valve in the close position, but the valves will open quickly against a small differential pressure. In addition to the intended function of supporting containment pressure boundary, the CVR system has the*following .intended function for 10 CFR 54.4(a)(1).
Protect the containment vessel from external pressure by limiting the pressure differential between the shield building annulus and containment atmosphere. Fuel Handling and Storage The purpose of the fuel handling and storage (FHS) system is to. provide the ability to defuel and refuel the reactor core. The FHS system provides a safe, effective means of transporting, handling and storing fuel and control element assemblies. The majority of the components in the FHS system code are structural components and are covered in the structural aging management reviews. The fuel transfer tube and blind flange-are considered part of this system code. These components form part of the containment pressure boundary. Hvdroqen Recombiners and Analyzers
The purpose of the hydrogen recombiners and analyzers (HRA) system is to monitor the hydrogen gas concentration in the containment and limit that concentration by recombination with oxygen. The stationary thermal recombiners each consist of an inlet pre-heater section,* a heater-rec.ombination section, and a louvered exhaust chamber. They are designed and . operated on the principle of natural convection, requiring no moving parts. The system includes two hydrogen analyzers. Each consists of sample and return lines, isolation valves, and a hydrogen analyzer that includes sample coolers, moisture separators, and sample pumps. For each unit there are seven sample lin.es which take six separate samples of the containment atmosphere and one sample of the annulus atmosphere. Each set of six lines has a common header inside the containment and penetrates the containment in a separate penetration assembly.*
The hydrogen recombiners and analyzer components are classified as*safety-related. However, consistent with changes to 1 O CFR 50.44, Amendment 192 to the Waterford 3 operating license eliminated the requirement for these components to mitigate the consequences of a design basis accident. Consequently, apart from support of the containment pressure boundary, the HRA system has no safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplementa'tion Results Page 2.3-38 Waterford Steam Electric Station, Unit 3 License Renewal Application Tec_hnical Information Other Systems Described Elsewhere in the Application The following systems have containment penetrations included in this review of containment penetrations. Each of these systems is described in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). System Code ANP ARM BM CAP GWM LRT PMU PSL FSAR References Section 3.8 Containment Vacuum Relief Section 3.8.2.3 Section 6.2.1.1.2 System Name Annulus Negative Pressure Area Radiation Monitoring (see Radiation Monitoring) Boron Management Containment Atmosphere Purge Gaseous Waste Management Leak Rate Testing Primary Makeup Primary Sampling Fuel Handling and Storage Section 9.1.4 Hydrogen Recombiners and Analyzers Section 6.2.5.2.1 Section 6.2.5.2.2 Components Subject to Aging Management Review The structural portions of the containment penetrations (penetration pipe sleeves) are addressed in Section 2.4.1, Reactor Building. The internals of electrical penetration assemblies are reviewed in Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Control Systems. Containment penetration components that support intended functions for other systems are evaluated with their respective systems. Containment penetration components in the Class 1 boundary are reviewed in Section 2.3.1.3, Reactor Coolant Pressure Boundary. Remaining containment penetration components are reviewed as listed below. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-39 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-3 lists the component types that require aging management review. Table 3.2.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G161 sh 2 LRA-G 164 sh 1 LRA-G 170 sh 4 LRA-G853 sh 1 LRA-G 162 sh 2 LRA-G 164 sh 2 LRA-G171 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-40 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-3 Containment Penetrations Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-41 2.3.2.4 ESF Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SS Cs which could* impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Physical Failures This section summarizes the scoping and screening results for ESF systems based on 10 CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures may be related to structural support or t6 spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. _Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically
piping systems) are within the scope of license renewa.1 based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.2 and 2.1.2.1.2. Physical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are . reviewed in Section 2.4, Scoping and Screening Results: Structures.
Pipe Whip. Jet Impingement, or Harsh Environments Systems conta!ning nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-42 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information criterion affected ESF systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Sprav Nonsafety-related portions of safety-related systems containing water, oil, or steam are considered within the scope of license renew,al based on the criterion of 1 O CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. ESF systems meeting this criterion are within the scope of license renewal per 10 CFR 54.4(a)(2). The following ESF systems, described in the referenced sections, are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) for physical interactions.
Section 2.3.2.1, Containment Spray
Section 2.3.2.2, Safety Injection System Descriptions The ESF systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) because of the potential for physical interactions between nonsafety-related components and safety,..related equipment are described in the sections referenced above. FSAR References For FSAR references for these systems, see the sections referenced above. Components Subject to Aging Management Review For each safety-to-nonsafety interface, nonsafety-related components connected to re.lated components were included up to one of the foJlowing: (1) The first seismic anchor, which is defined as a devi".e or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point thaf encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-43 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information (4) An endpoint of a plant-specific piping design analysis to ensure that forces and. moments are restrained. in three or:thogonal directions. For spatial interaction, ESF system components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 10 CFR 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in an ESF system does not fail or assumes failure only at specific locations, then that piping is Within the scope of license renewal per 1 O CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 1 a* CFR 54..4(a)(2), the intended function of pressure . boundary includes maintaining structural integrity for components that are included for related SSCs d_irectly connected to safety-related SSCs. . . Series 2 .. 3.2-4-x tables list the component types for ESF systems.that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. Series 3.2.2-4-x fables provide the results of the aging management review for ESF systems for 10 CFR 54.4(a)(2) based on potential for physical interactions. Code System Name Component Types AMR Results cs Containr:nent Spray Table 2.3.2-4-1 Table 3.2.2-4-1 SI *Safety Injection Table 2.3.2-4-2 Table 3.2.2-4-2 License Renewal Drawings Additipnal details for components subject to aging management review are provided in the following license renewal drawings. System Code System Name LRA [)rawings cs Containment Spray LRA-G163 SI Safety Injection LRA-G-167 sh 1 LRA-G-167 sh 2 LRA-G-167 sh 3 2.0
Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-44 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-4-1 Containment Spray System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review .. ---Component Type Intended Function Bolting Pressure boundary Orifice. Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tubing Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review anci Implementation Results page 2.3-45 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.2-4-2 Safety Injection System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-46 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information 2.3.3 Auxiliarv Systems The following systems are described in this section.
Section 2.3.3.1, Chemical and Volume Control
Section 2.3.3.2, Chilled Water
Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water
Section 2.3.,3.4, Compressed Air
Section 2.3.3.5, Containment Cooling HVAC
Section 2.3.3.6, Control Room HVAC
Section 2.3.3.7, Emergency Diesel Generator
Section 2.3.3.8, Fire Protection:.Water
Section 2.3.3.9, Reactor Coolant Pump Oil Collection
Section 2.3.3.10, Fuel Pool Cooling and Purification
Section 2.3.3.11, Nitrogen
Section 2.3.3.12, Miscellaneous HVAC
Section 2.3.3.13, Auxiliary Diesel Generator
Section 2.3.3.14, Plant Drains
Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-47 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.1 Chemical and Volume Control System Description This review includes the chemical and volume control system and the boric acid makeup system. Chemical and Volume Control The purpose of the chemical and volume control (system code CVC) system is to control the reactor coolant system (RCS) inventory, purity arid chemistry. Parfof the reactor coolant is bypassed through the CVC system via regenerative and letdown heat exchangers, which reduce the reactor coolant temperature before it passes through a filter and ion exchangers to purify the coolant. The purified coolant qm be sent to the volume control tank or diverted to the boron manage-ment system if necessary to reduce RCS inventory. Chemicals or additional coolant (e.g., primary water and boric acid) can be added to the volume control tank to adjust RCS che-mistry or increase inventory.* The charging pumps take suction from the volume control tank and pump the coolant back into the reactor coolant system. Discharge from the charging pumps is normally returned through the regenerative heat exchanger-to the reactor coolant system flow stream betWeen the reactor coolant pumps and the -reactor vessel. Charging pump flow can also be returned to the system as auxiliary pressurizer spray for operator control of RCS pressure during final stages of shutdown and to allow -pressurizer cooling* during normal operation and following an accident. -* The eve system also collects controlled bleed-off from the reactor coolant pump seals. The bleed-off flow is routed to the volume 9ontrol tank and then returned to the RCS. Degasification of the reactor coolant can be performed by venting the volume control-tank to'the gas surge header of the gaseous waste management system. Chemicals such as zinc (Zn) and hydrazine can be added after the volume control tank and pumped directly into the RCS via'the charging pumps. *The boric acid makeup (BAM) system works With the eve system to control reacfor coolant boron concentration. Concentrated boric acid from the BAM system can be added to the volume control tank to mix with the reactor coolant, or it can be delivered to the suction of the charging pumps for rapid injection into the RCS on receipt of a safety injection actuation signal. Some components of the CVC system form part of the reactor coolant pressure boundary. Other CVC system components are part of the containment pressure boundary. The CVC system has the following intended functions for 10 CFR 54.4(a)(1).
Maintain the rea_ctor coolant system inventory. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.3-48 Waterford Steam Electric Station, Unit 3 ( License Renewal Application Technical Information
Control boron concentration in the reactor coolant system.
Provide auxiliary pressurizer spray.
boric into the reactor coolant system upon a safety injection actuation signal.
Maintain integrity of reactor coolant pressure boundary.
Support containment pressure boundary. The CVC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity. of nonsafety-related components such that no physical interaction with safety-related components could prevent satisf(!ctorY. accomplishment of a safety function. The CVC system has the following intended functions for 10 eFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48); * . Perform a function* (letdown isolation) that demonstrates compliance with the Commission's reguiations for station blackout (1 O eFR 50.63). Boric Acid Makeup The purpose of the boric acid makeup (BAM) system is to provide a source of concentrated boric acid for RCS reactivity control and shutdown margin requirements. As .part of the chemical and volume control (CVC) syster:n, the BAM system can supply boric acid to the RCS through the
volume control tank and charging pumps for normal makeup, or directly through the charging pumps if necessary for load changes or shutdown margin control following an.accident. The BAM system includes the boric acid batching tank, boric acid makeup tanks, bori.c acid makeup pumps, and th\3 related piping,, valves, instruments and controls. The BAM system has the following intended function for 10 CFR 54.4(a)(1).
Provide a source of concentrated boric acid to the eve system for RCS reactivity control and shutdown margin requirements. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-49 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The BAM system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The BAM system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 9.3.4 *Section 9.3.4.2.1.2 (BAM described as a makeup system) Components Subject to Aging Management Review Class 1 components supporting the reactor coolant pressure boundary are reviewed in Section 2.3.1.3, Reactor Coolant Pressure BoundaJ"Y. CVC system components. that support safety injection system intended functions are reviewed in Section 2.3.2.2, Safety Injection. related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2). Remaining eve and BAM system components are reviewed as llsted below. Table 2.3.3-1 lists the component types that require aging management review. Table 3.3.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 1 LRA-G 162 sh 5 LRA-G163 LRA-G167 sh 3 LRA-G 168 sh 1 LRA-G 168 sh 2 LRA-G 168 sh 3 LRA-G171 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-50 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-1 Chemical and Volume Control System Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundaiy Bolting Pressure boundary Demineralizer Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Gear box housing Pressure boundary Heatexchanger(channel head) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exqhanger (tubes) Heat t(ansfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer: Filtration Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-51 --.,

2.3.3.2 'chilled Water System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the chilled water system is to provide chilled water for air handling systems in various parts of the reactor auxiliary building. There are two separate chilled water systems, the essential chilled water system and the supplementary chilled water system, with components from four different system codes: CHW (chilled water), RFR (refrigeration), SCC (supplementary chiller condensing) and SCH (supplementary chilled water). Essential Chilled Water Svstem The purpose of the essential chilled water system is to provide chilled water for those air handling systems which cool spaces containing equipment required for safety-related operations: The essential chilled water system furnishes chilled water for space cooling purposes and rejects heat through the component cooling water system. The essential chilled water system includes components in system codes CHW and RFR. The system consists of three full-capacity water chiller subsystems, each consisting of one chiller, pump, and expansion tank with level control actuated makeup,* and instrumentation and controls, piping and valves. Additionally, for corrosion protection, each subsystem provided with an individual and integral chemical feed system consisting. of a chemical feed tank, chemical feed and drain piping .. arid all necessary valves, fittings, accessories and appurtenances. The chiller's cool water is pumped to the cooling coils of the air handling units in various parts of the reactor auxiliary building. The safety-related chilled water loads are separated into two loops. The flow path can be aligned so that any two of the three water chiller subsystems can supply chilled water to the two cooling loops. Supplementarv Chilled Water Svstem The purpose of the supplementary chilled water system is to provide chilled water to related air handling units located in the reactor auxiliary building. The supplementary chilled water system consists of a chilled water recirculation loop with two packaged chiller units operating in series in a "lead/lag" configuration. The system components are located in the yard behind the chiller building with the chilled water supply and return piping routed underground to the reactor auxiliary building. The supplementary chilled water system includes components in system codes SCH, SCC and RFR. The SCC cooling towers were abandoned in place when the packaged chiller units were installed. The chilled water recirculation loop consists of two half-capacity chiller units, two full..:capacity pumps, eight air handling unit cooling coils, expansion tank, chemical addition pot, piping, valves, instrumentation and controls. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-52 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information The essential chilled water system has the following intended function for 10 CFR 54.4(a)(1).

Prov_ide chilled water for those air handling systems which cool spaces containing equipment required for safety::related operations ... The essential and supplementary chilled water systems have the following intended function for 10 CFR 54.4(a)(2):.*
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The essential chilled water system has the following intended function for. 1 O:CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commissior}'s regulations for fire protection (10 CFR 50.48). FSAR References Section 9.2.9 (essential chilled water system) No.ne for supplementary chilled water system. Components Subject to Aging Management Review Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory-accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2). Remaining chilled water systems components are reviewed as listed below. / ' Table lists the component types that require aging management review. table 3.3.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings.
LRA-G 160 sh 6 LRA-G853 sh 3 LRA-G853 sh 4 LRA-G853 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-53 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-2 Chilled Water System Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Therm owe II Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-54 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.3 Component Cooling and Auxiliary Component Cooling Water System Description This review covers the component cooling water system and the auxiliary component cooling water system. This review also includes supporting functions of the circulating water system and the control element drive mechanism 'cooling system. Component Cooling Water The purpose of the component cooling water (CC) system is to remove heat from the reactor coolant and the auxiliary systems during normal operation, shutdown, or emergency shutdown following a loss of coolant accident (LOCA) or a main steam line break inside containment. CC system cooling water is pumped through the dry cooling towers and the tube side of the component cooling heat exchangers, through the components being cooled, and back to the pumps. There are two redundant, independent, full-capacity CC system trains. Each CC system frain is provided with an auxiliary component cooling (ACC) system loop. The CC system includes two component cooling water heat exchangers, three full-capacity pumps, two dry cooling towers, one surge tank (baffled), one chemical addition tank, piping, valves, instrumentation and controls. The demineralized cooling water is pumped by the component cooling water pumps through two heat sinks: the dry cooling towers, where heat is dissipated to the atmosphere, and the component cooling water heat exchangers, where heat is removed by the ACC system. Component cooling water is distributed by four loops, two related and two*nonsafety-related. The coolant is then returned to the pumps. The component cooling water surge tank, connected to the suction side of the pumps, accommodates fluid expansion and contraction. The CC system has the following intended functions for 10 CFR 54.4(a)(1 ).
Dissipate the heat removed from the reactor and its auxiliaries during normal unit operation, d\,Jring refueling, or after a design basis accident.
Support containment pressure boundary. The CC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-55 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The CC system has the following intended function for 1 O CFR 54.4(a)(3).

Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Auxiliary Component Cooling Water The purpose of the ACC system is to remove heat from the CC system, if required, during normal operation, shutdown, or emergency shutdown following*a LOCA or a main steam line break inside containment. The CC and ACC systems work together to supply sufficient cooling to safety-and nonsafety-related reactor auxiliaries under all modes of operation. This cooling is also maintained to mitigate the consequences of a design basis accident.
ACC system cooling water is pumped through the shell side of the component cooling heat exchangers, where it removes heat from the component cooling water system and rejects it to the atmosphere via the wet cooling towers. There are two redundant, independent, full-capacity ACC trains, one for each train of the component cooling water system. Each train of the ACC system includes a component cooling water heat exchanger (shell side), a full-capacity pump, and a. wet type, mechanical draft cooling tower and cooling tower basin. The ACC system takes water from the wet cooling tower basin, pumps it through the component cooling water heat exchanger where its temperature is raised, and then to the wet cooling tower for heat dissipation to the atmosphere. The ACC system is required to operate whenever the heat rejection capacity of the CC system is exceeded by accident conditions, or whenever the outside ambient conditions prevent the CC system from rejecting its required heat load by way of the dry cooling towers. If not required, the ACC system is placed in standby with the ACC pumps secured.
The ultimate heat sink consists of the CC system dry cooling towers and the ACC system wet
cooling towers with water stored in the wet cooling tower basins. Each of two 100 percent capacity loops employs a dry and wet cooling tower. Each wet cooling tower consists of two cells with each cell serviced by four induced-draft fans. Replenishment of the wet cooling tower basins from on..:site water sources and/or the Mississippi River may be required in response to a tornado event if the tornado ejects water from the cooling tower basins. If available, additional makeup for thewet cooling tower basins can be supplied from onsite storage tanks (condensate storage tank, fire water storage tanks, demineralized water storage tank, and primary water storage tank). Provisions are in place (hose connections) to draw water from these sources via a nonsafety-related, portable, diesel-driven pump, which will.supply via hose directly to the basin. Additional makeup can also be provided directly to the wet cooling tower basins using the portable pump and a .fire hose from the potable water supply through a fire hydrant. However, because these sources of water may not be available after a tornado, this function is not an intended function for the systems that include these 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-56 Waterford Steam Electric Station, Unit 3 * / , License Renewal Application
Technical Information sources. In the event these sources are not available, provisions are in place to use the portable, diesel-driven pump to supply water from the Mississippi River to the circulating water system, which has piping that can be used to gravity feed makeup to the basin. The function of providing makeup water to the wet cooling tower basin is an intended function of the circulating water system. The system includes lines from the ACC pump discharge to the suction lines of the emergency feedwater system, These lines provide a source of water to the EFW pumps if the condensate storage pool is depleted during an accident. The system also includes jockey pumps, which operate when the ACC pump is idle to keep the piping upstream of the component cooling water heat exchanger outlet temperature control valve full of water and pressurized during normal operations. Each basin is provided with an independent, nonsafety-related filtration and chemical addition system to maintain water purity and pH. This .system consists of a pump, filter, and chemical feed tank. The ACC system has the following intended functions for_ 10 CFR 54.4(a)(1).
In conjunction with the component cooling system, the ACC system dissipates the heat removed from the reactor and its auxiliaries during normal unit operation, during refueling, or after a design basis accident. '
Provide a source of water to the suction of the EFW pumps if the condensate storage pool is The ACC system has no intended function for 10 CFR 54.4(a)(2). The ACC system has the following intended function for *10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire (1 O CFR 50.48). Circulating Water The purpose of the circulating water (CW) system is to provide cooling water to the main. condenser to condense steam from the main turbine, the feedwater turbines, and other condensate drain sources. The CW system also provides cooling to the reactor coolant system by cool_ing steam dumped to the condenser through the bypass valves during plant startup and shutdown. The CW system also provides cooling to the turbine closed cooling water system heat exchangers and the.steam generator blowdown heat exchangers. The blowdown system, boron management system, liquic:I waste management system, auxiliary component cooling water system, component cooling water makeup pumps, and dry cooling tower sumps discharge through the CW system. 2.0 Scoping and Screening Methodology for Identifying Structures and Componer:its Subject to Aging Management Review and Implementation Results Page 2.3-57 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information The CW system code includes the four circulating water p*umps, the river water supply' pump, * *circulating air evacuation pumps, vacuum breakers, piping, valves, expansion joints, instrumentation and controls. Each circulating water pump takes suction from two bays at the intake structure and discharges the water into a common distribution block from which two pipes direct thewater to the condenser. Warm water from the condenser and water from auxiliary systems returns to a common distribution block and then to the discharge structure. The CW system is credited to provide emergency makeup to wet cooling towers A B following a tornado. A portable diesel-driven pump provides water from the Mississippi River to the CW system, which can then gravity feed makeup to the basin through underground piping. The CW system* has no intended functions for 10 CFR 54.4(a)(1 ). The CW system has the following intended functions for 1 O CFR 54.4(a)(2).
Provide. a source of makeup to the wet cooling tower basins following a tornado. . ., .
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The CW systern has no intended functions for 1 O CFR 54.4(a)(3). Control Element Drive Mechanism. Cooling The purpose of the control element drive mechanism cooling (CDC) system is to coo.I the magnetic jack coils of the CEDM during normal operation. The system has no safety function. The CDC system consists of four exhaust fans, four inlet dampers, water cooling coils, and associated ductwork. Two of the four fans operate to maintain a negative pressure inside the cooling shroud for the magnetic jack coil elements. The other two fans serve as standby units. Containment air is drawn _through the cooling shroud, removing heat from the CEDl\'1 magnetic jack coil. The air is drawn through the water cooling coils where the heat is rejected to the*
component cooling water system. Cooled air is then discharged to the. containment atmosphere via the system exhaust fans. The nonsafety-related cooling coils provide a pressure boundary function for the component cooling water system. The CDC system has no intended functions for 10 CFR 54.4(a)(1). The CDC system has the following intended function for 10 CFR 54.4(a)(2).
Support the component cooling water system pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Page 2.3-58 Subject to Aging Management Review and Implementation Results* .

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The CDC system has no intended functions for 10 CFR 54.4(a)(3). FSAR References Section 9.2.2 Sectiori 9.2.5 Section 9.4.5.7 Section 10.4.5 Components Subject to Aging Management Review CC system components that maintain the pressure boundary of the system from instrument air accumulators to the valve operators are reviewed in Section 2.3.3.4, Compressed Air. An isolation valve for the dry cooling tower (OCT) sumps discharge to the CW system is reviewed in Section 2.3.3.14, Plant Drains. Nonsafety-related components of the CC and CW systems not .included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining CC/ACC/CW/CDC system components are reviewed as listed below.

Table 2.3.3-3 lists the component types that require aging management review. Table 3.3.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 158 sh 1 (ACC) LRA*G158 sh.2 (ACC) 160 sh 1 (CC) LRA-G160 sh 2 (CC/ACC) LRA-G160 sh 3 (CC) LRA-G160 sh 4 (CC) LRA-G160 sh 5 (CC/ACC) LRA-G160 sh 6 (CC/ACC) LRA-G164 sh 5 (ACC) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-59 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-3 Component Cooling and Auxiliary Component Cooling Water Systems Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Coil Pressure boundary
Expansion joint Pressure boundary Fan housing boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary. Heat exchanger (fins) Heat transfer Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary
Heat exchanger (tubes) . Heat transfer Pressure boundary Nozzle Pressure boundary Orifice Flow control * -Pressure boundary Piping Pressure boundar)i Pump casing Pressure boundary Sight glass Press-ure boundary Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components SubjeQt to Aging Management Review and Implementation Results , Page 2.3-60 2.3.3.4 Compressed Air System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Tec:hnical Information The purpose of the compressed air system is to provide a reliable supply of dry, oil-free air for pneumatic instruments and controls, pneumatically operated valves and the necessary service air for normal plant operation arid maintenance. The compressed air system is comprised of components from system codes IA (instrument air system) and SA (service air system). This review also includes the emergency breathing air system and compressed air components supporting the containment building. The compressed air system consists of two instrument air compressors, one instrument air receiver, two instrument air dryers with pre-and after-filters, three station air compressors, one station air receiver, piping, valves and instrumentation. Each instrument air and station air compressor package consists of an inlet filter, compressor, moisture. separator, heat exchanger and discharge filter. Air from either the instrument air compressor or station air compressor packages is discharged into the corresponding air receiver by a common header. Air from the instrument air receiver is passed through one of the instrument air dryers and filters assemblies. The compressed air system then divides into various branches. Instrument air lines supply air to the demineralizer plant, yard area, turbine building, reactor auxiliary building, reactor building, fuel handling building, service building, and intake structure. In the turbine, reactor auxiliary and reactor buildings, these branches are divided into several sub-branches. located at various elevations. The various air valves, pneumatic instruments and controls are supplied from lines. Downstream of the station air receiver, the system is divided into various branches. Service air lines supply air to the demineralizer plant, yard area, turbine building, reactor auxiliary building; reactor building, service building, hot machine shop and decontamination room, fuel handling building and intake structure. These branches are divided into several sub-branches in all of these buildings and are located at various elevations. Service air is used for the operation of pneumatic tools, equipment used for plant maintenance, and. for occasional air lancing of the wet cooling tower basin water to control microbiological growth. *
Most components of the system serve no safety function since they are not required to achieve safe shutdown or to mitigate the consequences of an accident. Air or nitrogen accumulators are provided as backup to the normal instrument air for valves required for operation during the safe shutdown of the plant following an accident or to mitigate the consequences of an accident. Nitrogen accumulators are reviewed with the nitrogen system (Section 2.3.3.11 ). The air accumulators and associated ,components supporting safety-related air operated valves are safety-related. This includes the essential instrument air system of backup accumulators provided for post-accident operation of certain containment isolation valves during a loss of instrument air. Where nitrogen accumulators provide backup for safety-related valve operation, 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-61 \ I Waterford steam Electric station, Unit 3 License Renewal Application Technical Information the compressed air system components at the interface with the nitrogen system support the nitrogen pressure boundary and are also safety-related. Where compressed air system lines enter containment, components of the system support the containment pressure boundary and are safety-related. The safety-related nitrogen accumulators are capable of providing motive air to pneumatically operated valves for 10 hours. Procedures are established for operating manual handwheel overrides or, for two accumulators, lining up backup air supplies for continued function after 10 hours. This backup air supply consists of air bottle stations that may be manually aligned to re-pressurize two accumulators following a design basis event concurrent with a loss of instrument air. These two accumulators enable control room operators to realign essential chiller cooling water valves from the wet cooling to the dry cooling towers to preserve wet cooling tower basin water inventory. * ' -The compressed air system has the following intended functions for 10 CFR 54.4(a)(1).
Provide a reserve supply of compressed air (via accumulators, backup air bottles, and related comporients) to support safety functions of air operated valves for safe shutdown . *and accident mitigation. *
Support containment pressure boundary. The_compressed air system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The compressed air system has the following intended functions for 10 CFR 54.4(a)(3). *
Perform a function (nitrogen pressure boundary) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (nitrogen-pressure boundary) that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). Emergencv Breathing Air The purpose of the emergency breathing air (EBA) system is to provide high quality breathing air for people in the control room envelope to ensure control room habitability during a fire and certain toxic gas events. The system includes an air compressor, purifier filters, four pressure air storage tanks, pressure regulators, and piping and valves for distribution to seven 2.0 Scoping and Screening Methodology for Identifying Stn,ictures and Components Subject to Aging Management Review and Implementation Results Page 2.3-62 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information manifolds around the control room envelope. Each manifold has filters, a pressure regulator, *an isolation valve, and quick discor:inect connections for up to four breathing hoses. The EBA system has no intended functions for 10 CFR 54.4(a)(1 ). The. EBA system has the following intended function for 1 O CFR 54.4(a)(2).
Provide stored, compressed air to the control room during a toxic gas release.
The EBA system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance.with the Commission.'s regulations for fire protection (10 CFR 50.48). Containment Building The primary containment and shield building are evaluated as structures, .but CB (for: . containment building) is used as a system code and includes several mechanical The purpose of the CB system mechanical components is to support the containment pressure boundary. The mechanical components include accumulators, filters, piping, and valves that support the operation and testing of seals for the maintenance hatch, the containment personnel lock, and containment escape lock. The CB system has the following intended function for 10 CFR 54.4(a)(1).
Support containment pressure boundary. The CB system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety.,.related components could prevent satisfactory accomplishment of,a safety
function. The CB system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References Section 6.3.3.5 (essential instrument air) Section (EBA) Section 6.5.3.1 Section 9.3.1 Section 9.3.9.2.1 (backup air supply) Section 9.5.1.3.1 [0.4(h)] (EBA) 2.0 Sc;oping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-63 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Instrument air system components that support the nitrogen system pressure boundary are reviewed in Section 2.3.3.11, Nitrogen. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining compressed air systems components are reviewed as listed below.
Table 2.3.3-4 lists the component types that require aging management review. Table 3.3.2-4 provides the results of the aging management review. License Renewal Drawings Adqitional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 152 sh 4 (IA) LRA-G 152 sh 6 (IA) LRA-G 1 !52 sh 9 (IA) LRA-5817-7912 (EBA) LRA-G 157 (SA) LRA-G 164 sh 2 (EBA) LRA-G 166 sh 2 (IA) LRA-B430 _M 116 (EBA) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-64 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-4 Compressed Air Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Filter housing Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Regulator body Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-65 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.5 Containment Cooling HVAC System Description The purpose of the containment cooling HVAC system (CCS) is to remove heat from the containment atmosphere, thus maintaining the containment pressure and temperature at acceptably low levels. During normal plant operations, the CCS operates continuously to maintain the pressure, temperature, and humidity. Following an accident, the CCS, in conjunction with the containment spray (CS) system, removes heat to maintain the containment pressure and temperature within design limits and limits offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CCS consists of four fan coolers that draw air from the containment and discharge it to a ring header around the top of containment. The fan cooler units consist of a vane axial fan and two banks of cooling coils supplied by the component cooling water system. The four fan cooler units are divided into two systems of two units each. During normal operation, the CCS draws containment air through the water cooling coils with the axial flow fan and discharges through a back draft damper to a duct riser. Each duct riser is common to *a pair of fan coolers and terminates with the cooled air being discharged into the ring header. From the ring header separate ducts feed cooled air to different parts of the containment. The CCS has the following intended function for 10 CFR 54.4(a)(1).
Remove heat to maintain the containment pressure and temperature within design limits and limit offsite radiation levels by reducing the driving force for fission product leakage from the containment atmosphere to the external environment. The CCS has no intended function for 10 CFR 54.4(a)(2). The CCS has the following intended function for 1 O CFR 54.4(a)(3}.
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 6.2.2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-66 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review CCS components are reviewed as listed below. Table 2.3.3-5 lists the component types that require aging management review. Table 3.3.2-5 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the. following license renewal drawings. LRA-G853 sh 1 LRA-G 160 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-67 --___ ./

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-5 Containment Cooling HVAC System Components Subject to Aging Management Review Component Type Intended Function . Bolting. Pressure boundary Cooler housing Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Fan housing Pressure boundary Flex connection Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Piping Pressure boundary -* Thermowell* Pressure boundary Tubing Pressure boundary . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management *Review arid lmplem_entation Results Page 2.3-68 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.6 Control Room HVAC System Description The purpose of the control room heating, ventilation, and air conditioning (HVC) system is to maintain the control room envelope in a habitable condition. The HVC system is designed to establish and maintain a habitable atmosphere in the event of a toxic chemical accident or a design basis accident with its resulting radioactive environment. The control room envelope includes the control room, computer room, computer room supplementary air conditioning equipment room, HVC equipment room, emergency living quarters, emergency storage room, toilets, locker rooms, kitchen, kitchenette; supervisor's office, corridors, conference room, and vault. Control room habitability systems are required to assure that the operators can remain in the control room to operate the plant safely under normal conditions and maintain the unit in a safe condition under accident conditions. The system consists of two full-capacity redundant air handling units (AH Us), two full-capacity toilet exhaust fans, a kitchen and conference room exhaust fan, two full-capacity redundant control room emergency filtration units, redundant isolation valves for the two emergency intakes, the normal intake, and the two separate exhausts. Other HVC equipment includes individual area dampers, heaters, and redundant equipment room AHUs. The redundant air conditioning units are served by redundant loops of the essential services chilled water system. The system maintains a slight positive pressure relative to the outside atmosphere within the envelope during normal operations to prevent any outside air from bypassing the safety-related monitoring instrumentation located in the air intake path. A variety of purging operations may be conducted through various dampers and exhaust flow paths. These purging operations may be performed to remove smoke. The north and south emergency air intakes provide two sources of control room fresh air during radiological accident conditions. The HVC system has three distinct and different operating modes and associated flow paths. The operating modes are the normal operating mode, safety injection actuation signal or high radiation mode, and toxic gas (e.g., chlorine or ammonia) mode. Three smoke purge flow paths can be enabled to remove smoke from the control room and computer room. These flow paths are normally automatically aligned but may be manually aligned. The HVC system has the following intended functions for 10 CFR 54.4(a)(1).

Remove heat from the control room following an accident.
Provide filtered outside air following an accident to maintain a positive pressure in the control room. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-69 ,,,..-

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information

Maintain the control room air quality within *limits following an accident. The HVC system has no intended functions for 1 O CFR 54A(a)(2). The HVC system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). FSAR References Section 6.4
Section 9.4.1 Components Subject to Aging Management Review HVC ,system components reviewed as li_sted below. Table 2.3.3-6 lists the component types that require aging management review. Table 3.3.2-6 provides the results of the aging management review: License Renewal Drawings Addi.tional details for subject to aging 'Tlanagement review are provided in the following license renewal drawings .. LRA-G853 sh 20 LRA-G853 sh 22 LRA-G853 sh 23 LRA-G853 sh 11 LRA-G853 sh 21 LRA-G853 sh 4 LRA-G853 sh 5 2.0 Scoping and Screening Methodology for Identifying Structures and Components* Subject to Aging Management Review and Implementation Results Page 2.3-70 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-6 Control Room HVAC System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary -Fan housing Pressure boundary Filter housing Pressure boundary Flex connection Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Piping Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Reyiew and lmplemel)tation Results . Page 2.3-71 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
2.3.3. 7 Emergency Diesel Generator System* Description The purpose of the emergency diesel generator (EOG) system is to provide an emergency source of AC power to safety buses during a loss of the preferred (offsite) and standby (onsite) AC power supplies to permit the engineered safety features systems to perform their safety functions. The system includes two independent diesel generators, each with independent support systems. The diesel engines, generators, instrumentation and controls are included in system code EG (emergency generator system). The diesel support systems include components in system codes EGA (emergency diesel generator air system), EGC (emergency diesel cooling system), EGF (emergency diesel fuel system) and EGL diesel lube oil system). The EOG air system includes starting air, control and shutdown air, and the combustion air intake and exhaust. Each diesel has two identical, redundant, skid-mounted air start systems, each consisting of an air compressor, an air receiver with two air accumulation pipes (which provide air storage capacity), an air dryer, filters, and associated valves, piping, and instrumentation. The
engine is started by injecting compressed air directly into the engine cylinders in sequence. The air start system also provides air to the pneumatically operated diesel control components and the shutdown air header. A turbocharger draws outside air for diesel combustion through a filter, silencer, and shutdown valve and supplies it at positive pressure to the diesel intake manifolds via intercooler/heaters. The driving force for the turbocharger is the exhaust gases from the diesel exhaust manifold. Diesel exhaust is directed through the turbocharger turbine and an exhaust silencer to the atmosphere.
A portable Isuzu diesel-driven air compressor is available for use during a station blackout or other times when the air receivers are depleted and cannot be repressurized by normal methods. The removable flexible hose is connected to either air. receiver drain valve. The EOG cooling system consists of an engine-driven main jacket water pump, motor-driven circulating jacket water pump, water cooler cooled by component cooling water, standby jacket water heater, standpipe (surge tank), and associated piping, valves, and instrumentation. Jacket water loads include the two inlet headers for cylinder cooling, the diesel speed governor oil cooler, the turbocharger casing, and the combustion air heaters. The EOG fuel system consists of a crankshaft-driven primary fuel oil booster pump, direct-current (DC) motor-driven standby fuel oil booster pump, fuel oil cooler, fuel oil feed tank, filters, strainers, fuel oil storage tank, fuel oil transfer pump, fuel injection pumps, and associated piping, valves, and instrumentation. 2.0 Seeping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-72 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The EOG lube oil system consists of an engine-driven main lube oil pump, motor-driven standby lube oil pump, motor-driven pre-lube pump, oil coolers cooled by the component cooling water system, strainers, filters, standby lube oil heater, crankcase oil sump, maintenance lube oil storage tank, and associated piping, valves, and The EOG system has the following intended function for 10 CFR 54.4(a)(1).
Provide an emergency source of AC power to safety buses during a loss of the preferred (offsite) and standby (onsite) AC power supplies to permit the engineered safety features systems to perform their safety functions. The EOG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components. could prevent satisfactory accomplishment of a safety function. The EOG system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a fun.ction (portable air compressor) that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 8.3.1.1.1 Section 9.5.4 Section 9.5.5 Section 9.5.6 Section 9.5. 7 Section 9.5.8 Components Subject to Aging Management Review Nonsafety-related components* of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3: 15,
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining EOG system components are reviewed as listed below. Table 2.3.3-7 lists the component types th.at require aging management review .. Table 3.3.2-7 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-73 License Renewal Drawings Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 164 sh 1 LRA-1564-2044 LRA-G 164 sh 2 LRA-5817-9519 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-7 Emergency Diesel Generator System Components Subject to Aging Management Review Component Type Intended Function Blower Pressure boundary Bolting Pressure boundary Expansion joint Pressure boundary Filter housing Pressure boundary Flame arrestor Pressure boundary Flow element Pressure boundary Heat exchanger (channel head) Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Level indicator Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Silencer Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tank Pressure boundary Thermowell Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-75 Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical_ Information Table 2.3.3-7 (Continued) Emergency Diesel Generator-System Components Subject to Aging Management Review Component Type Intended Function Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-76 2.3.3.8 Fire Protection: Water System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical *Information The review of the fire protection: water system includes components from the fire protection system, the diesel fuel oil system, anp the treated water system. Fire Protection The purpose of the fire protection system is to ensure the capability to safely shutdown the
reactor, maintain it in a safe shutdown condition, continue to control radioactive releases to the environment, and to prevent personnel injury and property damage in the event of a fire. The fire protection system includes components in system codes FP (fire protection system) and OFP (outside fire protection). Fire protection within the protected area is provided by components in the FP system code. The FP system stores water for the control and suppression of anticipated fires and distributes the water through a network of underground mains and distribution piping to the sprinklers and hose stations. The FP system consists of two storage tanks, three fire pumps; ajockey pump, and the associated piping and valves to supply water to sprinklers, standpipes and hydrants. The diesel fuel oil tanks and other diesel support equipment are included in the DFO (diesel fuel oil) system code.
The three fire pumps, one motor driven and two diesel driven, can take suction from either or both of the storage tanks. The jockey pump maintains fire main pressure. The firewater-pumps discharge into the distribution system. The water distribution system consists of underground yard piping serving all plant yard fire hydrants, sprinkler systems, water spray systems, and interipr standpipe systems. The underground piping forms a complete fire loop around the plant. The main fire loop supplies two other fire loops: the reactor auxiliary building *. which in turn supplies the containment building, and the turbine building. If available following a tornado, inventory from the fire water storage tanks may be used to replenish the wet cooling tower basin; however, because these tanks are not protected from tornado missiles, this is not an intended function for the tanks. The credited source is the Mississippi River through the circulating water system. The fire protection system also includes a separate fire suppression system, with a storage tank, pumps, piping, valves, sprinklers, hydrants, and hose houses. This separate system, which includes components of system codes OFP and FP, provides fire protection for selected buildings outside the protected area. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-77 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The fire protection system includes fire dampers that are either installed in ductwork or mounted in walls. Fire dampers mounted in walls are included in the evaluation of structural commodities. Where necessary to support a license renewal intended function, fire dampers installed in ductWork are included in the evaluation of the related HVAC *system. Waterford 3 does not use a Halon fire suppression system or a carbon dioxide suppression ,system. The fire protection system h*as the following intended function for 1 O CFR 54.4(a)(1 ).
Support containment pressure boundary. The fire protection system has no intended functions for 10 CFR 54.4(a)(2). The fire protection system has the following intended function for _10 CFR 54.4(a)(3). * . Perform a function that demonstrates compliance with the Commissiqn's regulations for fire.protection (10 CFR 50.48). Diesel Fuel Oil The purpose of the diesel fuel oil (DFO) system is to provide a supply of fuel oil for the operation of the two diesel-driven fire pumps and the auxiliary diesel generator (also referred to as the security diesel generator). The system includes tanks, piping, valves, instruments, and controls to support operation of the diesels. The auxiliary diesel generator supports lighting requirements for'a station blackout.
The DFO system does not support operation of the emergency diesel generators or the auxiliary boiler, which have separate fuel oil systems (EGF and ABF respectively). The DFO system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The DFO system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Treated Water The purpose of the treated water system is to provide a water source for the fire water storage tank, demineralized water system, and sealing and cooling water for various pumps. The treated water system includes components from the system codes TW (treated water system) and BO (BOZE system, the primary water treatment package). The treated water system is no longer used for processing raw water from the Mississippi River. The treated water system has been inactivated except for the clearwell tank, clearwell transfer pumps, bearing lubrication water pumps for the circulating water pumps, and associated piping, valves, instrumentation, and controls. Certain components (piping and valve bodies) in the treated water system support the pressure boundary of the fire protection system. Some of these components are also in the flow path for the potable water supply to the wet cooling tower basin. However, because the availability of the potable water supply to the site is not assured following a tornado, this is not an intended function for the TW system. The credited source is the Mississippi River through the circulating water system using the portable pump. No components of the treated water system are located where physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The treated water system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The treated water system has the following intended function for 10 CFR 54.4(a)(3).
Support the fire protection system pressure boundary. FSAR References Section 9.5.1 Section 9.2.3 (treated water, referred to primary water treatment plant) Components Subject to Aging Management Review FP system dampers installed in ductwork that are necessary to support a license renewal intended function are.reviewed in Section 2.3.3.12, Miscellaneous HVAC, and Section 2.3.3.6, Control Room HVAC. Components in the DFO system that support operation of the auxiliary diesel generator are reviewed in Section 2.3.3.13, Auxiliary Diesel Generator. Remaining components are reviewed as listed below. *
Table 2.3.3-8 lists the component types that req1,1ire aging management review. Table 3.3.2-8 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-79 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G161 sh 1 LRA-G161 sh 5 LRA-G 164 sh 3 LRA-G161 sh 3 LRA-G161 sh 6 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-80 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-8 Fire Protection: Water System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Expansion joint . Pressure boundary Flame arrestor Pressure boundary Flex hose Pressure boundary Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Hydrant Pres_sure boundary Piping Pressure boundary Pump casing Pressure boundary Silencer Pressure boundary Sprinkler Flow control Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tank Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary Vortex breaker Flow control 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-81 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information 2.3.3.9 Reactor Coolant Pump Oil Collection System Description . The purpose of the reactor coolant pump (RCP) oil collection system is to ensure that failure of the oil collection system does not lead to fire during normal operations or design basis accident conditions. The oil collection system consists of enclosures which encompass all externally located oil bearing components such that potential oil leakage from components will be contained and drained to an oil collection tank in a safe location. RCP oil collection components use the RC system code.
An RCP oil collection system is provided for each pump to direct lube oil to a collection tank from pressurized and unpressurized leakage sites, such as lift pump and piping, overflow lines, lube qil cooler, oil fill and drain lines and plugs, flanged connection in oil lines, and lube oil reservoirs. A gravity drain piping system transports any accumulated oil from ttie drip pan enclosures to oil collection tanks. There are two 200-gallon oil collection tanks. The tanks are located inside the reactor containment building outside the biological shield wall. Each tank is vented and provided with a flame arrester and a glass liquid level gauge to provide local indication of the existence of oil in the tank. Each tank is. capable of collecting oil from one RCP oil lube system(195 gallons). The RCP oil collection system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The RCP .oil collection system has the following intended function 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). FSAR References Section 9.5.1.1.3 Section 9.5.1.2.6 Components Subject to Aging Management Review RCP oil collection system components are reviewed as listed below. Table 2.3.3-9 lists the component types that require aging management review. Table 3.3.2-9 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-82 License Renewal Drawings Waterford Steam Electric Station, Unit 3 -License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G 164 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-83 Waterford Steam Electric Station, Uriit 3 License Renewal Application Technical Information 2.3.3-9 RCP Oil Collection System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Drip pan Pressure boundary Enclosure Pressure boundary Flame arrestor Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer Filtration Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-84 2.3.3.10 Fuel Pool Cooling and Purification System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the fuel pool cooling and purification (FS) system is to provide cooling and purification equipment to maintain spent fuel pool temperature, purity, and clarity within design requirements. The FS system consists of a cooling loop and a purification loop. These loops are independent and provide flow paths for transfer, purification, and draining of the refueling cavity, refueling canal, spent fuel cask decontamination area, spent fuel pool, and the refueling water storage pool. The cooling portion is a closed loop system comprised of two half-capacity pumps and one capacity heat exchanger cooled by the component cooling water system. A backup spent fuel pool heat exchanger is also available when the spent fuel pool heat exchanger is out of service. The fuel pool water is drawn from the fuel pool near the surface through a strainer and is circulated by the fuel pool pumps through the fuel pool heat exchanger. From the outlet of the fuel pool heat exchanger (or backup fuel pool heat exchanger), the cooled fuel pool water is returned to the fuel pool. The purification loop consists of the fuel pool purification pump, filter, ion exchanger, and strainers. Clarity and purity of the spent fuel pool, refueling cavity, and refueling water storage pool are maintained by these components. The purification flow is drawn from the spent fuel pool through a strainer and circulated by the pump through a filter which removes particulates, then through an ion exchanger to remove ionic material, and finally through a strainer that prevents resin beads from entering the fuel pool. The refueling cavity and refueling water storage pool also have connections to the purification loop. The connection to the refueling water storage pool through the purification loop also may be used to provide makeup to the fuel pool. This provides a backup makeup supply to the spent fuel pool
that has a seismic Category I makeup water source, the refueling water storage pool. The FS system includes two nonsafety-related valves associated with the spent fuel cask decontamination pit that are credited as flood boundaries for the design basis flood. The FS system includes four nonsafety-related valves that provide drainage of containment spray fluid from the refueling cavity post-LOCA. The spent fuel storage racks are free standing and go wall-to-wall in the spent fuel pool and spent fuel cask storage area. The spent fuel storage racks are grouped into two design styles, designated as Region 1 and Region 2. Both rack styles contain Baral as the active neutron absorbing poison. The neutron absorbers and storage racks are subject to aging management review and are included in this review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-85 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The FS system has the following intended functions for 10 CFR 54.4(a)(1).
Remove decay heat from spent fuel assemblies.
Support containment pressure boundary.
Provide neutron absorption in the spent fuel.pool. .
Provide structural support of fuel assemblies in the spent fuel pool. The FS system has the following intended functions for 10 CFR 54.4(a)(2).
Provide a backup makeup water supply to the spent fuel pool from a seismic Category I source.
Provide for containment spray fluid drainage from the refueling cavity post-LOCA.
Provide flood barrier for design basis flood.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The FS system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References Sections 9.1.2, 9.1.3 (referred to as fuel pool system or spent fuel pool cooling and cleanup system) Components Subject to Aging Management_ Review* The refueling cavity drainage portion of the FS system is reviewed in Section 2.3.3.14, Plant Drains. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed *in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining system components are reviewed as listed below. Table 2.3.3-10 lists the component types that require aging management review. Table 3.3.2-10 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-86 License Renewal Drawings Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 160 sh 1 LRA-G163 LRA-G 160 sh 4 LRA-G169 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-87 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-1 O Fuel Pool Cooling and Purification System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Heatexchanger(channel head) Pressure boundary Heat exchanger (shell) Pressure boundarY Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Neutron absorber Neutron absorption " Piping Pressure boundary Pump* casing Pressure boundary Rack Support for Criterion (a)(1) equipment Thermowell Pressure boundary Tubing Pressure boundary Valve body . Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-88 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.11 Nitrogen System Description The purpose of the nitrogen (NG) system is to provide nitrogen gas for normal plant operation and maintenance and for charging nitrogen accumulators associated with safety-related components.
The nitrogen system has a completely automated storage and supply network with resupply coming from a vendor tanker/trailer. The* system withdraws liquid. nitrogen from a* storage tank via one of two positive displacement pumps. The liquid nitrogen is converted into a gas by a vaporizer unit and is stored in three high pressure storage cylinders connected to the supply header. From the supply header, nitrogen is delivered directly to the main steam isolation valve (MSIV) nitrogen charging connections located just below the MSIV actuators and to a pressure control manifold. The pressure control manifold then reduces the nitrogen pressure for distribution to various plant loads.
Nitrogen is distributed to the reactor auxiliary building, reactor containment building, and turbine generator building. Nitrogen.pressure is reduced as needed to meet load requirements. The following major loads are supplied by the nitrogen system:
Safety injection tanks
Reactor drain tank and quench tank
Accumulators used as backup air sources for safety-related air operated valves
Gas surge tank, gas decay tanks, and equipment drain tank_
Volume control tank
Boron management flash tank and holdup tanks
Demineralized water storage tank, primary water storage tank
Condensate storage tank
Steam generators for blanketing and purging Safety-related relief valve NG-1523 is installed to protect safety-related nitrogen accumulators and a containment penetration from over-pressurization should nonsafety-related pressure reducing valves and nonsafety-related pressure relief valves fail to function properly. Two valves in the NG system support the main steam pressure boundary. This nitrogen flow path provides a nitrogen blanket to the steam generators during outages. Valve NG-432 supplies nitrogen to the holdup tanks in the boron management system and is. classified as Safety Class 3. However,-since the holdup tanks do not perform a safety function, NG-432 does not perform a safety function in accordance with 10 CFR 54.4(a)(1 ). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page ?*3-89 i .:

( Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The NG system has the following intended functions for 1 O CFR 54.4(a)(1 ). *

Provide a reserve supply of compressed nitrogen (via accumulators and related components) to support safety functions of air operated valves for safe shutdown and accident mitigation.
Support pressure boundaries of safety-related systems that use nitrogen.
Support containment pressure boundary. The NG system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety
function. The NG system has the following intended functions for 1 O CFR 54.4(a)(3).
Perform a function (accumulators for air operated valves) that demonstrates compliance with 'the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (accumulators for air operated valves) that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). FSAR References Section 9.3.9 Components Subject to Aging Management Review NG system components that support SI system intended functions are reviewed in Section 2.3.2.2, Safety Injection. Two valves supporting the main steam pressure boundary are reviewed in Section 2.3.4.4, Main Steam. Safety-related valve NG-1523 does not require aging management review because the valve fails to its desired position (pressure boundary integrity is not required). Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining NG system components are reviewed as listed below. Table 2.3.3-11 lists the component types that require aging management review. Table 3.3.2-11 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-90 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for components subject to aging management review are provided in the following license renewal drawings.
LRA-G 166 sh 1 LRA-G 166 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-91 Table 2.3.3-11 Nitrogen System Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Flex hose Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Regulator body Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results * ' Page 2.3-92 2.3.3.12 Miscellaneous HVAC System Description Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information This review includes the following site HVAC systems with intende.d functions for license renewal.
Cable vault and switchgear ventilation
Containment atmosphere release
Fuel handling building HVAC
Reactor auxiliary building HVAC
Shield building ventilation
Turbine building HVAC For other HVAC systems not addressed here, see Section 2.3.3.5, Containment Cooling HVAC, and Section 2.3.3.6, Control Room HVAC. Cable Vault and Switchgear Ventilation The purpose of the cable vault and switchgear ventilation system (SVS) is to maintain a suitable operating environment for electrical equipment and prevent the accumulation of a combustible concentration of hydrogen in the battery rooms during normal and accident conditions. The SVS also provides for smoke purge in the electrical areas in the event of a fire. The cooling part of the SVS is made up of two separate air handling subsystems, each with two full-capacity air handling units consisting of a medium efficiency filter, chilled water cooling coil, and centrifugal fan. Electric heating coils are included in the air handling units of_ one of the air handling subsystems. The remainder of the SVS consists of two full-capacity battery room exhaust fans for each battery room, two exhaust fans for smoke purging, one exhaust fan used during normal operation and smoke purging, and tw.o full-capacity ventilation*fans. The SVS has the following intended functions for 10 CFR 54.4(a)(1).
Maintain a suitable operating environment for electrical equipment during accident conditions.
Prevent the accumulation of a combustible concentration of hydrogen in the battery rooms during accident conditions. I, The SVS has no intended functions for 10 CFR 54.4(a)(2). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-93

\ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SVS has the following intended function for 1 O CFR 54.4(a)(3).

Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Containment Atmosphere Release The purpose of the containment atmosphere release (CAR) system is to purge containment at low containment atmosphere pressure. As described in FSAR Section 6.2.5, the CAR system is part of the combustible gas control system, which consists of three systems: the CAR system, a hydrogen analyzer system, and a hydrogen recombiner system (see description* of the hydrogen analyzer and recc:imbiners in Section 2.3.2.3, Containment Penetrations).
The CAR system serves as a long-term post-accident'clean up system. When post-LOCA containment pressure has reduced sufficiently, the CAR system transfers gases from inside containment to the reactor building annulus. CAR system operation following a design basis accident allows fission products to be released to the shield building annulus for fission-product removal by the shield building ventilation system. When containment pressures have been
reduced to* approximately atmospheric, the CAR system can be started to purge containment The CAR system consists of two full-capacity exhaust trains and two full-capacity supply trains. Each supply train draws air from the reactor auxili.ary building and discharges to the contain merit. Each exhaust train draws a controlled amount of air from the containment and discharges into the shield building ventilation system recirculation ducting leading to the shield building annulus. The system includes containment isolation valves. The CAR system has the following intended functions for 10 CFR 54.4(a)(1).
Support post-accident fission product transport to the shield building annulus for removal by the shield building ventilation system.
Support containment pressure boundary. The CAR system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The CAR system has no intended functions for 1 O CFR 54.4(a)(3). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation-Results Page 2.3-94 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Fuel Handling Building HVAC The purpose of the fuel handling building HVAC, (HVF) system is to provide a suitable environment for personnel, equipment and controls in the fuel handling building during normal operation. During normal operation, outside air is distributed to the fuel handling building by the normal supply fan and exhausted from the building by the normal exhaust fans. The ducting for the normal flow path is designed to assure that airflow is directed from areas of low potential radioactivity to areas of progressively higher potential radioactivity. Following a fuel handling isolation dampers isolate the areas of the fuel handling building where a fuel handling accident can occur.
Emergency filtration exhaust fans take suction on the spent fuel handling area of the fuel handling building with each fan pulling the air through a heater, a medium efficiency filter, high efficiency particulate air (HEPA) filters, and a charcoal adsorber. The filtered gases are then exhausted to the atmosphere. , The components of the HVF system designed to operate in response to a fuel handling aQcident are classified as safety-related (safety class 3). The fuel handling accident analysis V)las revised for the implementation of the alternate source term. The revised analysis does not credit the HVF filtration system for mitigation of the event. the ventilation isolation function is conservatively included as an intended function for the system. The HVF system has the following intended function for 1 O CFR 54.4(a)(1 ).
Isolate the normal ventilation in the fuel handling area envelope in the event of a fuel. handling accident. The HVF system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The HVF system has no intended functions for 10 CFR 54.4(a)(3). Reactor Auxiliary Building HVAC The reactor auxiliary building {RAB) HVAC (HVR) system consists of the following subsystems:
RAB normal ventilation
RAB miscellaneous HVAC
RAB controlled ventilation area
Emergency diesel ventilation
RAB H&V equipment room ventilation 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-95 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RAB Normal Ventilation System The purpose of the RAB normal ventilation system is to cool and heat parts of the reactor auxiliary building during normal operation. The RAB normal ventilation system includes a ventilation supply and ventilation exhaust system. The ventilation supply system includes filters, heating and cooling coils, two full-capacity fans, dampers, and ducting to distribute outside air throughout the reactor auxiliary building. The ventilation exhaust system includes filters, charcoal adsorbers, dampers, two full-capacity fans, and ducting to exhaust reactor auxiliary building air to the plant stack. The system includes a connection from the containment atmosphere purge system to transfer the purge exhaust to the plant stack. The RAB normal-ventilation system has individual safety-related and nonsafety-related air handling units located inside equipment rooms. The safety-related air handling units,
consisting of a fan section, cooling coil and filters, operate during accident conditions when the equipment in their respective room is operating to maintain an acceptable environment for the equipment. air handling units are located inside the following equipment rooms:
Component cooling water pump rooms A, B and AB
Component cooling water heat exchanger rooms A and B
EFW pump rooms A and B *
Charging pump rooms A, B and AB
Shutdown heat exchanger rooms A and B
Safeguard pump room A and B
HPSI pump room AB These units circulate room air through the filters and cooling coil and discharge the cooled air directly to the room where they are located. The fari coolers do not include any distribution ductwork. The essential chilled water system supplies chill water to the safety-related fan coolers. RAB Miscellaneous HVAC System The purpose of the RAB miscellaneous HVAC system is to maintain a desirable operatin*g environment for equipment and to provide comfort for pers.onnel during normal operations. The RAB miscellaneous HVAC is not required to operate during or after a design basis accident or to assist in the safe shutdown of the reactor. The system consists of dampers, filters, heating and cooling coils, fans and distribution ducting. The system provides ventilation for various administrative areas, the hot machine shop, decontamination area, central alarm station area, and other work and storage areas. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-96 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RAB Controlled Ventilation Area System The purpose of the RAB controlled ventilation area system (CVAS) is to provide high efficiency filtration and iodine adsorption for air exhausted from the controlled ventilation
areas following a design basis accident. The controlled ventilation areas contain equipment such as the shutdown heat exchangers,_ containment spray pumps, the high and.low pressure safety injection pumps, containment penetrations, and post-accident sampling equipment. The CVAS exhausts air from the controlled ventilation area following a LOCA to create and maintain a negative pressure relative to surrounding areas. The system limits the post-accident radiological releases to maintain dose consequences below the guidelines of 1 O CFR 50.67. The CVAS consists of exhaust ducts, isolation valves, inlet and suction valves, filter trains, exhaust fans, gravity and bypass dampers and connecting ductwork to the main exhaust duct wh_ich leads to t.he plant stack. The filter trains consist of a demister, electric heating coil, prefilter, upstream HEPA filter, charcoal adsorber, and downstream HEPA filter. Emergency Diesel Ventilation System The purpose of the EOG ventilatiqn system is to remove the heat associated with diesel operation from the EOG A and B rooms. During normal plant operations, the RAB normal ventilation system maintains temperature in the EOG rooms. The EOG ventilation system remains in standby during normal. operation, starting in conjupction with a diesel start. Each EOG room has its own separate ventilation system consisting of an outside air intake damper, an axial flow exhaust fan, a gravity damper, and an outside air exhaust louver. RAB H& V Equipment Room Ventilation System The purpose of the RAB heating and ventilation °{H&V) equipment room ventilation system is to maintain a suitable operating environment for the equipment located in the H&V equipment room during normal or accident conditions. The RAB H&V equipment room is supplied by two full-capacity air handling units. Each unit includes a filter, heating coil, and centrifugal fan. The fans take suction either from the outside air intake or from the RAB H&V equipment room itself, depending on room temperature. Air is exhausted directly from the RAB H&Vequipment room by two full-capacity exhaust fans discharging through a duct containing a gravity damper. The reactor auxiliary. building HVAC system has the following intended functfons for 1 O CFR 54.4(a)(1 ).
Maintain an acceptable operating environment for safety-related equipment. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-97 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Provide high efficiency filtration and iodine adsorption for all air exhausted from the controlled ventilation areas following a design basis accident. The reactor auxiliary building HVAC system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The reactor auxiliary building HVAC system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (EOG ventilation, RAB H&V ventilation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). ' Shield Building Ventilation The purpose of the shield building ventilation (SBV) system is to control the release and removal of fission products from the shield building annulus atmosphere and to maintain annulus pressure within the assumptions of the radiological analyses following a design basis accident. The SBV system is not normally in operation. During accident conditions, this system maintains a negative pressure in the shield building annulus by mixing shield building in-leakage with the air in the annulus and discharging it through a filter train that includes charcoal and HEPA filters. The system provides holdup and removal of fission products by recirculation and filtration using two full-capacity redundant fan and filter systems which exhaust the annular space and discharge back to the annulus or through the plant stack to the afmosphere as required to
maintain a negative pressure in the annulus. On the suction side of each fan, the air is drawn sequentially through a demister, electric heating coil, prefilters, HEPA filter, charcoal adsorber and HEPA afterfilter. A backdraft damper located on the discharge side of the exhaust fan precludes backflow through the system. Downstream of the backdraft dampers, two flow paths are provided to enable discharge through the plant stack or recirculation through a supply tieader in the annulus.
The SBV system has the following intended functions for 10 CFR 54.4(a)(1).
Control the release and removal of fission products from the shield building annulus atmosphere.
Maintain annulus pressure within the assumptions of the radiolog.ical analyses.
Support containment pressure boundary. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-98 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SBV system has no intended functions for 10 CFR 54.4(a)(2) or (a)(3). Turbine Building HVAC The purpose of the turbine building ventilation (HVT) system is to provide a suitable operating environment for equipment and personnel during *normal operation. The ventilation system, except for the switchgear room described below, is a single-pass type and consists of ventilation air intake louvers and dampers, supply fans, exhaust fans, and exhaust louvers and dampers distributed about the periphery of the building. The turbine building switchgear room is separately ventilateq by two half-capacity air handling units that cool the space with outside _air. Each air handling unit contains a medium efficiency filter arid centrifugal fan. Outside air is mixed with return air at the suction of the air handling units to maintain the temperature in the switchgear room. Heating units are mounted on the wall. A nonsafety-related fan is used to provide ventilation for the turbine generator building (TGB) battery room. The TGB battery chargers are necessary for control power to the off-site power switchgear during a fire event where off-site power is not lost; in this scenario, the exhaust fan is not required. However, in a fire event where off-site power is initially lost and the TGB batteries are supplying the DC loads and discharging, then the TGB battery exhaust fan will be required once off-site power is restored to support removal of hydrogen generated from the TGB batteries during recharging. The HVT system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The HVT system has the following intended function for 10 CFR 54.4(a)(3). * . Perform a function (switchgear room and battery room ventilation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). FSAR References Section 9.4.3.5 (SVS) Section 6.2.5 (CAR) Section 6.2.5.2.3 (CAR) Section 9.4.2 (HVF) Section 9.4.3 (HVR) Section 6.5.1.2.1.2 (HVR) Section 6.2.3 (SBV) Section 6.5.1 (SBV) Section 9.4.4 (HVT) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-99 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Nonsafety-related components of the systems not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining HVAC systems components are reviewed as listed below. Table 2.3.3-12 lists the component types that require aging management review. . . . Table 3.3.2-12 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. Reactor Auxiliary Building HVAC LRA-G853 sh 11 LRA-G853 sh 15 LRA-G853 sh 16 LRA-G853 sh 17 LRA-G853 sh 18 LRA-G853 sh 19 LRA-G853 sh 21 _ Various HVAC (Chilled Water) LRA-G853 sh 4 LRA-G853 sh 5 LRA-G853 sh 9 Cable Vault and Switchgear Ventilation LRA-G853 sh 8 . Containment Atmosphere Release LRA-G853 sh 1
Fuel Handling Building HVAC LRA-G853 sh 2 Shield Building Ventilation LRA-G853 sh 1 Turbine Building HVAC LRA-G853 sh 14 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-100 Waterford Steam Electric Station, Unit 3 License Renewal Application -Technical Information Table 2.3.3-12 Miscellaneous HVAC Systems Components Subject to_Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Fan housing Pressure boundary Filter housing Pressure boundary Flex connection Pressure boundary Flex hose Pressure boundary Heat exchanger (fins) Heat transfer Heat exchanger (housing) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Heater housing Pressure boundary Nozzle Flow control Pressure bouhdary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-101 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.3.13 Auxiliary Diesel Generator System Description This review includes the auxiliary diesel generator (ADG, a component in the site security [SS] system) and a function of the diesel fuel oil system. Site Security
The purpose of the SS system is to provide site access controls, surveillance equipment and communications equipment used to maintain security. at the site. The system includes a diesel generator to assure a continuous source of power for the security equipment, independent of the plant electrical systems. The security diesel generator, also known as the auxiliary diesel generator, is credited for station lighting during a station blackout event. The ADG is a nonsafety-related skid-mounted turbocharged John Deere diesel engine poweririg a generator. The diesel has its own radiator and cooling water subsystem and therefore does not require an external cooling water supply. The diesel is electrically started from battery power. The security diesel has its own fuel tank with a 24-hour supply of fuel, which is adequate for the Waterford 3 four-hour coping analysis for station blackout. The ADG is normally in standby and operated only during testing. The SS system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The SS system ha.s the following intended function for 1 O CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). Diesel Fuel Oil See Section 2.3.3.8, Fire Protection: Water for a description of the DFO system. DFO system components supporting operation of the ADG include a fuel oil tank, piping, valves, instruments, and controls. The DFO system has no intended functions for 10 CFR 54.4(a)(1) or (a)(2). The DFO system has the following intended function for 1 O CFR 54.4(a)(3) related to the ADG.
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-102 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information FSAR References None Components Subject to Aging Management Review SS and DFO system components supporting the ADG are reviewed as listed below. Table 2.3.3-13 lists the component types that require aging management review. Table provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawing. LRA-G 164 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-103 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-13 Auxiliary Diesel Generator System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Expansion joint Pressure boundary Flame arrestor Pressure boundary Piping Pressure boundary Silencer Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-104 Waterford Steam Electric Station, Unit 3 ,,----*. License Renewal Application
Technical Information 2.3.3.14 Plant Drains System Description The review of plant drains includes components from the sump pump system (system codes SP and PME) and the sanitation system (system code SAN). The review also includes components from systems described elsewhere in the application but that support an intended function for plant drains. See "Components Subject to Aging Management Review" below. *Sump Pump The purpose of the sump pump (SP) system is to provide for the drainage of equipment, tanks, and wetted surfaces during normal plant operations as well as anticipated large volume flows associated with abnormal or accident conditions. The review of the SP system also includes components with a PME (portable and miscellaneous) system code .. components of the SP system support both radioactive and non-radioactive drainage systems. The radioactive drainage systems arid non-radioactive drainage systems are isolated from each other. Each area housing safety-related equipment is provided with an independent drainage system and attendant sump to preclude the flooding of such areas from other drainage systems. Water discharged from fire suppression systems is handled by the floor drain systems, but this function is not credited for an internal flooding event and not credited for compliance with Appendix R. Dr.ainage from radiologically controlled areas is routed to the waste management systems. Except as noted below, the equipment and floor drainage systems do not serve any safety function and are classified as nonsafety-related. The sump pump system Jncludes safety-related components in the discharge flow path from the containment sump pumps that form part of the containment pressure boundary. The sump pump system includes components associated with the dry cooling tower (OCT) Each OCT sump is provided with a set of motor-driven sump pumps, normally aligned to discharge to the circulating water system, to protect safety-related equipment in the area. Each cooling tower area is also provided with a portable diesel-driven sump pump and hoses that can be connected during extreme rainfall events to discharge water directly over the NPIS exterior floodwall.
One portable DCT diesel-driven pump and one motor-driven sump pump per DCT sump are credited in the analyses for the probable maximum precipitation (PMP) event to prevent flooding of safety-related equipment in the area. In the analysis for the standard project storm (SPS) with the simultaneous occurrence of the operating basis earthquake (OBE), a single diesel-powered sump pump per OCT sump is adequate to prevent flooding of safety-related equipment. Although piping segments through the NPIS wall are classified as safety-related (non-AS ME, non-seismic), they do not perform a safety function in accordance with 1 O CFR 54.4(a)(1 ). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-105 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Roof drains inside the NPIS are credited with removing water from the roofs of structures containing safety-related components during the PMP event. These nonsafety-related drains perform an intended function that meets the criteria of 10 CFR 54.4(a)(2) of protecting related components during design basis rainfall events. These drains are evaluated as part of the SP system. No credit is taken for floor drains or sump pumps for internal flooding everits such as pipe breaks or fire system discharge; however, as discussed above, the OCT sump pumps are credited in the PMP analysis. For the ECCS equipment sumps, the .section of the sump drainage line from the pump discharge check valve back to the pump protects the compartment from backflow through the drainage system. The SP system has the following intended function fot 10 CFR 54.4(a)(1).
Support containment pressure boundary. The SP system .has the following intended functions for 10 CFR 54.4(a)(2).
Protect safety-related components during design basis rainfall and/or flooding events.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The SP system has no intended functions for 1 O CFR 54A(a)(3). Sanitation The purpose of the sanitation (SAN) system is to collect all sewage originating within the protected area and to transfer it to the municipal sanitary waste system. The system consists of lift stations and associated instrumentation, piping and valves. Sanitary collection facilities are located at several locations within the nuclear plant island structure (NPIS) boundaries to accept sanitary waste. The sanitary. drain piping is vented to atmosphere via roof vents to allow gravity flow drainage through an NPIS wall penetration at elevation +12. 7 ft. MSL. This piping functions as a flood barrier for the design basis floqd.
The SAN system has no intended functions for 10 CFR 54.4(a)(1). The SAN system has the following intended function for 1 O CFR 54.4(a)(2).
Support NPIS flood barrier. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-106 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The SAN system has no intended functions for 1 O CFR 54.4(a)(3). FSAR References . Sump Pump System Section 2.4.2.3.3 (roof drains) Section 2.4.2.3.4 (cooling tower area) Section 3.6A.6.4.2.1 (compartment flooding) Section 9.3.3 Components Subject to Aging Management Review Sanitation System Section 9.2.4 Two condensate makeup and storage system valves (CMU-908, and CMU-909) in the fuel handling building are credited flood barrier valves between the Fuel Cask Decontamination Area, open to the train bay which is not flood protected, and the FHB sump. These valves, which are not depicted on an LRA drawing, are included in this review. The 6-inch refueling cavity drains in the refueling cavity (LRA Drawing LRA-G163) provide for containment spray fluid drainage from the refueling cavity post-LOCA. The drains, components in the fuel pool cooling and purification system, are included in this review. Components in sprinkler drains and in the resin waste management (RWM) system and the solid waste management (SWM) system support the NPIS flood barrier and are included in this review. The RWM and SWM systems are described in Section 2.3.3.15, Auxiliary Systems in *Scope for 1 O CFR 54.4(a)(2). Nonsafety-related components of the SP system not included in other reviews whose failure could prevent satisfactory accomplishment*of safety functions are reviewed in Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2). Remaining plant drains components are reviewed as listed below. Table 2.3.3-14 lists the component types that require aging management review. Table 3.3.2-14 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-107 License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details fbr components subject to aging management review are provided in the following license renewal drawings. LRA-G 173 sh 1 LRA-G 173 sh 2 LRA-G 173 sh 3 LRA-G 170 sh 5 LRA-G 158 sh 2 LRA-G163 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-108 Waterford Steam Electric station, Unit 3 Table 2.3.3-14 Plant Drains License Renewal Application "' Technical Information Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer Filtration Strainer housing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-109 2.3.3.15 Auxiliary Systems in Scope for 1 O CFR 54.4(a)(2) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As discussed in Sections 2.1.1.1 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) interact with safety-related systems in one of two
ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an ss.c. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are not discussed in this section. Phvsical Failures This section summarizes the scoping and screening results for auxiliary systems based on 1 O CFR 54.4(a)(2) because_ of the potential for physical interactipns with safety-related equipment. Physical failures may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At WF3, certain components-and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Safety-Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.1 and 2.1.2.1.2. Physical Impact or Flooding The evaluation of interactions due to physical impact or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the' criterion of 1 O CFR 54.4(a)(2). Where this 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-110 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information criterion affected auxiliary systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Sprav Nonsafety-related system components or nonsafety-related portions of safety-related systems containing water, oil, or steam are considered within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. Auxiliary systems meeting this criterion are within the scope of license renewal per 10 CFR 54.4(a)(2). The following auxiliary systems, described in referenced sections, are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) for physical interactions. System Code System Name Section Describing System AE Air Evacuation Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) ARR Airborne Radioactivity Removal Section 2.3.3.15, Auxiliary Systems in Scope for . 10 CFR 54.4(a)(2) ANP Annulus Negative Pressure Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) AS Auxiliary Steam Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2)* BAM Boric Acid Makeup Section 2.3.3.1, Chemical and Volume Control BM Boron Management Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) eve Chemical and Volume Control Section 2.3.3.1, Chemical and Volume Control CF Chemical Feed Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) CHW, Chilled Water Section 2.3.3.2, Chilled Water RFR,SCH, sec cw Circulating Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water
cc Component Cooling Water Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-111 System Gode IA, SA CAP CAR CB DF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT LWM NG PAS PW PMU PSL System Name -Compressed Air Containment Atmosphere Purge -Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation. Leak Rate Testing Liquid Waste Management Nitrogen .. Post Accident Sampling Potable Water Primary Makeup Primary Sampling 0 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section Describing System Section 2.3.3.4, Compressed Air Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2)
Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.4, Compressed Air Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.7, Emergency Diesel Generator Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.10, Fuel Pool Cooling and Purification Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) -Section 2.3.3.15, Auxiliary Systems in Scope for -10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.11, Nitrogen Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology tor Identifying Structures and Components Page 2.3-112 Subject to Aging_ Management Review and Implementation Results -

System Code System Name ARM, PRM Radiation Monitoring HVR Reactor Auxiliary Building HVAC RCC Reactor Cavity Cooling RWM Resin Waste Management SSL, CTB Secondary Sampling SWM Solid Waste Management SP, PME Sump Pump TC Turbine Building Cooling Water System Descriptions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section Describing System Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.12, Miscellaneous HVAC Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Section 2.3.3.14, Plant Drains Section 2.3.3.15, Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) The following systems within the scope of license renewal based.on the criterion of 10 CFR 54.4(a)(2) are not described elsewhere in the application. Each system has the following intended function.

Maintain integrity of nonsafety-related components such that no physical interaction with safety-related componer:its could prevent satisfactory accomplishment of a .safety function. The systems described below have components that support this intended function. For systems with intended functions that meet additional scoping criteria, the additional intended functions are noted in the descriptions below with a reference to the section where the affected components are evaluated (e.g., Section 2.3.2.3, Containment Penetrations). Air Evacuation The purpose of the air evacuation system (AE) is to remove air from the three condenser shells to create a vacuum in the condenser during plant startup and to maintain the 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-113 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information vacuum by removing non-condensible gases and in-leaking air from the steam space of. the three condenser shells during normal operation. The system has no safety function. The system consists of three full-capacity condenser vacuum pump assemblies. Each assembly consists of one motor driven, rotary, water-seal type, two-stage vacuum pump and seal water system. Ea.ch seal water system includes one centrifugal circulating pump, one heat exchanger, one separator and all necessary piping, valves, instruments and electric devices. , The non-condensible gases and water vapor mixture is drawn directly from each shell of the condenser. The mixture flows through the condenser vacuum pump(s) and then to -the separator, where most of the water vapor is condel}sed, and the non-condensible gases are released to the atmosphere via a discharge silencer. The exhaust is monitored for radioactivity prior to discharge to the atmosphere to provide early detection of a steam generator tube leak; in this event, the discharge can be routed to the reactor auxiliary building HVAC system exhaust. The condensed water normally is returned to the condenser; a backup overflow drain line is routed to the industrial waste sump.
Airborne Radioactivity Removal The purpose of the airborne radioactivity removal (ARR) system is_ to limit the buildup of airborne radioactivity leaKing from the reactor coolant system during normal operation, _ and* reduce airborne radioactivity of containment atmosphere to *permit personnel access inside containment during normal operation, shutdown or refueling. The system is used . for radioactivity removal during normal operation only and serves no function for accident dose reduction. The system consists of two airborne radioactivity removal uriits, each consisting of a medium efficiency filter, HEPA prefilter,* charcoal adsorber, and centrifugal fan. Annulus Negative Pressure The annulus negative pressure (ANP) system is provided to maintain the shield building annulus at a negative pressure during normal operation. This minimizes the leakage of unfiltered air to the outside atmosphere. The system draws from the annulus through a single duct which penetrates the shield building through two isolation valves in series to two full-capacity exhaust fans arranged in parallel. The fans discharge to a single duct to the stack. The fans are stopped and . " the isolation valves are closed on a safety injection actuation signal (SIAS) or a containment isolation actuation signal (CIAS). Apart from support of the secondary containment pressure boundary by the isolation valves, the system has no safety functi_on.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-114 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information In addition to the 10 CFR 54.4(a)(2) function described above, the ANP system has the following intended function for 10 CFR 54.4(a)(1).
_ Support containment pressure boundary. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Gontainment Penetrations. Auxiliary Steam The of the auxiliary steam system (AS) is to distribute low pressure steam to plant auxiliary equipment. The AS system is supplied by either the main steam system or the auxiliary boiler system. The AS system supplies steam to the boric acid concentrator, the boric acid/waste concentrator, and the decontamination facility steamerette. The system includes piping and valves located in the reactor auxiliary building. Boron Management The purpose of the boron management (BM) system is to accept, collect, and process_ radioactive waste from various plant systems for recycle or disposal. The BM system proyides a mechanism for concentrating and recovering dissolved boron from the liquid effluent for reuse in the plant or removal from the site. The BM system includes two concentrators, several tanks and. pumps, filters and ion exchangers, and the associated piping and valves_ required to collect and process radioactive waste fluids from various plant systems for recycle or disposal. -The major influent to the f?M system is from the letdown line in the CVC system and is the result of feed and bleed operations during plant shutdowns, startups, and dilution due to fuel burnup over core life. Other sources into the BM system consist of valve and equipment leak-offs, miscellaneous drains, and relief valve discharges. The reactor drain tank collects these discharges within the containment, while the equipment drain tank and equipment drain s_ump accumulate those from outside the containment. From the of the collection tanks and CVC system, water .is sent to the holdup tanks, where the radioactivity of the liquid is significantly reduced during storage. From the holdup tanks, water is processed through filters and ion exchangers and stored in the boric acid condensate tanks. From there the fluid is either released or reprocessed. The section of the system including the flash tank and flash tank pumps is inactive and isolated from the rest of the system by closed valves. Use of the tank required a continuous feed of nitrogen, which created an excessive amount of gaseous waste to be stored and processed. The three-way valve at the inlet to the flash tank is positioned to bypass the tank and has no supply air or power. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review am;! Implementation Results. -Page 2.3-115 '1 )

Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Portions of the BM system that receive *and store reactor coolant water discharge for decay are classified as safety-related (Safety Class 3). This includes the holdup tanks, reactor drain tank pump, equipment drain tank pump, and associated piping and isolation valves. However, as part of the licensing basis change to use the alternate source term (10 CFR 50.67), the FSAR analyses of the liquid waste system (BM system and waste management system) leak or failure (release to atmosphere) was deleted from FSAR Section 15.7.3.2. This event is no longer required by the Standard Review Plan (NUREG-0800). Therefore, the Safety Class 3 components of the BM system no longer perform a safety function in accordance with 10 CFR 54.4(a)(1).

BM system components that support the containment pressure boundary are related (Safety Class 2). A BM system valve also supports the pressure boundary of tlie refueling water storage pool (RWSP). Other components of the system have no safety function. In addition to the 10 CFR 54.4(a)(2) function described above, the BM system has the following intended function for .10 CFR 54.4(a)(1). : *
Support containment pressure boundary. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations .. A valve supporting the RWSP pressure boundary is reviewed in Section 2.3.2.2, Safety Injection. Chemical Feed The purpose of the chemical feed (CF) system is to feed various chemicals into the secondary system to maintain and control the pH and to control the oxygen level for the protection of the steam generator tube integrity. The CF system includes a hydrazine feed system-and an *ammonia feed system, designed to feed a hydrazine solution and an aqueous ammonia solution, respectively, into the secondary system. The system also includes two independent chemical feed skids generically designed to feed alternate chemicals as water chemistry technology evolves. The system consists of tanks, pumps, valves, piping, controls and indicators. Containment Atmosphere Purge The purpose of the containment atmosphere purge (CAP) system is to reduce the level of radioactive contamination in the containment atmosphere to permit personnel access. The CAP system consists of a containment purge air makeup unit and a separate containment purge exhaust which is connected to the exha.ust portion of the reactor auxiliary building HVAC (HVR) system. The CAP system includes no*faris; motive force. for the purge and makeup is provided by the HVR system exhaust fans. Apart from 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-116 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information containment isolat[on valves and ducting on the makeup and exhaust lines, the CAP system has no safety function. These valves also isolate the system on a high radiation signal to support the fuel handling accident analysis. The makeup portion of the system provides air to the containment while purge operations are being conducted. Makeup air enters through a louvered damper and passes through a medium efficiency filter and an electric heating coil. The makeup air flows in series through containment isolation valves to enter the containment. The exhaust portion of the system draws air from inlet dampers, arranged in parallel, serving the general containment area and the refueling pool area inside containment. Exhaust air passes through the inlet dampers and a series of containment purge isolation valves to the HVR system where it is filtered for removal of any radioactive particulates and radioiodines before being exhausted by HVR system exhaust fans to the plant stack. In addition to the 1 O CFR 54.4(a)(2) function described above, the CAP system has the following intended functions for 1 O CFR 54.4(a)(1 ).
Isolate the system on high radiation signal to support the fuel handling accident analysis.
Support containment pressure boundary. Components that isolate the system and also support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Decontamination Facility The purpose of the decontamination facility (OF) is to provide locations and facilities to decontaminate equipment. Equipment decontamination areas are provided at selected locations in the plant. The OF system code includes components of the decontamination equipment. These components include rinse tanks, pumps, filters, strainers, valves, and piping. Gaseous Waste Management The purpose of the gaseous waste management (GWM) system is to provide for collection, storage, sampling, and discharge of potentially radioactive gaseous waste. The GWM system consists of a gas surge tank, two waste gas compressors, three gas decay tanks, and the associated piping and valves required to collect gaseous waste and allow for release through the plant stack. Waste gases enter the GWM system by way of three headers: the vent gas collection header, the containment vent header, and the gas surge header. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-117 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The vent gas collection header collects gas primarily from aerated vents of process equipment in the boric. acid makeup and boron management systems, the liquid waste management system, the chemical and volume control system, and the fuel pool cooling and purification system. Because of the large volume of gas and the low activity level from the sources, the gases are routed directly to the plant stack. Waste gases which are routed to the gas surge header and containment vent header are mainly hydrogenated, radioactive, or potentially radioactive gases from various sources throughout the plant. Gaseous wastes are generated from reactor coolant degassing operations, processing of radioactive liquid wastes, and tank purging. These gases are collected and stored for decay in the gas surge tank prior to release to the environment. The gas surge tank acts as an accumulator for the system, allowing batch processing of the waste gases. The waste gas compressors process the gas, taking suction on the gas surge tank and discharging to a gas decay tank. The gas decay tanks collect the waste gas by the waste gas compressors and store it for approximately 60 days. This allows for the decay of the shorter lived nuclides and reduces the overall activity before the gas is discharged through the plant stack. _ Components of the containment vent header support the containment pressure boundary. Other GWM system components support the pressure boundary of the safety-related chemical and volume control (CVC) and the boron management (BM) system, which has no safety functions. In addition to the 10 CFR 54.4(a)(2).function described above, the GWM system has the following intended functions for 10 CFR 54.4(a)(1 ).
Support the pressure boundary of the chemical and volume control system.
Support containme_nt pressure boundary. Components that support the eve system are reviewed in Section 2.3.3.1, Chemical and Volume Control Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Hot Machine Shop and Decontamination Facilitv Ventilation The purpose of the hot machine shop and decontamination facility ventilation (HVD) system is to maintain a suitable operating environment for personnel and to limit concentrations of airborne radioactivity within the areas and in the exhausted air. The ventilation supply system includes two supply air handling units, one supplying the hot machine shop and the other the decontamination facility. Each air handling unit has a 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-118 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information medium efficiency filter, electric heating coil, chilled water cooling coil, a*nd centrifugal fan. Two exhaust air handling units, one each for the decontamination' room and hot machine shop, exhaust air using a medium efficiency filter, HEPA filter, and centrifugal Jan which discharges through a pneumatically operated damper and louver. The HVD system contains drain valves and piping located in the reactor building. Leak Rate Testing The purpose of the leak rate testing (LRT) system is to support integrated leak rate testing of the containment. The system includes pressure, temperature and humidity instrumentation and test connection valves on station air system containment penetrations (penetrations 63 and 65) and the H&V instrumentation penetration (penetration 53). These LRT valves form part of the containment pressure boundary. LRT system components containing indoor air and waste water are attached to safety-related equipment and located* in areas with safety-related equipment. In addition-to the 10 CFR 54.4(a)(2) function described above, the LRT system has the following intended function for 1 O CFR 54.4(a)(1 ).
Support containment pre_ssure boundary. Components that support containment pressure boundary are reviewec;l in Section 2.3.2.3, Containment Penetrations.
Liquid Waste Management The purpose of the liquid waste mc;inagement (LWM) system is to collect, store, process, monitor, and release liquid wastes while ensuring that all releases of radioactive materials, both in plant and to the environment, are within applicable requirements. The
system manages both radioactive and non-radioactive liquid wastes from process systems, equipment drains, and sumps. The system includes a variety of storage and collection tanks, pumps, piping, valves, filters, and instruments and controls. Post Accident Sampling
The purpose of the post accident sampling (PAS) system is to permit sampling of the primary coolant and safety injection sump following an accident. (Post-accident sampling of the containment atmosphere is supported by the hydrogen re.combiners and analyzers (HRA) system.) Components of the PAS system code are used to collect, cool and 2.0 -Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation.Results Page 2.3-119 \_ __ -*

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information analyze reactor ,coolant and safety injection sump samples. The system supports collection of diluted, undiluted, and full pressure liquid samples and gas grab samples. The PAS system consists of accumulators, a chiller, dryers, filters, heat exchangers, pumps, piping, valves, and instrumentation and controls. Post-accident sampling is not a safety function, and the system contains no safety-related components.

Nonsafety-related PAS components containing treated water or waste water are located in areas.with safety-related equipment. Potable Water The purpose of the potable water (PW) system is to distribute water from. the St. Charles* Parish Water System throughout the plant site. The system provides potable Wqter, both hot and cold, for drinking water, sanitary services, and emergency showers and eyewash stations. The distribution system also supplies makeup water to the fire water storage tanks and to the primary water treatment plant clearwell tank. The potable water distribution system may be used as necessary (if available) to replenish water to the wet cooling tower basins following a tornado. A hose connection in the makeup water supply to the fire water storage tanks and a p9rtable diesel-driven pump are provided to allow makeup from the potable water system to the wet cooling tower basins. However, because the availability of the potable water supply to the site is not assured following a tornado, this Is not an intended function for the potable water supply. The credited source is the Mississippi River through the circulating water system using the portable pump.
Potable water to the reactor auxiliary building is supplied via a solenoid-operated isolation valve. This valve isolates potable water to the reactor auxiliary building during a seismic event or piping rupture to prevent control room flooding. The system has no related components. Nonsafety-related components are located in areas with safety-related equipment. This includes piping and valves as well as a hot water storage tank and associated pump. In addition to the 10 CFR 54.4(a)(2) function described above, the PW system has the following intended function for 1 O CFR 50(a)(2), which is included in this review.
Isolate potable water from the reactor auxiliary building during a seismic event or piping rupture.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-120 I Primarv Makeup Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The prim.ary makeup (PMU) system provides storage and transfer capability necessary to supply demineralized water to primary plant systems including the chemical and volume control system, boron management system, reactor coolant system (reactor drain tank and quench tank), and waste management systems. The PMU system consists of a 260,000 gallon primary water storage tank (PWST) located in the yard, two full-capacity primary water pumps, and associated system valves, distribution piping, and instrumentation. PWST makeup comes from the demineralized water system. Th_e PMU pumps take suction from the PWST to supply primary grade water to plant loads. The system distribution piping includes safety-related components for a containment penetration. The system has no other safety functions except to support the pressure boundary of the eve system. . If.available. following a tornado, inventory from the PWST be used to replenish the wet cooling tower basin; however, because this tank is not protected from tornado missiles, this is not an intended function for the tank. The credited source is the Mississippi River through the circulating water system. In addition to 10 CFR 54.4(a)(2) function described above, the PMU system has the following intended functions for 10 CFR 54.4(a)(1). * . Support the CVC system pressure boundary.
Support containment pressure boundary. PMU system components that support the pressure boundary of the CVC system are reviewed in Section 2.3.3.1, Chemicaland Volume Control. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. PrimafY Sampling The purpose of the primary sampling (PSL) system is to collect and analyze fluid and gaseous grab samples from the reactor coolant system, chemical and volume control system, safety injection system, and the primary water storage tank during all modes of operation without requiring access to the containment. The PSL takes samples and brings them to a common location in the primary sampling room PSL panel in the reactor auxiliary building for analysis. The analyses performed on the samples determine fission and corrosion product activity levels, boron concentration, residual hydrazine, silica, lithium, pH and conductivity levels, crud concentration, dissolved gas concentration, and chloride. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-121 Waterford Steam Electric Station, Unit 3 License Renewal Application Techl']ical Information The PSL system includes safety-related components that form parts of the pressure boundary of the chemical and volume control system. The PSL system also includes components that are part of the containment pressure boundary. Other than the support of the safety-related system and containment pressure boundaries, the PSL system has no safety function. Safety-related components associated with safety injection (SI) system sampling are components in the SI system. In addition to the 10 CFR 54.4(a)(2) function described above, the PSL system has the following intended functions for 10 CFR 54.4(a)(1).
Support the *safety-related pressure boundaries of sampled systems.
Support containment pressure boundary. The PSL system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function (safety-related systems pressure boundaries) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). PSL system components that support the pressure boundary of the CVC system are reviewed in Section 2.3.3.1, Chemical and Volume Control. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. Radiation Monitoring The radiation monitoring system consists of components in the ARM and PRM system codes:
The purpose of area radiation monitoring (ARM) components is to inform operations personnel, both locally and in the main control room, of radiation levels in areas where area radiation monitoring system detectors are located, provide warning when abnormal radiation levels occur in specific plant areas, and warn of possible equipment
malfunctions. Some channels of the area radiation monitoring system provide a containment purge isolation signal and enable main control room operators to monitor radioactivity levels inside the containment. In the event of a fuel handling accident, the area radiation monitoring system provides a signal to isolate the fuel handling building and start the emergency ventilation system. The purpose of process radiation monitoring (PRM) components is to sample, detect, measure, and record trends of radioactive concentrations in liquid process systems, ventilation systems, and airborne or liquid effluents. These components also provide 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-122 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information alc;1rms and automatic termination o-r redirection of liquid and airborne radioactive discharges. PRM components support the pressure boundary of monitored systems. The radiation monitors are comprised mainly of EiC components, which are within the scope of license renewal by default (see Section 2.1.1). Intended functions performed by EiC components are not reviewed here. However, there are safety-related mechanical components with the ARM system code associated with containment atmosphere radiation sampling. Also, the PRM system code includes mechanical components (pumps, valves, piping, heat exchangers, dryers, and filters) to support the operation of some process monitors. These mechanical components for most of the radiation monitors are not classified as safety-related and have no safety function. However, the mechanical components that support monitoring of the containment atmosphere, plant stack effluent, and component cooling water are classified as safety-related .. The containment atmosphere radiation monitor (PRM-IR-0100Y) takes particulate, iodine and gas readings of the containment atmosphere to help detect identified or unidentified leaks in the RCS pressure boundary. While the rad _monitor itself and certain components associated with the monitor are classified as safety-related, they* do not perform a function in accordance with the criteria of 10 CFR 54.4(a)(1) and are therefore not within the scope of license renewal for 1OCFR54.4(a)(1). This rad monitor is associated with a containment penetration, and the piping and valves associated with the penetration perform a safety function in accordance with the-_criteria of 10 CFR 54.4(a)(1). The plant stack monitors (PRM-IRE-0100.1, -0100.2) provide indication of the activity levels of radioactive materials released to the environs, so that determination of the total release is possible. They are credited in FSAR Section 15.7.3.4 (referred to as airborne radiation monitors) for a containment purge isolation signal. Although the containment purge isolation has no protective function in accordance with IEEE Standard 279-1971, isolation of containment purge (system code GAP) is conservatively credited to support the fuel handling accident analysis. Therefore, the PRM system performs a safety function associated with the plant stack rad monitors. The component cooling water radiation monitors provide for early detection of radioactivity leakage into normally nonradioactive systems. This is not a safety function in accordance with 1 O CFR 54.4(a)(1) nor does it support a safety function (not credited in an analysis of off-site dose release). However, these components have an intended function of supporting the pressure boundary of the component cooling water _system. In addition to the 1 O CFR 54.4(a)(2) function describe(j above, the radiation monitoring system has the following intended functions for 10 CFR 54,4(a)(1).
Support isolation of containment purge in the event of c;i fuel handl.ing accident. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results -Page 2.3-123 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Support component cooling water system pressure boundary.
Support containment pressure boundary. Nonsafety-related components that support dry cooling tower sumps discharge flow paths to the circulating cooling water system are reviewed in Section 2.3.3.14, Plant Drains. Components supporting the component cooling water system pressure boundary are reviewed in Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water. The plant stack monitors are included in Section 2.3.3.12, Miscellaneous HVAC. The safety-related mechanical components of the containment atmosphere radiation monitors are reviewed in Section 2.3.2.3, Containment Penetrations. Reactor Cavitv Cooling The purpose of the reactor cavity cooling (RCC} system is to maintain the ambient steady state air temperature in the annular space between the reactorvessel and the concrete primary shield wall below the maximum design basis air temperature of the reactor cavity during normal operations. The system has no safety function. The RCC system consists of two full-capacity axial supply fans arranged in parallel and connected to a common supply duct. Each fan is provided with a supply discharge gravity damper to prevent recirculation through the standby fan. Each axial supply fan . . draws cooled air from the containment cooling system ring header. The fans supply air to ventilate the annular space between the reactor vessel and primary shield wall. Resin Waste Management The purpose of the resin waste management (RWM) system is to collect and store spent radioactive ion exchanger resin from the various process demineralizers*and to transfer resins to the portable solidification and/or dewatering system. The RWM system includes a spent resin spent resin transfer pump, spent resin dewatering pump, spent resin strainers, and associated valves, piping and controls.
For NPIS penetrations 75 and 76, resin waste management system piping and valves provide flood barrier protection during a Probable Maximum Flood (PMF) event. In addition to the 10 CFR 54.4(a)(2) function described*above, the RWM system has the . following intended function for 10 CFR 54.4(a)(2).
Support NPIS flood barrier. Components that support the NPIS flood barrier are reviewed in Section 2.3.3.14, Plant Drains. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management'Review and Implementation Results Page 2.3-124 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Secondary Sampling The purpose of the secondary sampling system is to collect steam and water samples from the secondary cycle, the makeup demineralizer, the blowdown demineralizer, condensate transfer pump discharge, and the steam generators and to bring them to a common location in the secondary lab and sampling room for analysis. Water quality analyses are performed to provide a basis for the control of the secondary cycle water chemistry and steam generator integrity. The analyses performed on the samples are . appropriate to determine pH, specific and cation conductivity levels, silica, sodium, dissolved oxygen, and residual hydrazine concentrations. The secondary sampling system includes components of the secondary sampling (SSL) system code and the constant temperature bath (CTB) system code. The CTB system components provide constant temperature cooling water used to cool secondary plant samples. The system includes coolers, pumps, a sample recovery tank, piping, valves, and instrumentation and controls. The SSL system code includes safety-related components that support the pressure boundary of the main steam system. The SSL system code also includes components that are part of the containment pressure boundary. Other than the support of the main steam system and containment pressure boundaries, the secondary sampling system has no safety function. In addition to the 1 O CFR 54.4(a)(2) function described above, the secondary sampling system has the following intended functions for 10 CFR 54.4(a)(1).
Support the safety-related pressure boundary of main steam system.
Support containment pressure boundary. The secondary sampling system has the following intended function for 1 O CFR 54.4(a)(3).
Perform a function (main steam pressure boundary) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48). Components that support the main steam pressure boundary are reviewed in Section 2.3.4.4, Main Steam. Components that support containment pressure boundary are reviewed in Section 2.3.2.3, Containment Penetrations. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-125 Solid Waste Management Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the solid waste management (SWM) system is to process, package and store low-level solid radioactive wastes for subsequent shipment and offsite burial. The SWM system code includes the waste concentrate storage tank, a dewatering tank, a *sodium silicate storage tank, a cement silo, pumps, and associated valves and piping. 'This equipment is not used. Isolation valves remain active in this system code. For NPIS penetration 114, solid waste management piping and a valve provide flood barrier protection during a Probable Maximum Flood (PMF) event. . . In addition to the 10 CFR 54.4(a)(2) function described above, the SWM system has the following intended function for 10 CFR 54.4(a)(2).
Support NPIS flood barrier. Components that support the NPIS flood barrier are reviewed in Section 2.3.3.14, Plant Drains.
Turbine Building Cooling Water The purpose of the turbine building cooling water (TC) system is to provide a heat sink for power cycle equipment during normal operation and shutdown conditions. The TC . system is a closed loop system which uses treated demineralized water to remove heat from the turbine auxiliaries and other components located within the turbine building. The water is circulated by two turbine cooling water pumps, and the heat removed via two turbine cooling water heat exchangers is transferred to the circulating water system. Components associated with the turbine building cooling water surge tank are located in the reactor auxiliary building. FSAR References The. following table lists the FSAR references for systems described in this section. System Code System FSAR Reference AE Air Evacuation Section 10.4.2 (main condenser evacuation system) ARR Airborne Radioactivity Removal Section 9.4.5.2 ANP Annulus Negative Pressure Section 9.4.5.8 AS Auxiliary Steam None 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-126 System Code BM CF CAP OF GWM HVD LRT LWM PAS PW PMU PSL ARM PRM RCC RWM SSL CTB SP, PME TC System Boron Management Chemical Feed Containment Atmosphere Purge Decontamination Facility Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Liquid Waste Management Post Accident Sampling Potable Water Primary Makeup Primary Sampling Radiation Monitoring Reactor Cavity Cooling Resin Waste Management Secondary Sampling Solid Waste Management Turbine Building Cooling Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information FSAR Reference Section 11.2.2.1 section 10.4.10 Section 9.4.5.3 None Section 11.3 Section 9.4.3.6 Figure 3.8-3 Section 11.2 Section 9.3.8 Section 9.2.4 Section 9.2.3 Section 9.3.2 Section 7.6.1.5 Section 11.5 Section 12.3.4 Section 9.4.5.6 Section 11.4.5 (spent resin transfer system) Section 9.3.2 Section 11.4 Section 9.2. 7 (turbine closed cooling water system) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-127 Components Subject to Aging Management Review Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A boundary determined using the bounding approach, which included piping beyond the safety-to..:nonsafety interface up to a flexible connection or the end *of a piping run (such as a vent or drain line) or up to and including a mounted component (4) Ail endpoint of a plant-specific* piping design analysis to ensure that forces and moments are restrained in three orthogonal directions. For spatial interaction, auxiliary system components containing water, oil, or steam and located in spaces containing safety-related equipment are subject to' aging management review in this 1 O CFR 54.4(a)(2) review if not already included in another system review .. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety-related piping in an auxiliary system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 1 O CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 1 O CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related .SSCs directly connected to safety-related SSCs. Series 2.3.3-15-x tables list the component types for auxiliary systems that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. Series 3.3.2-15-x tables provide the results of the aging management review for auxiliary systems for 10 CFR 54.4(a)(2) based on potential for physical.interactions. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-128 System Code AE ARR ANP AS BAM BM eve CF CHW, RFR, scH, sec cw cc IA,SA CAP CAR CB DF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT LWM NG PAS PW System Name Air Evacuation Airborne Radioactivity Removal Annulus Negative Pressure Auxiliary Steam Boric Acid Makeup Boron Management Chemical and Volume Control Chemical Feed Chilled Water Circulating Water Component Cooling Water Compressed Air Containment Atmosphere Purge Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Liquid Waste Management Nitrogen Post Accident Sampling Potable Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Types AMR Results Table 2.3.3-15-1 Table 3.3.2-15-1 Table 2.3.3-15-2 Table 3.3.2-15-2 Table 2.3.3-15-3 Table 3.3.2-15-3 Table 2.3.3-15-4 Table 3.3.2-15-4 Table 2.3.3-15-5 Table 3.3.2-15-5 Table 2.3.3-15-6 Table 3.3.2-15-6 Table 2.3.3-15-7 Table 3.3.2-15-7 Table 2.3.3-15-8 Table 3.3.2-15-8 Table 2.3.3-15-9 Table 3.3.2-15-9 Table 2.3.3-15-10 Table 3.3.2-15-10 Table 2.3.3-15-11 Table 3.3.2-15-11 Table 2.3.3-15-12 Table 3.3.2-15-12 Table 2.3.3-15-13 Table 3.3.2-15-13 Table 2.3.3-15-14 Table 3.3.2-15-14 Table 2.3.3-15-15 Table 3.3.2-15-15 Table 2.3.3-15-16 Table 3.3.2-15-16 Table 2.3.3-15-17 Table 3.3.2-15-17 Table 2.3.3-15-18 Table 3.3.2-15-18 Table 2.3.3-15-19 Table 3.3.2-15-19 Table 2.3.3-15-20 Table 3.3.2-15-20 Table 2.3.3-15-21 Table 3.3.2-15-21 Table 2.3.3-15-22 Table 3.3.2-15-22 Table 2.3.3-15-23 Table 3.3.2-15-23 Table 2.3.3-15-24 Table 3.3.2-15-24 Table 2.3.3-15-25 Table 3.3.2-15-25 Table 2.3.3-15-26 Table 3.3.2-15-26 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-129 System Code System Name PMU Primary Makeup ,. PSL Primary Sampling ARM, PRM Radiation Monitoring HVR Reactor Auxiliary Building HVAC RCC Reactor Cavity Cooling RWM Resin Waste Management SSL, CTB Secondary Sampling SWM Solid Waste Management SP, PME Sump Pump TC Turbine Building Cooling Water License Renewal Drawings Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Types AMR Results Table 2.3.3-15-27 Table 3.3.2-15-27 Table 2.3.3-15-28 Table 3.3.2-15-28 Table 2.3.3-15-29 Table 3.3.2-15-29 Table 2.3.3-15-30 Table 3.3.2-15-30 Table 2.3.3-15-31 Table 3.3.2-15-31 Table 2.3.3-15-32 Table 3.3.2-15-32 Table 2.3.3-15-33 Table 3.3.2-15-33 Table 2.3.3-15-34 Table 3.3.2-15-34 Table 2.3.3-15-35 Table 3.3.2-15-35 Table 2.3.3-15-36 Table 3.3.2-15-36 Additional details for components subject to aging management review are provided in the following license renewal drawings.
System Code System Name LRA Drawings AE Air Evacuation LRA-G163 ARR Airborne Radioactivity Removal LRA-G853 sh 11 ANP Annulus Negative Pressure LRA-G853 sh 1 AS Auxiliary Steam LRA-G 164 sh 2 BAM Boric Acid Makeup LRA-G168 sh 3 BM Boron Management LRA-G171 sh 1 LRA-G171 sh 2 LRA-G171 sh 3 eve Chemical and Volume Control LRA-G168 sh 1 LRA-G168 sh 2 CF Chemical Feed LRA-G164 sh 1 LRA-G164 sh 6 LRA-G170 sh 1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Manageme.nt Review and Implementation Results LRA-G170 sh 3 LRA-G171 sh 2 Page 2.3-130 System Code CHW, RFR, SCH, sec cw cc IA, SA CAP CAR CB OF EG, EGA, EGC, EGF, EGL HVF FS GWM HVD LRT System Name Chilled Water Circulating Water Component Cooling Water Compressed Air Containment Atmosphere Purge Containment Atmosphere Release Containment Building Decontamination Facility Emergency Diesel 'Generator Fuel Handling Building HVAC Fuel Pool Cooling and Purification Gaseous Waste Management Hot Machine Shop and Decontamination Facility Ventilation Leak Rate Testing Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LRA Drawings LRA-G853 sh 3 LRA-G853 sh 4 LRA-G853 sh 9 LRA-G164 sh 5 LRA-G164 sh 6 LRA-G158 sh 2 LRA-G160 sh 1 LRA-G160 sh 5 LRA-G160 sh 2 LRA-G162 sh 1 LRA-G160 sh 3 LRA-G162 sh 3 LRA-G 160 sh 4 LRA-G170 sh 6 LRA-G152 sh 4 LRA-G157 LRA-G152 sh 6 LRA-G164 sh 6 LRA-G152 sh 9 LRA-G853 sh 1 LRA-G853 sh 21 LRA-G853 sh 1 None None LRA-1564-2044 LRA-5817-9519 LRA-G164 sh 1 LRA-G164 sh 2 LRA-G853 sh 2 LRA-G163 LRA-G169 LRA-G170 sh 4 LRA-G170 sh 6 None LRA-G164 sh 1 LRA-G164 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-131 System Code LWM NG PAS PW PMU PSL ARM, PRM HVR RCC RWM SSL, CTB SWM SP, PME TC System Name Liquid Waste Management Nitrogen Post Accident Sampling Potable Water Primary Makeup Primary Sampling Radiation Monitoring Reactor Auxiliary Building HVAC Reactor Cavity Cooling Resin Waste Management Secondary Sampling Solid Waste Management Sump Pump Turbine Building Cooling Water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information LRA Drawings LRA-G170 sh 1 LRA-G170 sh 2 LRA-G170 sh 3 LRA-G166 sh 1 sh 2 LRA-G168 sh 2 LRA-G162 sh 3 None LRA-G161 sh 2 LRA-G170 sh 3 LRA-G168 sh 2 LRA-G170 sh 5 LRA-G162 sh 1 LRA-G162 sh 5 LRA-G164 sh 2 LRA-G853 sh 11 LRA-G853 sh 16 LRA-G853 sh 15 LRA-G853 sh 21 LRA-G853 sh 1 LRA-G168 sh 1 LRA-G170 sh 5 LRA-G170 sh 1 LRA-G171 sh 1 LRA-G170 sh 2 LRA-G162 sh 1 LRA-G162 sh 4 LRA-G162 sh 2 LRA-G 162 sh 6 LRA-G170 sh 5 LRA-G173 sh 2 LRA-G173 sh 3 l-RA-G159 sh 2 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-132 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3;3-15-1 Air Evacuation System Components Affecting Safety-Related Systems Components Subject to Aging Management Review Co111ponent Type Intended Function Bolting Pressure bound.ary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components . Subject to Aging Management Review and Implementation Results Page 2.3-133 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-2 Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body
Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Strw;:tures and Components Subject to Aging Management Review and Implementation Results Page 2.3-134 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-3 Annulus Negative Pressure System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-135 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Table 2.3.3-15-4 Auxiliary Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-136 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-5 Boric Acid Makeup System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-137 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-6 Boron Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Condenser (shell) Pressure boundary Cooler housing Pressure boundary Demineralizer Pressure boundary Evaporator Pressure boundary Filter housing Pressure boundary Flow element Pressure bOLmdary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-138 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-7 Chemical and Volume Control System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary .Demineralizer Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-139 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-8 Chemical Feed System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Cylinder Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-140 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-9 Chilled Water System Nonsafety-Related Components Affecting Safety-Related Systems . Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Sc:oping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-141 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-1 O Circulating Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review. Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Valve body Pre.ssure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplementatipn Results Page 2.3-142 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-11 Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary . Filter housing Pressure boundary Flow element Pressure bo_undary Piping Pressure boundary .. Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-143 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-12 Compressed Air System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-144 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-13 Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boun*dary -Heater housing Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-145 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-14 Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-146 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-15 Containment Building Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-147 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-16 Decontamination Facility Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-148 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-17 Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-149 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-18 Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Blower housing Pressure boundary Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-150 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-19 Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Orifice Pressure boundary . Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-151 Waterford Steam Electric Station, Unit 3 Licel')se Renewal Application Technical Information Table 2.3.3-15-20 Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Cooler housing Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Separator Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-152 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-21 Hot Machine Shop and Decon Facility Ventilation System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-153 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-22 Leak Rate Testing System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-154 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-23 Liquid Waste Management System Nonsafety-Related Components Affecting_ Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Condenser (shell) Pressure boundary Cooler housing Pressure boundary Demineralizer Pressure boundary Evaporator Pressure boundary Filter housing Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary body Pressu're boundary 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and_ Implementation Results Page 2.3-155 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-24 Nitrogen System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary

Strainer housing Pressure boundary Trap Pressure boundary Valve body Pressure boundary 2.0 Scoping' and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-156 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-25 Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Chiller housing Pressure boundary Heat exchanger (shell) Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-157 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-26 Potable Water System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-158 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-27 Primary Makeup System Nonsafefy-Related'Components Affecting Safety-Related Systems Components Subject to Aging Management.Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results
Page 2.3-159 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-28 Primary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flex hose Pressure boundary Heat exchanger (shell) Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Trap Pressure boundary Valve body Pressure boundary Vessel Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-160 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-29 Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing '" Pressure boundary Heat exchanger (shell) Pressure boundary Piping Pressure boundary Pump casing Press1,1re boundary Trap Pressure boundary *-. Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-161 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-30 Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Damper housing Pressure boundary Ducting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-162 Waterford S!eam Electric station, Unit 3 License Renewal Application TechniQal Information Table 2.3.3-15-31 Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type . Intended Function Blower housing Pressure boundary Bolting Pressure boundary Ducting Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-163 Waterford steam Electric station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-32 Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-164 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-33
Secondary Sampling System Nonsafety-Related. Components Affecting Safety-Related Systems Components Subject to Aging Management Review-Component Type Intended Function Bolting Pressure boundary Cooler housing Pressure boundary Orifice .. Pressure boundary .-Piping Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results I Page 2.3-165 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-34 Solid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting* Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-166 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-35 Sump Pump System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Strainer housing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-167 Wate.rford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.3-15-36 Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems
Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-168
2.3.4 Steam and Power Conversion Systems The following systems are included in this section.
Section 2.3.4.1, Condensate Makeup and Storage
Section 2.3.4.2, Emergency Feedwater
Section 2.3.4.3, Main Feedwater
Section 2.3.4.4, Main Steam Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-169 2.3.4.1
Condensate Makeup and Storage System Description Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The purpose of the condensate makeup and storage system is to make up water to, and discharge water from, the condensate system and to store and transfer demineralized water for initial fill and makeup to various normally nonradioactive systems throughout the plant. The condensate makeup and storage system includes components in system codes CML.i (condensate makeup and storage system) and DW (demineralized water system). The CMU system includes two sources of condensate makeup: the safety-related condensate storage pool in the reactor/auxiliary building and the nonsafety-related condensate storage tank in the yard. The CMU system also indudes component cooling water makeup pumps and a distribution subsystem for the condensate storage pool. The DW system includes the nonsafety-related demineralized water storage tank located in the yard. The condensate storage tank and demineralized water tank are provided with a nitrogen blanket to maintain the dissolved oxygen content. These tanks share a distribution subsystem comprised of pumps, piping and valves with component identification numbers that use the CC (component cooling water), CD (condensate), CMU, and DW system codes; for license renewal, these components are included with the condensate makeup and storage system review.
The condensate storage pool is the water supply for the EFW pumps. The flow path from the condensate storage pool to the EFW pumps is considered part of the condensate makeup and storage system. The condensate storage pool, component cooling water makeup pumps, and the associated distribution subsystem provide makeup to the component cooling water system. They can also distribute makeup to the emergency diesel generator jacket water standpipes, the essential chiller expansion tanks, and the fuel pool makeup fill and purification loop. The makeup supply to the spent fuel pool provides a seismic Category I makeup supply from the condensate storage pool. The nonsafety-related condensate storage tank, demineralized water tank, condensate storage tank pumps, condensate transfer pump, hotwell transfer pump, and the associated distribution subsystem provide demineralized water to various systems and components, including the condenser hotwell, the auxiliary boiler, the chemical feed system, auxiliary feedwater pump, condensate storage pool, refueling water storage pool, and auxiliary component cooling water wet cooling towers. This subsystem also provides water to hose stations inside the reactor building. Apart from the containment pressure boundary components, the distribution subsystem from the condensate storage tank and demineralized water tank has no safety function. If available following a tornado, inventory from the condensate storage tank and demineralized water tank may be used to replenish the wet cooling tower basin; however, becpuse these tanks are not protected from tornado missiles, this is not an intended function for the tanks. The credited source is the Mississippi River through the circulating water system. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-170 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Two nonsafety-related valves (CMU-908 and -909, fuel casket spray valve isolation and bypass) are credited as part of the flood barrier for the fuel handling building for the design basis flood. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(1 ).
Provide a source of makeup to the component cooling water system, the emergency diesel generators and the essential chilled water system.
Provide water for the EFW pumps.
Support containment pressure boundary. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(2).
Provide a makeup water supply to the spent fuel pool.
Provide flood barrier for design basis flood.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The condensate makeup and storage system has the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (EFW water supply and makeup to other safe shutdown equipment) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (EFW water supply) that demonstrates compliance with the *Commission's regulations for station blackout (10 CFR 50.63). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-171

'; Waterford Steam EleCtric Station, Unit 3 License Renewal Application Technical Information FSAR References Section 9.1.3.1.e (spent fuel pool makeup) Section 9.2.3.2 (demineralized water) Section 9.2.6 (condensate storage) Section 10.4.9.2 (condensate storage pool) Components Subject to Aging Management Review Safety-related basket strainers in the condensate storage pool are reviewed in Section 2.4.2, Nuclear Plant Island Structure. Valves credited as flood barriers are reviewed in Section 2.3.3.14, Plant Drains. Components supporting the component cooling water system pressure boundary are reviewed in Section 2.3.3.3, Component Cooling and Auxiliary Component Cooling Water. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, . Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table 2.3.4-1 lists the component types that require aging management review. Table 3.4.2-1 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G 153 sh 4 LRA-G 160 sh 6 LRA-G161-sh 2 LRA-G163 LRA-G 164 sh 2 LRA-G169 LRA-G853 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and-Components Subject to Aging Management Review and Implementation Results Page 2.3-172 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-1 Condensate Makeup and Storage System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flow element Flow control Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Thermowell Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging.Management Review and Implementation Results Page 2.3-173 ! Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.2 Emergency Feedwater System Description The purpose of the emergency feedwater (EFW) system is to provide cooling water to the steam generators for the removal of decay heat from the reactor during emergency situations when the main feedwater system is not available. The system can also be used during emergency situations to cooldown the reactor coolant system to the temperature and pressure required for shutdown cooling system operation. The EFW system consists of two half-capacity motor-driven pumps, a full-capacity steam turbine-driven pump, and the associated piping and valves. For license renewal, the EFW system is considered to begin at the EFW pumps. Supply to the pumps from the condensate storage pool is provided by the condensate makeup and storage system. The three pumps take suction from a common suction header supplied by two lines from the condensate storage pool. The pumps discharge to a common supply header. Each EFW pump can be isolated by suction and discharge valves which are normally locked open. The suction and discharge lines of the pumps are normally cross-connected by locked-open manual valves. Water from the discharge header is then delivered to each main feedwater header through an arrangement of control and isolation valves. The discharge of the EFW pumps can supply either or both steam generators. Steam for the emergency feedwater pump turbine is supplied from either or both steam generators, taken upstream of the main steam isolation valves. The wet cooling tower basins of the auxiliary component cooling water system are available to the EFW pumps as an alternate source of water if the condensate storage pool becomes depleted. The EFW system has the following intended functions for 10 CFR 54.4(a)(1 ).

Provide cooling water to one or both steam generators for the removal of decay heat from the reactor during emergency situations when the main feedwater system is not available.
Support containment pressure boundary. The EFW system has the following intended function for 10 CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-174 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The EFW system has the following intended functions_for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). FSAR References Section 10.4.9 Components Subject to Aging Management Review The emergency feedwater pump turbine and EFW components that support the lube oil cooler for the emergency feedwater pump turbine governor and governor valve servo are reviewed in Section 2.3.4.4, Main Steam.' Components with an EFW component identification in the flow path from the condensate storage pool to the EFW pumps are reviewed in Section 2.3.4.1, Condensate Makeup and Storage. Nonsafety-related components of the system not included in other reviews whose failu-re could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 1 O CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table-2.3.,4-2 lists the _component types that require aging management review. Table 3.4.2-2 provides the results of the aging management review. License Renewal Drawings Additional details for components subject fo aging management review are provided in the following license renewal drawings. LRA-G 153 sh 4 LRA-G 160 sh 6 2,0 _ Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-175 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-2 Emergency Feedwater System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Coil Heat transfer Pressure boundary Heat exchanger (housing) Pressure boundary Orifice Flow control Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-176 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.3 Main Feedwater. System Description The purpose of the main feedwater (FW) system is to supply water from the condensate system to the steam generators at the proper pressure, temperature and flow rate to maintain steam generator water level under all plant operating conditions. The FW system components are arranged in two parallel paths that provide feedwater to each steam generator. The FW system consists of two turbine-driven pumps, three high-pressure heaters, regulating valves, isolation valves, and other miscellaneous valves and piping. A control system*operates the regulating valves and controls feed pump speed to maintain steam generator water level: The condensate system supplies water to the suction of the .feedwater pumps. Each feedwater pump discharges to the combined discharge header, which feeds three parallel high-pressure feedwater heaters. The heaters discharge to a single header.that splits to supply each steam generator. Following the split in the header, a flow venturi measures feedwater flow to each steam generator. Each steam generator feedwater supply line has one main feedwater regulating valve, one start-up feedwater regulating valve, and one motor-operated feedwater regulating bypass valve. Downstream of the regulating valves, the feedwater flows through a check valve, main feedwater isolation valve, and another check valve before going to the steam generator. The emergency feedwater (EFW) system ties into the feedwater lines downstream of the main feedwater isolation valves. When required, automatic isolation of the steam generators is provided by the main feedwater isolation valves with backup from the main feedwater regulating.valves and start-up feedwater regulating valves. The portion of the FW system from the check valves located outside containment to the steam generator feed nozzles is part of the containment pressure boundary. The FW system has the following intended functions for 10 CFR 54.4(a)(1).
Provide automatic isolation of the feedwater flow to the steam generators. I
Support the delivery of emergency feedwater to the steam generators.
Support containment pressure boundary. The FW system has the following intended functions for 1 O CFR 54.4(a)(2).
Provide backup automatic isolation of the feedwater flow to the. steam generators. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-177
' .. , i \ i I "'-. ... ./ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The FW system has the following intended functions for 1 O CFR 54.4(a)(3).
Perform a function (EFW system support, FW isolation) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Perform a function (EFW system support) that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). FSAR References Section 10.4.7 Components Subject to Aging Management Review Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfactory accomplishment of safety functions are reviewed in Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2). Remaining components are reviewed as listed below. Table 2.3.4-3 lists the-component types that require aging management review. Table 3.4.2-3 provides the results of the aging management review. License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. LRA-G151 sh 1 LRA-G 153 sh 4 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results . Page 2.3-178 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-3 Main Feedwater System Components Subject to Aging Management Review Component Type In.tended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary *' Tubing Pressure boundary \(alve body Pressure boundary -2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-179 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.4 Main Steam System Description This review includes the main steam system and supporting functions performed by the steam generator blowdown system and the reheat steam system. Main Steam The purpose of the main steam (MS) system is to convey steam from the steam generators to the high pressure turbine and to other auxiliary equipment for power generation. During power operating conditions, main steam normally supplies the high pressure main turbine, the moisture separator reheaters, and the auxiliary steam system. During reduced power conditions, main steam replaces or supplements steam to the feedwater pump turbines and the gland seal steam system. The main steam system is the source of steam for the turbine-driven emergency feedwater pump. The MS system provides for overpressure protection for the steam generators and main steam lines, discharges steam to the condenser or atmosphere when the main turbine* is unavailable, and provides for isolation of the main steam lines when required.
The main steam system conveys steam from the steam generators to the high pressure turbine through the containment vessel in two main steam lines. Downstream of the steam generators, / each main steam line has a flow element, six safety relief valves, a power-operated atmospheric relief valve, and a main steam isolation valve (MSIV). A steam supply line to the emergency feedwater pump turbine branches from each main steam line, upstream of the MS IVs. Downstream of the MSIVs, the main steam lines supply the high pressure turbine, the gland seal system, the auxiliary steam system, and a common main steam header. Lines from the main steam header supply the moisture separator reheaters, the steam generator feedwater pump turbines, and the steam bypass system. The steam bypass system, comprised of in the MS system code, includes six valves connected to the main steam header that discharge steam directly to the main condenser. In the event of a steam line break upstream of an MSIV and a failure of the MSIV to close on the unaffected steam generator, blowdown of the unaffected steam generator is prevented by the closure of the nonsafety-related*turbine stop valves and turbine bypass valves that serve as an acceptable backup for this accident. The MS system has the following intended functions for 10 CFR 54.4(a)(1).
Isolate the SGs from the non-safety portions of the MS system during emergency con.ditions by automatic closure of the MS IVs. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-180 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Dissipate heat generated and accumulated in the nuclear steam supply system (N$SS) to atmosphere during emergency conditions by operation of the main steam safety valves and/or the atmospheric dump valves until shutdown cooling can be initiated.
Provid.e main steam line and steam generator overpressure protection.
Provide redundant flow paths for the steam supply to emergency feedwater pump turbine.
Support containment pressure boundary. The MS system has the following intended functions for 10 CFR 54.4(a)(2).
Prevent blowdown of the µnaffected steam generator during a main steam line break ever:it when the fault is upstream of one MSIV and .the single failure is the failure of the other steam generator MSIV to close.
Maintain integrity of nonsafety-related components such that no physical interaction with safefy-related components could prevent satisfactorY accomplishment of a safety function. The Ms system has the following intended functions for 10 CFR 54.4(8)(3).
Perform a function (relief valves, MS IVs, EFW) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48).
Perform a function (support EFW) that demonstrates compliance with the Commission's . regulations for station blackout (10 CFR 50.63). Blowdown The purpose of the steam generator blowdown (BO) system is to control the chemical composition of water in the steam generator shells. The BO system removes water from the steam generators to maintain water chemistry. Two blowdown lines, one from each steam generator, exit the containment through their own penetrations. Two air-operate.d containment isolation valves, one inside and one outside, are located in each of the lines exiting containment. Downstream of the containment isolation valves, blowdown water pressure and temperature are reduced, and the water is processed through mixed bed demineralizers or processed as waste. Clean water is returned to .the secondary system. The system includes tanks, heat exchangers, pumps, demineralizers, piping, valves, flow elements, and instrumentation. The portion of the BO system from the steam generators to and including the outside containment isolati6n valves comprises an extension of the steam generator boundary. The remainder of the BO system has no safety function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-181 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The BD system has the following intended functions for 10 CFR 54.4(a)(1).
Support*the steam generator pressure boundary.
Support containment pressure boundary. The BD system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function. The BD system has the following intended function for 10 CFR 54.4(a)(3).
Perform a function (blowdown isolation) that demonstrates compliance with the Commission's regulations for fire protection (1 O CFR 50.48). Reheat Steam The purpose of the reheat steam (RS) system is to reheat and dry the high pressure turbine exhaust by means of the moisture separator reheaters and to provide the reheated steam to the low pressure turbines. Two horizontal axis, cylindrical shell combined moisture*separa.tor and. ' . ' reheater assemblies are installed in the steam lines connecting the high pressure and low pressure turbines.
Steam from the high pressure turbine passes up through the moisture separators. The water . separated from the steam is drained from the moisture separator-reheaters to the moisture separator reheater shell drain tanks, which drain into the intermediate pressure feedwater heaters. The steam then flows through the rehe.ater section of the moisture separator-reheater, where it is heated by a steam tube bundle. Main steam is supplied to this tube bundle froi:n the main steam line. The condensate from this tube bundle is drained to the moisture *separator reheater drain collector tank, which drains into the high feedwater heaters. Steam flow from the moisture separator reheaters is then directed to the low pressure turbines. A sepa_rate outlet located on Moisture Separator Reheater 8 supplies steam flow for normal operation of the feedwater pump turbines. In the event of a steam line break upstream of an MSIV and a failure of the MSIV to close. on the unaffected steam generator, blowdown of the unaffected steam generator is prevented by the closure of the nonsafety-related turbine stop valves and turbine bypass valves that serve as an acceptable backup for this accident. Part of this flow path is isolated by two RS valves to the steam generator feedwater pump turbines. The RS system has no intended functions for 10 CFR 54.4(a)(1). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-182 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The RS system has the following intended for 1 O CFR 54.4(a)(2).
Support preventing blowdown of the unaffected steam generator during a main steam line break event when the fault is upstream of one MSIV and the single failure is the failure of the other steam generator MSIV to close. The RS system has no intended functions for 1 O CFR 54A(a)(3): FSAR References Section 10.3 (main steam supply system) Section 10.4.4 (steam bypass system, also referred to as turbine bypass system) Section 10.4.8 (steam generator blowdown) Section 10.2.2.2.4 (reheat steam) Components Subject to Aging.Management Review The nitrogen chambers in the MSIV aCtuators are reviewed in Section 2.3}.11, Nitrogen. Nonsafety-related components of the system not included in other reviews whose failure could prevent satisfacfory accomplishment of safety functions are reviewed in* Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR S4.4(a)(2r Remaining compo-nents a're. reviewed as listed below .. Table 2.3.4-4 lists the component types that require aging manage*ment-review. _ Table 3.4.2-4 the results of the aging mariagemertt review. . License Renewal. Drawings Additional details for components subject to aging management review are provided in the followi_ng license renewal drawings. LRA-G151 sh 1 LRA-G151 sh 2 LRA-G151 sh 4 LRA-G 162 sh 2
LRA-G164 sh 5 LRA-G 165 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-183 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-4 Main Steam System Components Subject to Aging Management Review Component Type Intended Function Bearing housing Pressure boundary Bolting Pressure boundary Filter housing Pressure boundary Flow element Flow control Pressure boundary Heat exchanger (channel Pressure boundary head) Heat exchanger (shell) Pressure boundary Heat exchanger (tube sheet) Pressure boundary Heat exchanger (tubes) Heat transfer Pressure boundary Nozzle Flow control Pressure boundary Orifice Flow control Pressure boundary Piping . ,. Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer Filtration Strainer housing Pressure boundary Thermowell Pressure boundary Tubing Pressure boundary ,* Turbine casing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Subject to Aging Management Review and Implementation Results Page 2.3-184 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.3.4.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a}(2) As discussed in Sections 2.1.1.2 and 2.1.2.1.2, systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) interact with safety-related systems in one of two ways: functional or physical. A functional failure is one where the failure of a nonsafety-related SSC to perform its function impacts a safety function. A physical failure is one where a safety function is impacted by the loss of structural or mechanical integrity of an SSC. Functional Failure Functional failures of nonsafety-related SSCs which could impact a safety function are identified with the individual system's evaluation and are* not discussed in this section. Phvsical Failure This section summarizes the scoping and screening results for steam and power conversion (S&PC) systems based on 10 CFR 54.4(a)(2) because of the potential for physical interactions with safety-related equipment. Physical failures* may be related to structural support or to spatial interaction. Nonsafety-Related Systems or Components Directly Connected to Safety-Related Systems (Structural Support) At Waterford 3, certain components and piping outside the safety class pressure boundary must be structurally sound to maintain the pressure boundary integrity of safety class piping. Systems containing such nonsafety-related SSCs directly connected to safety-related SSCs (typically piping systems) are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2). Nonsafety-Related Systems or Components with the Potential for Spatial Interaction with Related Systems or Components The following modes of spatial interaction are described in Sections 2.1.1.1 and 2.1.2.1.2. Physical Impact or Flooding _ .
The evaluation of interactions due to physical impa9t or flooding resulted in the inclusion of structures and structural components. Structures and structural components are reviewed in Section 2.4, Scoping and Screening Results: Structures. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-185 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Pipe Whip. Jet Impingement. or Harsh Environments Systems containing nonsafety-related high energy lines that can affect safety-related equipment are included in the review for the criterion of 1 O CFR 54.4(a)(2). Where this criterion affected S&PC systems, those systems are within the scope of license renewal per 1 O CFR 54.4(a)(2). Leakage or Spray Nonsafety-related system components or nonsafety-related portions of safety-related systems containing water; oil, or steam are considered within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) if such components are located in a space containing safety-related SSCs. S&PC systems meeting this criterion are within the scope of license renewal per 1 O CFR 54.4(a)(2). The following S&PC systems, described in the referenced sections, are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) for physical interactions. System Number System Name Section Describing System BO Slowdown Section 2.3.4.4, Main Steam CD Condensate Section 2.3.4.5, Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) CMU Condensate Makeup and Storage Section 2.3.4.1, Condensate Makeup and ow Storage EFW Emergency Feedwater Section 2.3.4.2, Emergency Feedwater FW Main Feedwater Section 2.3.4.3, Main Feedwater MS Main Steam Section 2.3.4.4, Main Steam System Description The following system within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(2) is not described elsewhere in the application. Condensate The purpose of the condensate (CD) system is to supply purified and preheated water to the feedwater pumps via the condensate polishers and low-pressure and 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-186 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information intermediate-pressure feedwater heaters. The system also supplies water to the steam generator blowdown system, feedwater pump glands, and condenser exhaust hood spray. The major components of the condensate system are the main condenser, condensate pumps, gland steam condenser; low-pressure feedwater heaters, and pressure feedwater heaters. Apart from the condensate polisher system components, the condensate system includes the components in the feedwater flow path from the main condenser hotwell up to the feedwater pump suction. Condensate flow begins at the main condenser hotwell. The main condenser functions as the heat sink for the low-pressure turbines and pump turbines exhaust, main steam system bypass steam, and miscellaneous flows, drains and vents during normal operation. The condenser also provides de-aeration of the condensate. The pumps discharge water through the polishing demineralizers. A portion of the flow then passes through the tubes of the gl_and.steam condenser, which receives the exhaust steam from the glands of the main turbine and the feedwater pump turbines and condenses it back into water. After the gland steam condenser, the condensate flows through three parallel strings of low-pressure feedwater beaters and then through the
three pcirallel strings of intermediate-pressure feedwater heaters. Water exits the intermediate-pressure heaters and is combined with the discharge of the heater drain pumps (system FHD). The total water flow is sent to the combined suction of the steam generator feed pumps. The CD system code is used for safety-related piping that supports the flow path from ,the condensate storage pool to the emergency feedwater pumps. Safety-related piping using the CD system code also supports the condensate makeup and storage fill line to the condensate storage pool and the refueling water storage pool; the fill lines are pressure boundaries for the pools. This safety-related piping is reviewed for license renewal *as part of the condensate makeup and storage system (Section 2.3.4.1 ). The CD system code has no other mechanical components that are safety-related. The CD system has no .intended functions for 1 O CFR 54.4(a)(1 ). *. The CD system has the following intended function for 1 O CFR 54.4(a)(2).
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory
accomplishment of a safety function. The CD system has no intended functions for 1 O CFR 54.4(a)(3). 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-187 FSAR References Section 10.4.7 Components Subject to Aging Management Review Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information For each safety-to-nonsafety interface, nonsafety-related components connected to related components were included up to one of the following: (1) The first seismic anchor, which is defined as a device or structure that ensures that forces and moments are restrained in three orthogonal directions. (2) An equivalent anchor (restraints or supports), which is .defined as a boundary point that encompasses at least two supports in each of three orthogonal directions. (3) A. boundary determined using the bounding approach, which included piping beyond the safety-to-nonsafety interface up to a flexible connection or the end of a piping run (such as a vent or drain line) or up to and including a mounted component. . (4) An endpoint of a plant-specific piping design anaiysis to ensure that. forces and moments are restrained in three orthogonal directions. For spatial interaction, S&PC system containing water, oil, or steam and located in spaces containing safety-related equipment are subject to aging management review in this 54.4(a)(2) review if not already included in another system review. Components are excluded from review if their location is such that no safety function can be impacted by component failure. If a HELB analysis assumes that nonsafety.:related piping in an S&PC system does not fail or assumes failure only at specific locations, then that piping is within the scope of license renewal per 10 CFR 54.4(a)(2). Appropriate components are subject to aging management review to provide reasonable assurance that those analysis assumptions remain valid through the period of extended operation. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes maintaining structural integrity for components that are included for related SSCs directly connected to safety-related SSCs. Series 2.3.4-5-x tables list the component types for S&PC systems that require aging management review for 10 CFR 54.4(a)(2) based on potential for physical interactions. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-188 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Series tables provide the results of the aging management review.for S&PC systems for 1 O CFR 54.4(a)(2) based on potential for physical interactions. System Number System Component Types AMR Results SD Slowdown Table 2.3.4-5-1 Table CD Condensate Table 2.3.4-5-2 Table 3.4.2-5-2 CMU Condensate Makeup and Storage Table 2.3.4-5-3 .Table 3.4.2-5-3 DW EFW Emergency Feedwater . Table 2.3.4-5-4 Table 3.4.2-5-4 FW Main Feedwater Table 2.3.4-5-5 Table 3.4.2-5-5 MS Main Steam Table 2.3.4-5-6 Table 3.4.2-5-6 License Renewal Drawings Additional details for components subject to aging management review are provided in the following license renewal drawings. System Code System LRA Drawings SD Slowdown LRA-G164 sh 5 LRA-G164 sh 6 LRA-G173 sh 1 CD Condensate LRA-G164 sh 2 LRA-G164 sh 6 CMU Condensate Makeup and Storage LRA-G160 sh 1 DW LRA-G161 sh 2 LRA-G162 sh 3 EFW Emergency Feedwater LRA-G153 sh 4 FW Main Feedwater LRA-G153 sh 4 MS Main Steam LRA-G151 sh 1 LRA-G151 sh 4 LRA-G165 sh 3 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results .. LRA-G163 LRA-G853 sh 9 Page 2.3-189.

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-1 Slowdown System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Accumulator Pressure boundary Bolting Pressure boundary Demineralizer Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Heat exchanger (shell) Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to ,A.ging Management Review and Implementation Results Page 2.3-190 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4.;5-2 Condensate System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Piping Pressure boundary Sight glass Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-191 ,. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-3 Condensate Makeup and Storage System Nonsafefy-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Filter housing Pressure boundary Flow element Pressure boundary Piping Pressure boundary Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-192 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-4 Emergency Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Valve body Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-193 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-5 Main Feedwater System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Orifice Pressure boundary Piping Pressure boundary 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-194 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.3.4-5-6 Main Steam System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Module8 Support for criterion (a)(1) equipment Piping Pressure boundary Strainer housing Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary a. The MSIV hydraulic pump module provides lube oil that is used to maintain the MSIVs open. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.3-195 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4 SCOPING AND SCREENING RESULTS: STRUCTURES The following structures and structural components are within the scope of license renewal.

Section 2.4.1, Reactor Building
Section*2.4.2, Nuclear Plant Island Structure
Section 2.4.3, Turbine Building and Other Structures
Section 2.4.4," Bulk Commodities 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4.1 Reactor Building Description The reactor building is a Category I structure comprised of a free-standing steel containment vessel and a containment internal structure. The steel containment vessel is enclosed inside the shield building, which is a reinforced concrete structure. The reactor building, and all other seismic Category I structures are housed in a common reinforced concrete structure called the nuclear plant island structure (NPIS). The purpose of the reactor building is to support and protect the enclosed vital mechanical and electrical equipment, including the reactor vessel, the reactor coolant system, the steam generators, pressurizer, auxiliary and engineered safety features systems required for safe operation and shutdown of the reactor. The safety function of the reactor building is to limit the release of radioactive fission products following an accident thereby limiting the dose to the public and control room operators. The reactor building structure also provides physical support for itself, the reactor coolant system, engineered safety features, and other systems and equipment located within the structure. In addition, the reactor building supports the plant stack and also serves as a reliable final .barrier against the escape of fission products to ensure the leakage limits are not exceeded and fission product releases are within 1 O CFR 20 during normal plant operation and 10 CFR 50.67 during the postulated design basis accidents. The exterior walls and dome of the concrete shield building provide protection for the reactor vessel and all other safety-related system, structures and components inside the steel containment from missiles and natural phenomena. The carbon steel components and the concrete inside the steel containment vessel are credited as structural heat sinks in the energy absorption analysis during a loss of coolant accident. The reactor building and its associated structures contains jib cranes and monorails used for maintenance related activitie_s. During normal operations this equipment is stored and restrained in a designated storage position. An annular space is provided between the walls and domes of the steel containment vessel and concrete shield building to permit in-service inspections. A more detailed description of the reactor building is provided below. Steel Containment Vessel The steel containment vessel is a vertical upright cylinder, all welded steel pressure vessel with hemispherical dome and ellipsoidal bottom which houses the reactor pressure vessel, the reactor coolant piping, the pressurizer, the quench tank, the reactor coolant pumps, the *steam generators, and the safety injection tanks. It is completely enclosed by the reinforced concrete shield building. The steel containment vessel ellipsoidal bottom is totally encased in concrete and founded on the concrete base and common foundation mat with the shield building. A circular bridge crane or polar crane is used inside containment _to facilitate maintenance activities 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-2 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information during refueling. The polar crane girder support plates are welded to the shell liner. Except for some miscellaneous platform framing and some minor seismic restraints, no major floor framing or seismic restraint supports are attached to the shell liner. An equipment hatch constructed of carbon steel has been provided to enable passage of large equipment and components from the outside into the steel containment vessel during plant shutdown. The equipment hatch is a welded steel assembly, with a double gasket flanged and bolted cover. Additionally, two carbon steel personnel airlocks provide personnel access from the reactor auxiliary building into the steel containment vessel. The airlocks are equipped with double doors that are interlocked to prevent simultaneous opening of the two doors. Each door is designed with a double gasket to ensure a high degree of leak tightness. In addition to the equipment hatch and personnel airlocks, containment penetrations include piping penetrations (including the fuel transfer tube penetration) and electrical penetrations. Containment penetration assemblies form openings through the shield building and steel containment vessel for passage of electrical conductors, HVAC ducts, and process system piping, including the fuel transfer tube penetration. The function of the containment piping penetration assemblies is to provide for passage of process, service, sampling and/or instrumentation pipe lines (or in the case of the fuel transfer assembly, new or speriffuel) into the steel containment vessel, while maintaining the desired containment integrity and providing a leak-tight seal with adequate provisions for movement between the piping components and the

containment structure during operation. The safety-related containment integrity function is shared by the steel containment vessel, shield building, containment isolation system and penetration assemblies. Some assemblies, .such as guard pipes, also function as barriers between high energy process systems and the containment annulus, preventing pressurization of the annulus in the event of a high energy line preak. Bellows expansion joints serve to provide for the passage of process pipes into the containment while maintaining a leak tight seal between them and to absorb relative movements (thermal and/or seismic) between the containment vessel, shield building and/or the process piping. Bellows assemblies located between the containment vessel and the flued head are designated as primary bellows. Those bellows assemblies located between the shield wall and the flued head are designated as secondary bellows. The steel containment vessel contains one seismic Category I safety injection system (SIS) sump*and one containment sump. The SIS sump is a large collecting reservoir designed to provide an adequate supply of water to the containment spray system and SIS during the recirculation mode. The SIS sump is located at the lowest floor elevation inside containment exclusive of the reactor vessel cavity and containment sump. The containment sump, which is located at the lowest point within the reactor cavity, collects liquid discharges of low purity reactor grade) wastes from equipment, tanks, miscellaneous leak-off points, and floor drainage. Two sump pumps discharge the sump contents to the waste tanks through a radiation monitor located outside* the containment. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-3 Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Trisodium phosphate dodecahydrate (TSP) is stored in the containment in multiple containers located on the -11' MSL elevation. The containers are constructed of stainless steel angles, stainless steel plates at and bottom, and stainless steel wire mesh on the four vertical sides. The containers are all welded construction with a hinged top plate to allow for TSP surveillance inspection. The function of the TSP is to raise the SIS sump pH following a design basis loss of coolant accident. . Containment Internal structure The containment internal structures components and framing are seismic Category I and are enclosed completely by the steel containment vessel. The concrete components are the primary and secondary shield walls, a refueling canal, enclosures around the pressurizer and the regenerative heat exchanger. The internal steel structures are the reactor vessel, steam . generators and the reactor coolant pump support framing along with pipe, duct and tray . restraints, operating floor framing, and miscellaneous platform framing. Concrete floor fill, placed in the bottom. of the steel containment vessel support the internal structures. The concrete floor fill, concrete primary and secondary shield walls and the concrete enclosures form compartments within which the entire reactor coolant system is located. The primary and secondary shield walls and other containm_ent internc;il structures provide protection from internal missiles. The purpose of the internal structures is to provide structural support and radiation shielding for the reactor coolant system, auxiliary systems, and engineered features.
Around the reactor pressure vessel is a* primary shield wall. This wall is a rectangular reinforced concrete structure and provides support for the reactor vessel through a ring girder. A secondary shield wall consisting of two half-cylindrical reinforced concrete walls, enclose the steam generators, reactor coolant pumps and reactor coolant piping, located on each side ofthe reactor
vessel. A concrete pedestal resting upon the concrete floor fill provide support for the steam generators. The pressurizer and regenerative heat enclosures consist of reinforced concrete walls, supporting floor, and a roof forming compartments abutting the secondary shield wall. Vent openings in the pressurizer enclosure walls and supporting floor slab.provides for pressure relief. The secondary i;;hield wall and adjacent columns located on the concrete fill support both walls. The enclosures provide biological shielding during normal operation. For the'f>ressurizer enclosure the walls also serve to contain potential missiles. A watertight permanent cavity seal ring (PCSR) is installed between the reactor vessel flange .. and floor of the refueling pool specifically for the refueling operation. The PCSR has multiple hatches, which can be opened to provide access for activities within the reactor cavity. These hatches also allow for ventilation between the reactor cavity and the refueling cavity. During plant outages removable hatch covers are installed to provide a watertight seal. Double 0-ring_ 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page2.4-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information seals act against the PCSR and the removable hatches. A welded flexure ring is provided on the reactor vessel seal ledge and the refuel pool embedment ring. The flexure ring design permits relative displacement (due to a safe shutdown earthquake) between the vessel flange and the pool floor while still maintaining a watertight seal. To ensure a leak tight seal, the seals for the removable hatches are tested after installation and before flooding the pool. The refueling canal connects the reactor cavity and the spent fuel storage pool of the fuel handling building through the fuel transfer tube. The refueling cavity concrete provides a support structure for the operating floor, intermediate platform and* the missile shield above the reactor pressure vessel. The refueling cavity will be flooded with borated water during refueling.
Therefore, the refueling canal reinforced concrete walls are provided with a stainless steel liner completely covering the interior face of the cavity for the purpose of rendering the refueling cavity completeiy watertight. A refueling machine is the principal means of transporting fuel assemblies between the reactor cavity and the fuel transfer tube. The steel platform travels on steel tracks along each side of the reactor cavity above the refuel canal pool. Shield Building The shield building is a free standing structure without any structural ties between it and the steel containment yessel above the foundation level. Concrete fill placed in the bottom of the structure provides support of the steel containment. The shield building, supported on the common foundation of the NPIS, is a reinforced concrete structure constructed as a right cylinder with a shallow dome roof. Conventional reinforcing steel bars were used throughout the structure. Clearance between the bottom face of the concrete shield building dome and the top of the steel containment dome allows for access for inspection and to assure freedom of movemenf ofthe steel containment. An annulus airlock is provided for access from the outside environment to the shield building annular space. A shield building maintenance hatch is provided for equipment access to the steel containment vessel. A seismic Category I concrete filled door is provided for. this maintenance hatch at the exterior face of the shield building to protect this access opening. The door is double sealed to prevent in-leakage to the containment annulus space. The function of the shield building is to protect the steel containment vessel from external missiles and the annular space provided between the interior face of the concrete shield building walls and the outside face of the steel containment vessel provides the means for collecting and diluting any leakage. The reactor building has the following intended functions for 10 CFR 54.4(a)(1), (a)(2) and (a)(3).
Provide physical support, shelter and protection for safety-related equipment within the scope of license renewal. (10 CFR 54.4(a)(1)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Provide primary containment to limit the release of radioactive materials so that offsite doses from a postulated design basis accident are below the guideline values of 10 CFR 50.67. (10 CFR 54.4(a)(1)) .
Maintain integrity of nonsafety-related structural components such that safety functions are not affected. (1 O CFR 54.4(a)(2))
Provide shelter, support and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. The reactor building
houses equipment credited in the safe shutdown analysis for fire protection (10 CFR 50.48), for station blackout (10 CFR 50.63) and for anticipated transients without scram (10 CFR 50.62). (10 CFR 54.4(a)(3)) FSAR References Section 3.8.1 Section 3.8.2 Section 3.8.3 Section 3.8.4 Section 6.1.3 Section 6.2.2.2.2.1 Section 9.3.3.2.1.2 Figure 1.2-17 Figure 1.2-18 Figure 1.2-19 Figure 1.2-20 Figure 1.2-21 Figure 1.2-22 Components Subject to Aging Management Review Figure 3.8-31 Figure Figure 3.8-44 Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. structural commodities that are unique to the reactor building are included in this review. Those, that are common to in-scope systems and
structures (anchors, embedments, pipe and equipment supports, instrument panels and racks, cable trays, conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. Table 2.4-1 *lists the component types that require aging management review. Table 3.5.2-1 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Page 2.4-6 Subject to Aging Management Review and Implementation Results
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 Reactor Building Components Subject to Aging Management Review Component Crane: rails and str.uctural girders Crane: structural gii"ders Penetration bellows Penetration sleeves Plant stack. Steel components: annulus access lock Steel components: beams, columns and plates *steel components: impingement barriers Steel components: jib cranes Steel components: liner plate Heat sink Support for Criterion (a)(2) equipment Heat sink Support for Criterion (a)(2) equipment Enclosure protection Heat sink Pressure boundary Support for Criterion (a)(1) equipment Enclosure protection Heat sink Pressure boundary Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) .equipment Fire barrier Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Heat sink Missile barrier Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(2) equipment *Heat sink Support for Criterion (a)(1) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Intended Function Steel components: maintenance hatch shield Fire barrier door Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Steel components: monorails Heat sink Support for Criterion (a)(2) equipment Steel components: personnel airlock, escape Enclosure protection lock, construction hatch, maintenance hatch Fire barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: personnel airlock, escape Pressure boundary lock, construction hatch; maintenance hatch: Support for Criterion (a)(1) equipment locks, hinges; and closure mechanisms Steel components: pressure retaining bolting Heat sink Pressure boundary. Support for Criterion (a)(1) equipment Steel component: reactor missile shield Heat sink Missile barrier ' Support .for Criterion (a)(1) equipment Steel component: reactor cavity seal ring and Flood barrier hatches Heat sink Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Steel components: refueling maintenance Heat sink structure Support for Criterion (a)(2) equipment Steel components: refueling platform Heat sink equipment assembly and rails Support for Criterion (a)(2) equipment Steel elements (accessible areas): liner; liner Enclosure protection anchors; integral attachments (steel Heat sink *, containment vessel) Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Steel elements (inaccessible areas): liner; liner anchors; integral attachments (steel containment vessel) elements: SIS sump screens/strainers Support members: welds; bolted connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) Support members: welds; bolted c.onnections; support anchorage to building structure (supports and restraints for the reactor pressure vessel) Beams, columns, floor slabs and interior walls (primary and secondary shield walls; pressurizer compartments; reactor cavity; l!lnd missile shield and barriers) Concrete (accessible areas): shield building; all Concrete (accessible areas): refueling canal Intended Function Enclosure protection Heat sink* Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Heat sink Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(1) equipment Heat sink Support for Criterion (a)(1) equipment Enclosure protection Heat sink Missile barrier . Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment . Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-1 (Continued) Reactor Building Components Subject to Aging Management Review Component Concrete (accessible areas): shield building wall and dome;. interior and above-grade *exterior Concrete (inaccessible areas): refueling canal Concrete (inaccessible areas): shield building; all Compressible seals for annulus lock; escape lock; personnel lock; maintenance hatch Containment penetration seals and sealant Inflatable seal for maintenance hate.ti shielding door Moisture barrier Service Level I coatings Intended Function Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2).equipment Support for Criterion (a)(3) equipment Enclosure protection Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Missile barrier Pressure boundary Support for Criterion (a)(t) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Pressure boundary Support for Criterion (a)(1) equipment Pressure boundary Support for Criterion (a)(1) equipment Pressure boundary Support for Criterion (a)(1) equipment _ Enclosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying St.ructures and Components Subject to Aging Management Review and Implementation Results page 2.4-1 O (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 2.4.2 Nuclear Plant Island Structure Description The nuclear plant island structure contains the component cooling water system structure, fuel handling building, reactor auxiliary building, and reactor building. The reactor building is addressed separately in Section 2.4.1. Nuclear Plant Island Structure lNPISJ The purpose of the NPIS is to provide a common structure for the building, reactor auxiliary building, fuel handling building, and component cooling water system*sfructure as well as providing a common foundation mat for these structures. The nuclear plant island structure is a seismic Category I structure supported on a continuous reinforced concrete foundation mat. The NPIS is a reinforced concrete box structure with solid exterior walls. All exterior doors and penetrations below elevation +30 feet which lead to areas containing safety-related equipment are watertight. The structure is founded on a continuous reinforced concrete foundation resting on a compacted shell filter blanket, which is supported by the Pleistocene sediments. Double water stops are provided at the construction joints in the foundation mat, while single water stops for vertical construction joints in the exterior walls are provided up to elevation +30 feet. In addition, stainless steel plates are provided at the bottom of the mat, where sumps and mal'}holes are located. The cylindrical wall of the shield building is direcUy founded on the common mat as well as the steel containment vessel, which is supported on the concrete fill. To assure proper contact between the containment and the concrete fill, the !nterface is grouted with epoxy between the concrete fill and the bottom of the vessel through channels left by pulled tubing. The primary shield wall, secondary shield wall and refueling canal of the internal structure are also founded on concrete fill supported by the NPIS.

The nuclear plant island structure has the following intended function for 10 CFR 54.4(a)(1), (a)(2) and (a)(3). *
Provides physical support, shelter, and protection for safety-related systems*, structures, and components within the scope of license renewal. (10 CFR 54.4(a)(1))
Provides physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure* could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (1 O CFR 50.48) and station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-11 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling Water Svstem Structure The purpose of the component cooling water system (CCWS) structure is to provide a source of cooling water for safe shutdown of the plant. The CCWS structure is located on the east and west side of the reactor building. The structure comprises two independent sets of dry and wet cooling towers in conjunction with water stored in the wet cooling tower basins. Each set of dry and wet cooling towers consists of reinforced concrete box structures supported on the common mat foundation of the nuclear plant island structure. An access to the equipment hatch of the reactor building is provided in the west CCWS structure. The motor control centers and the transformers for the dry and wet cooling towers are protected from tornado missiles by grating capable of withstanding tornado missile impact. The purpose of the component cooling water system structure is to house the CCWS, which services all reactor auxiliaries and serves as the ultimate heat sink. The ultimate heat sink is defined as the dry cooling towers, the wet cooling towers, and the water stored in the wet cooling tower basins.
Dry Cooling Tower The dry cooling towers consist of two separate and independent forced draft cooling towers. Each dry cooling tower is subdivi.ded into five reinforced concrete and each chamber is equipped with three fans supported on the walls at different levels in each of these chambers. The cooling coils of three of the dry cooling tower chambers of each tower are protected from tornado missiles by grating located above the coils. Dry cooling tower fans and motors are located below grade, and protected from tornado missiles by building walls and/or access platforms. Wet Cooling Towers The wet cooling towers consist of two separate independent multi-fan cooling units. Each wet cooling tower has two reinforced concrete chambers. The wet cooling towers utilize fill section consisting of a large number of cross fluted, vertically oriented stainless steel sheets. These sheets are attached at their sides to stainless steel frames which in turn are supported by structural steel beams. The drift eliminator for the cooling tower is located above the water distribution pipes. Drift eliminators are constructed of vertical corrugated slats of stainless steel sheets. The fan deck of the wet cooling towers is constructed of a series of stainless steel panels and is supported by structural steel beams. These beams also support the fan-motor drive assembly and the fan stacks. Galvanized steel access hatches, located in the fan deck, provide means of access to the interior of the tower.
2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The component cooling water system structure has the following intended functions for 10 CFR 54.4(a)(1) (a)(2) and (a)(3). *
Provide physical support, shelter and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. (1 O CFR 54.4(a)(1))
Provide a source of cooling water for safe shutdown of the plant. The structure is designed to provide a reliable source of cooling water and is the ultimate heat sink. (10 CFR 54.4(a)(1 )) -* Provide physical support, shelter, and protection for nonsafety-related systems,
structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provide physical support, shelter, and protection for safety-related systems, structures, and components and nonsafety-related systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (1 O CFR 50.48) and for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) Fuel Handling Building The purpose of the fuel handling building is to provide housing for a spent fuel storage pool, spent fuel pool pumps, spent fuel pool heat exchanger, backup fuel pool heat exchanger, spent fuel pool purification pump and heating and ventilating equipment. The handling* building is located immediately north of the reactor building. The building is a reinforced concrete structure supported on the common NPIS mat foundation. Above the common foundation mat the building is structurally separated from the reactor building at all levels. The building's exterior walls, floors, and interior partitions provide plant personnel with biological radiation shielding and protection for the surrounding equipment. The spent fuel pool, within the structure, is a stainless steel-lined reinforced concrete tank structure provides space for storage of spent fuel, spent fuel cask an*d miscellaneous items. The spent fuel cask storage area is located adjacent to (on the west side of) the spent fuel pool. Stainless steel liners are placed directly against the concrete to form the sides of the three regions (spent fuel pool, spent fuel cask storage area and refueling canal). The steel floor liner plate is supported on a steel beam grillage, which in turn is supported by* the concrete base. The entire steel grill age is grouted to the underside of the floor liner plate. *A leak detection system is provided to monitor the pool liner welds. The system consists of a network of stainless steel angles attached to the outside of the pool liner walls and floor by means of seal welds. A bridge crane for the handling of spent fuel casks and for maintenance activities runs on rails supported on a reinforced concrete frame above the operating floor. Multiple bulkhead gates accommodate fuel handling, spent fuel cask handling and provide flood protection. Additionally, the removable 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
watertight gates provide separation of the pool storage areas. The removable gates.contain inflatable elastomer seals that provide a watertight seal between the gate and the pool wall liner face. lri the fuel handling building area there is one removable flood-protected gate (Gate 3A) welded shut. This gate is located by the spent fuel cask decontamination area and is provided as a flood barrier. The refueling canal is located adjacent to (on the west side of) the spent fuel cask storage area. The refueling canal connects the reactor cavity and the spent fuel storage pool of the fuel handling building through the fuel transfer tube. The transfer tube consists of a stainless steel pipe installed inside the carbon steel penetration connecting the refuel cavity and the spent fuel pool. The inner pipe acts as the transfer tube and is fitted with a double-gasketed blind flange in the refueling cavity. Expansion bellows are provided to compensate for differential movement between the two pipes and between the outer pipe and other structures. The handling of the spent fuel in the spent fuel pool is accomplished with the spent fuel machine which runs on rails along the top of the spent fuel pool structure.' Monorail hoists and a smaller crane service the equipment and new fuel storage area. The fuel handling building has the following intended functions for 10 CFR 54.4(a)(1 ), (a)(2), and (a)(3).
Provides physical support, shelter, and protection for safety-related systems, structures, and components within the scope of license renewal. (10 CFR 54.4(a)(1))
Maintain integrity of safety and nonsafety-related components such that safety functions are not affected. by providing biological shielding *and a watertight compartment in which to carry out the refueling process. (1 O CFR 54.4(a)(2))
Provide shelter, support and protection for safety-related equipment and related equipment within the scope of license renewal. The fuel handling_ building houses equipment credited in the safe shutdown analysis for fire protection (1 O CFR 50.48). (10 CFR 54.4(a)(3)). Reactor Auxiliary Building The purpose of the reactor auxiliary building is to provide plant personnel with the necessary
biological radiation shielding, protect.the equipment inside from the effects of adverse conditions and provide protection to cable and piping penetration areas of the reactor building. The reactor auxiliary building is a seismic Category I structure located immediately south of the reactor building. The reactor auxiliary building houses the waste treatment facilities, engineered safeguards systems, switchgear, laboratories, diesel generators and main control room. The reactor auxiliary building is a multistory reinforced concrete structure with an interior floor construction of concrete beams and girders supported by reinforced concrete columns founded on the common NPIS mat foundation. Above the common mat foundation, the building is. structurally separated from the reactor building at all levels. Within the waste treatment facility is 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information a seismic Category I cask handling bridge crane, for handling miscellaneous radioactive waste. The reactor auxiliary building also houses two seismic Category I fuel oil storage tanks for supplying two diesel generators. The tanks are located in separated enclosed vaults located on opposite sides of the reactor auxiliary building. These enclosures are fire barriers consisting of concrete walls, floors, and ceilings, The condensate storage pool (CSP) and refueling water storage pool (RWSP) are also contained as an integral part of the reactor auxiliary building. The CSP and RWSP are located in the north side of the reactor auxiliary building in separate concrete vaults lined with stainless steel. The pools are vented to the atmosphere and contain vacuum and vortex breakers. The reactor auxiliary building has the following intended functions for 1 O CFR 54.4(a)(1 ), (a)(2) and (a)(3).
Provide physical support, shelter, and protection for safety-related systems, structures, and components. (1 O CFR 54.4(a)(1 ))
Provide. physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of. function(s) identified for 10 CFR 54.4(a)(1). (10 CFR 54.4(a)(2))
Provi_de shelter, support and protection for safety-related equipment and nonsafety-related equipment within the scope of license renewal. The reactor auxiliary building houses equipment credited in the safe shutdown analysis, fire protection (1 O CFR 50.48), and for station blackout (1 O CFR 50.63) and environmental qualification (10 CFR 50.49). (10 CFR 54.4(a)(3)) . FSAR References Nuclear Plant Island Structure Section 2.4.1.1 Figure 3.8-1 Section 3.8.5.1 Figure 3.8-31 Figure 3.8-45 Component Cooling Water Structure Section 3.8.4.1.4 Figure 1.2-24 Section 9.2.2.2.1 Section 9.2.5.2 Fuel Handling Building Figure 1.2-25 Section 3.4.1 Figure 1.2-15 Section 3.8.3.1.3 Figure 1.2-16 Table 3.2-1 Table 3.2-1 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and lmplerrientation Results Page 2.4-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Section 3.8.4.1.3 Section 9.1.2.2 Section 9.1.4.2.2.4 Reactor Auxiliary Building Section 3.8.4.1.2 Figure 3.8-42 Section 9.5.1.1.3 Section 9.5.1 Section 10.4.9 Components Subject to Aging Management Review Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. Structural commodities that are unique to the NPIS structure are included in this review. Those that are common to in-scope systems and structures (anchors, embedments, equipment supports, instrument panels, racks, cable trays, and conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. Table 2.4-2 lists the component types that require aging management review. Table 3.5.2-2 provides the results of the aging management review. -2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-16 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-2 Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function a11c! ,Other Metif!IS '. ' ' ' , .. ' *' " .<. *; '" '1'* * '" .** Control room ceiling support system Support for Criterion (a)(2) equipment Cooling tower fill/mist eliminators Heat sink Support for Criterion (a)(1) equipment Cranes: rails Support for Criterion (a)(2) equipment Cranes: structural girders Support for Criterion (a)(2) equipment Steel components: all structural steel Enclosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: fuel pool gate Flood barrier Heat sink Support for Criterion (a)(1) equipment Steel components: fuel pool liner plate Heat sink Support for Criterion (a)(1) equipment Steel components: CSP liner plate Enclosure protection Heat sink Support for Criterion (a)(1) equipment Steel components: RWSP liner plate Enclosure protection Heat sink Support for Criterion (a)(1) equipment Steel components: monorails Support for Criterion (a)(2) equipment Steel components: vortex breakers/ screens/ Enclosure protection strainers Support for Criterion (a)(1) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results *<' Page 2.4-17 Waterford Steam Electric Station, Unit 3 Renewal Application Technical Information Table 2.4-2 (Continued) Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function . ,,. * .. ' *,. Concrete ':'" J ,*' ,, " Beams, columns, floor slabs and pipe chase Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): all Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): below-grade Enclosure protection exterior; foundation Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): interior and Enclosure protection above-grade exterior Flood barrier Heat sink Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results ' *, Page 2.4-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-2 (Continued) Nuclear Plant Island Structure Components Subject to Aging Management Review Component Intended Function Concrete (accessible areas): NPIS exterior Enclosure protection above-and below-grade; foundation Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): all Enclosure protection Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): exterior above-Enclosure protection and below-grade; foundation. Flood barrier Heat sink Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Masonry walls Enclosure protection Fire barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Roof slabs Enclosure protection Missile barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment . 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-19 2.4.3 Turbine Building and Other Structures Description The following structures are included in. this review.
Turbine Building
Other Structures Battery House, 230kV Switchyard Control House, 230kV Switchyard Fire Pump House Fire Water Storage Tank Foundations Manholes, Handholes and Duct Banks Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Transformer and Switchyard Support Structures and Foundations Turbine Building The purpose of the turbine building is to provide support and housing for the turbine-g'enerator and associated auxiliaries. The turbine building is adjacent to and south of the auxiliary building. The main generator is located on the turbine generator pedestal located at the operating floor level. The lower levels of the turbine building contain the turbine generator auxiliary equipment and the nonsafety-related medium voltage switchgear. The turbine building also houses the auxiliary medium voltage switchgear through which offsite or preferred power from the unit auxiliary or start-up transformers is distributed to the nonsafety-related loads and to the safety-related onsite power system. The turbine building houses no components identified as performing a safety function in accordance with 10 CFR 54.4(a)(1 ). To ensure that its structural integrity is maintained and that it will not affect 10 CFR 54.4(a)(1) structures, the turbine building is included in the scope of license renewal for 10 CFR 54.4(a)(2). The turbine building consists of reinforced concrete foundations, floor slabs, masonry block walls and metal siding up to the operating floor level. Above the turbine building operating floor the area is open to the atmosphere. Portions of the exterior wal.ls on the lower level consist of structural steel framing and metal siding. The lower superstructure also supports the turbine building gantry crane. Interior walls are masonry block and reinforced concrete designed to provide fire protection as. required to protect plant personnel and equipment. The turbine 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information pedestal is a reinforced concrete structure *supported on a separate foundation from the turbine building foundation mat. The turbine building has no intended function for 10 CFR 54.4(a)(1). The turbine building has the following intended function for 1 O CFR 54.4(a)(2) and (a)(3).
Maintain structural integrity of nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 10 CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 o CFR 50.63) and for fire protection (1 o CFR 50.48). (10 CFR 54.4(a)(3)) Other Structures Battery House, 230kV Switchyard The purpose of the battery house is to provide a protected area for the switchyard batteries in support of station blackout battery house, 230kV switchyard, is a nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety function. The battery house is a prefabricated metal building supported on a reinforced concrete foundation. The battery house, 230kV switchyard, has no intended functions for 10 CFR 54.4(a)(1) and (a)(2).
The battery house, 230kV switchyard, has the following intended functions for 10 CFR 54.4(a)(3). *
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for Station Blackout (1 O CFR 50.63). (10 CFR 54.4(a)(3)) . Control House, 230kV Switchyard The purpose of the control house is to provide a protected area for the relay panels which control commodities within the switchyard. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The control house, 230kV switchyard, is a nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety function. The control house is a prefabricated metal building supported on a reinforced concrete foundation. The control house, 230k\/ switchyard, has no intended functions for 10 CFR 54.4(a)(1) and (a)(2). The control house, 230kV switchyard, has the following intended functions for 10 CFR 54.4(a)(3).
Provides physical support, shelter, and protection for systems; structures, and. components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) Fire. Pump House The purpose of the fire pump house is to provide space for three horizontal centrifugal fire pumps (one motor driven and two diesel driven) and a jockey pump for fire main pressure maintenance and shelter for the security diesel. The fire pump house, located south of the demineralized water storage tank, is a * . nonsafety-related structure separated from safety-related systems, structures, and components such that its failure would not impact a safety*function. The fire pump house is a prefabricated metal building with structural steel framing and built-up roofing with exterior walls consisting of galvanized steel siding. The interior walls are of concrete block construction. The entire structure is supported on a reinforced concrete foundation supported on wooden piles driven into the subgrade. Three-hour .fire barriers consisting of concrete block walls separate fire pumps, located in cubicles within the structure from each other. The pumps take their suction from two --vertical ground level water storage tanks located south. of the structure. The fire pump house has no intended functions for 10 CFR 54.4(a)(1) and (a)(2). The fire pump house has the following intended functions for 1 O CFR 54.4(a)(3).
Provides physical support shelter, and protection for systems, structures, and components re.lied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for fire protection (1 O CFR 50.48) and station blackout (1 O CFR 50.63). (1 O CFR 54.4(a)(3)) 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-22 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire Water Storage Tank Foundations The purpose of the fire water storage tank foundations are to provide structural support for two fire water sto.rage tanks.* The fire water storage tank foundations are individual foundations located adjacent to and south of the fire pump house and consists of a mat foundation constructed of reinforced concrete supported on concrete piles with steel pipe casings driven into the subgrade. The fire water storage tank foundations are nonsafety-related structures separated from safety-related systems, structures, and components such that its failure would not impact a safety function. 1The fire water storage tank foundations have no intended functions for 10 CFR 54.4(a)(1) *and (a)(2). The fire water storage tank foundations have the following intended functions for 10 CFR 54.4(a)(3). .*
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commissions' regulations for fire protection (10 CFR 50.48). (10 CFR 54.4(a)(3)) . Manholes, Handholes and Duct Banks The purpose of manholes, handholes and duct bank_s are to provide structural support, shelter and protection to systems, structures, and components that are relied on in safety analysis or plant evaluations to perform a function that demonstrates compliance with the Commission's regulated events and are housed within these structures during normal plant pperation, and during and following postulated design basis accidents. Manholes and handholes consist of reinforced concrete rectangular box structures buried underground with a reinforced concrete panel on top or incorporated as part of the NPIS basemat. The manholes have an 'opening and a cover to allow access. There are no Class IE manholes located on the NPIS. The remaining manholes are located in the yard and are not identified as Class IE, but support a license renewal intended function. In some instances, adjacent to each manhole is a handhole structure, which is* physically independent of the manhole structure but it does become part of the underground duct as it ties into it on both sides of the manhole structure. These hahdholes provide access to communication cables located within the duct run. Manholes, handholes and duct banks allow underground routing of cables and some piping. Redundant trains are utilized as necessary to meet site conditions. This redundancy is provided 2.0 Scoping and Screening Methodology for Identifying Structures and Components
Subject to Aging Management Review ar;id Implementation Results Page 2.4-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information as either entirely separate trains or designed with separating, reinforced concrete walls between the trains. --Duct banks comprise multiple raceways in an excavated trench in the yard that are encased in concrete and then backfilled with soil or engineered compacted backfill. The duct banks are used to route cables between structures and switchyard areas. Duct banks that are b1:1ried shallow in the yard may be provided with a reinforced concrete protection slab that is cast over the duct bank. * -These structures have no intended function for 10 CFR 54.4(a)(1). These structures have the following intended function for 10 CFR 54.4(a)(2) and (a)(3).
Provides physical support, shelter, and protection for nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of function(s) identified for 1 O CFR 54.4(a)(1 ). (10 CFR 54.4(a)(2))
Provides physical support, shelter, and protection for: systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with Commissions' regulations for fire protection (10 CFR 50.48) and station blackout (10 CFR 50.63). (10 CFR 54.4(a)_(3)) Transformer and Switchyard Support Structures and Foundations The purpose of transformer and switchyard support structures and foundations is to provide structural support to systems, structures, and components that are relied on in safety analysis or plant evaluations to perform a function that demonstrates compliance with the Commission's regulation for station plackout, specifically those necessary to recqver offsite power following a station blackout. The transformer and switchyard support structures and foundations are located in the switching station and 230kV switchyard. The switching station is located.adjacent to and south of the _ turbine building. The 230kV switchyard is located an additional distance south of the turbine building. -The structures that provide physical support to the switching station and 230kV switchyard components in the* station blackout offsite power recovery path include the transformer foundations and foundations for the associated switchyard breakers, switchyard bus, switchyard towers, cable duct banks, and cable trenches. The transformer yard foundations are reinforced concrete pedestals that are supported by a reinforced qoncrete spread footing at grade or below grade. Structural steel members support the electrical components necessary for the electrical distribution system in the switchyards and are supported by the reinforced concrete pedestals. Transmission and pull-off towers are steel tower structures supported on reinforced concrete pier 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-24 Waterford Steam !=lectric Station, Unit 3 License Renewal Application Technical Information foundations. Therefore, the transformers and supporting structures are within the scope of license renewal based on the criterion of 1 O CFR 54.4(a)(3). The transformer and switchyard support structures include the transformer and breaker foundations and supporting steel. The transformer and switchyard support structures and foundations have no intended functions for (10, CFR 54.4(a)(1) or (a)(2). The transformer and switchyard support structures and foundations have the following intended function for 1 O CFR 54.4(a)(3).
Provides physical support, shelter, and protection for systems, structures, and components relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (10 CFR 50.63). (10 CFR 54.4(a)(3)) FSAR References Turbine Building None Other Structures Battery House, Control House, Manholes and Duct Banks None Fire Pump House Section 9.5.1.2.2 Section 9.5.1.3 Transformer and Switchyard Support Structures and Foundations Section 1.2.2.4 . Figure 8.1-4 Section 8.2 (system function) Section 8.2.1 Section 8.2.1.3 Figure 8.1-5 Components Subject to Aging Management Review Structural commodities are structural members that support or protect plant equipment including system components, piping, and electrical conductors. Structural commodities that are unique to. the turbine building and other structures are included in this review. Those that are common to in-scope systems and structures (anchors, embedments, equipment supports, instrument panels, racks, cable trays, and conduits, etc.) are reviewed in Section 2.4.4, Bulk Commodities. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-25 Waterford Steam Electric Station,. Unit 3 License Renewal Application Technical Information Table 2.4-3 lists the component types that require aging management review. Table 3.5.2-3 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-26 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Table 2.4-3 Turbine Building and Other Structures Components Subject to Aging Management Review Intended Function . */ .. . . . . ... .. . . . '"*;"' Steel and Other Metals.*. " ' . ' ' . .,A,<, ... . . .. ,',, .. . ' **"* . ... , . Cranes: rails and structural girders Support for Criterion (a)(2) equipment Steel components: all structural steel Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Steel components: metal siding Enclosure protection Support for Criterion (a)(2) equipment Steel components: roof decking or floor Enclosure protection decking Fire barrier Steel piles Support for Criterion (a)(3) equipment Transmission tower, angle tower, pull-off Support for Criterion (a)(3) equipment tower ' .. ... ' ' '* *<< *'* ** ... ..**:, .:; > ,* ! :: Concrete .. .. .. , . ': . ' ," ,,_,,.,, " . ' . *:* ,, .. '; .. . : ;.*r ** .. *.:: '.: *:' :. .. '. Beams, columns and floor slabs Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): all Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): below-grade Enclosure protection exterior; foundation Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): interior and Enclosure protection above-grade exterior Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (accessible areas): exterior above-Enclosure protection and below-grade; foundation Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Concrete (inaccessible areas): all Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results <;/ ,., . . ; *-,.> '* . . Page 2.4-27 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-3 (Continued) Turbine Building and Other Structures Components Subject to Aging Management Review _Component Concrete (inaccessible areas): exterior above-and below-grade; foundation Duct banks Foundations (e.g., switchyard, transformers, tanks, circuit breakers) Manholes and handholes Masonry walls Wooden piles. Intended Function Enclosure protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure Protection Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enelosure protection Fire barrier _Flood barrier Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Fire barrier
Support for Criterion (a)(2) equipment Support for (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-28 2.4.4 Bulk Commodities Description Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information Bulk commodities subject to aging management review are structural components or commodities that perform or support intended functions of in-scope systems, structures and components (SSCs). Bulk commodities unique to a specific structure are included in the review for that structure (Sections 2.4.1, 2.4.2, and 2.4.3). Bulk commodities common to in-scope SSCs (e.g., concrete embedments and anchors, bolted connections/bolting, component supports, cable trays, compressible joints and seals, conduit, decking, doors [including air locks and bulkhead doors], electrical panels and enclosures, hatches/plugs, instrument panels and racks, miscellaneous steel, racks, piping and equipment supports, tube track supports) are addressed in this review. Bulk commodities evaluated in this section are designed to support both safety-related and nonsafety-related equipment during normal and accident conditions in the event of external events '(tornadoes, earthquakes, floods, missiles) and internal events (LOCA, pipe breaks). Bulk commodities are structural components that support the various intended functions performed by the structures in which they are located. These functions for 10 CFR 54.4(a)(1), (a)(2), and (a)(3) include the following.
Provide support, shelter and protection for safety-related equipment and related equipment within the scope of license renewal. 1 O CFR 54.4(a)(1)
Maintain integrity of nonsafety-related structural components such that safety functions are not affected. 1 O CFR 54.4(a)(2)
Provide support and protection for equipment credited in the Appendix R safe shutdown analysis and for fire protection (1 O CFR 50.48), for environmental qualification (10 CFR 50.49), for anticipated transients without scram (10 CFR 50.62), and for station blackout (10 CFR 50.63). 10 CFR 54.4(a)(3) Insulation may have the specific intended functions of (1) maintaining local area temperatures within design limits or (2) maintaining integrity such that falling insulation does not damage safety-related equipment. FSAR References None 2.0 Scoping and Screening Methodology for Identifying Structures and Components . Page 2.4-29 Subject to Aging Management Review and Implementation Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Components Subject to Aging Management Review Bulk commodities subject to aging management review are structural components or commodities that perform or support intended functions of in-scope SSCs. Bulk commodities unique to a specific structure are addressed in the aging management review for that structure. Bulk commodities common to in-scope SSCs (anchors, embedments, pipe and equipment supports, instrument panels and racks, cable trays, conduits, etc.), as well as seismic II/I supports, are ir:icluded in this evaluation. Insulation is subject. to aging management review if it performs an intended function as described above. . . Table 2.4-4 lists the component types that require aging management review. Table 3.5.2-4 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging M*anagement Review and Implementation Results Page 2.4-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 Bulk Commodities Components Subject to Aging Management Review Component Anchorage/embedments Cable tray Conduit Constant and variable load spring hangers;* guides; stops (Supports for ASME Class 1, 2 and 3 piping and components) Doors Fire doors Fire hose reels Fire protection components: miscellaneous steel, including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Manways, hatches, manhole covers and hatch covers Mirror insulation Missile shields Intended Function Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Enclosure protection Flood barrier Missile barrier Pressure boundary Fire barrier Support for Criterion (a)(3) equipment Support for Criterion (a)(3) equipment Fire barrier Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Enclosure protection Flood barrier Missile barrier Pressure boundary Support for Criterion (a)(1) equipment Support. for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(2) equipment Enclosure protection Missile barrier 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 (Continued) Bulk Commodities Components Subject to Aging Management Review Component Miscellaneous steel (decking, grating, handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc.) Penetration seals (end caps) Penetration sleeves (mechanical/electrical not penetrating PC boundary) Racks, panels, cabinets and enclosures for electrical equipment and instrumentation Tube track Supports for ASME Class 1, 2, 3 piping and components (constant and variable load spring hangers; guides; stops) Support members; welds; bolted connections; support anchorage to building structure Anchor bolts Intended Function Enclosure protection Flood barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Enclosure protection Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Enclosure protection Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Endosure protection Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)°(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-32 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.4-4 (Continued) Bulk Commodities ComponentS Subject to Aging Management Review Component High-strength structural bolting (supports for ASME Class 1, 2, and 3 piping and components Structural bolting; structural steel and miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc.) Structural bolting Building concrete at locations of expansion and grouted anchors; grout pads for support base plates Equipment pads/foundations Curbs . Manways, hatches/plugs, manhole covers and hatch covers Missile shields Structural fire barriers, walls, ceilings, floor slabs, curbs, dikes Support pedestals Intended Function Support for Criterion (a)(1) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Flood barrier Support for Criterion (a)(2) equipmenf Support for Criterion (a)(3) equipmen_t Fire barrier Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment Missile barrier Fire barrier Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment Support for Criterion (a)(3) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table-2.4-4 (Continued) Bulk Commodities Components Subject to Aging Review Compressible joints and seals Fire stops Fire wrap Insulation (includes jacketing, wire mesh, tie wires, straps, dips) Penetration seals . Roof membranes Seals and gaskets (doors, manways and hatches) Vibration isolators Support for Criterion (a)(1) equipment .support for Criterion (a)(2) equipment Fire barrier Fire barrier *Insulation Support for Criterion (a)(2) equipment Enclosure protection Fire barrier
Flood barrier Pressure boundary Support for Criterion (a)(2) equipment Enclosure protection Support for Criterion (a)(2) equipment Flood barrier Pressure boundary Support for Criterion (a)(1) equipment Support for Criterion (a)(1) equipment Support for Criterion (a)(2) equipment 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.4-34 \

( Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS Description As stated in Section 2.1.1, plant electrical and instrumentation and control (l&C) systems are included in the scope of license renewal as are electrical and l&C components in mechanical systems. The default inclusion of plant electrical and l&C systems in the scope of license renewal is the bounding approach used for the scoping of electrical systems. The basic philosophy used in the electrical and l&C -components IPA is that components are included in the review unless specifically screened out. When used with the plant spaces approach, this method eliminates the need for unique identification of individual components and specific component locations. This assures components are not improperly excluded from an aging management review. The electrical and l&C IPA began by grouping the total population of com*ponents info commodity groups. The commodity groups include similar electrical and l&C*components with common characteristics. Component level intended functions of the commodity groups were identified. During the IPA screening process, commodity groups and specific plant systems were eliminate.d from further review if they did not perform or su.pport an intended function. *

In addition to the plant electrical systems, certain switchyard components used to restore offsite power following a station blackout (SBO) were conservatively included within the scope of license renewal even though those components are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (1 O CFR 50.63). The April 1, 2002, SBO guidance letter 1 and NUREG-1800 Section 2.5.2.1.1 provide scoping guidance to include equipment needed.for site power recovery, which includes equipment not explicitly required for compliance with 10 CFR 50.63.* LRA Drawing LRA-G285 depicts the electrical interconnection between Waterford 3 and the offsite transmission network. LRA Drawing LRA-G285 identifies* major components or commodities associated with off-site power recovery following SBO. The highlighted portions depict the components in the SBO recovery path that are subject to aging management review. Components in the off-site power circuits that are not highlighted have no intended function for license renewal and thus a.re not subject to aging management review. 1. NRG.to NEI, "Staff Guidance on Scoping of Equipment Relied on to Meet the Requirements of the Station Blackout (SBO) Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3))," letter dated April 1, 2002 (ISG-02). ADAMS accession number ML020920464. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-1 FSAR References Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Additional details for electrical systems and commodities can be found in FSAR Chapters 7 and 8. Scoping Boundaries Plant electrical and l&C systems are included in the scope of license renewal as are electrical and l&C components in mechanical systems. Waterford 3 preferred (offsite) power is from the 230 kV switchyard via two physically and independent circuits via overhead transmission lines to the switching station and then to the startup transformers. The .startup transformers supply power to the nonsafety-related buses (3A2 and 382). The nonsafety-related buses (3A2 and 382) supply power to the related buses (3A3-S and 383-S). The ESF buses 3A3-S and 383-S may also receive power from the two diesel generators, should the preferred power from buses 3A2 or 382 be unavailable. All safety-related loads receive power from these two buses. Waterford 3 takes no credit for backfeed through the main transformers as an offsite .power source. . The offsite power source required to support SBO recovery. actions is the source from the 230 kV switchyard supplying the startup transformers. The path for offsite power recovery includes two 230 kV switchyard circuit breakers feeding each startup transformer, the circu_it transformer and ttansformer-to:onsite electrical distribution)nterconnections, and the associated control circuits and structures. Steel transmission towers and foundations, structures housing switchyard batteries, and structures supporting breakers, disconnects, transformers, transmission conductors, and switchyard bus utilized in the 230-kV off-site power recovery paths are evaluated in Section 2.4, Scoping and Screening Results: Structures. Commodity Groups Subject to AMR As discussed in Section 2.1.2.3.1, Waterford 3 passive electrical commodity groups corresponµ to two of the passive commodity groups identified in NEI 95-1 O:
High voltage insulators. ,
Cables and connections, bus, electrical portions of electrical and l&C penetration assemblies, fuse holders outside of cabinets of active electrical components. The commodity group cables, connections, bus, electrical portions of electrical and l&C penetration assemblies, and fuse holders outside of cabinets of active electrical components is further subdivided into the following. 2.0 Scoping and Screening Methodology for Identifying structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Cable connections (metallic parts).
Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements.
Electrical cables and connections subject to 10 CFR 50.49 EQ requirements.2
Electrical cables and connections not subject to 1 O CFR 50.49 EQ requirements used in instrumentation circuits.
Electrical and l&C penetration cables and connections not subject to 10 CFR 50.49 EQ requirements. 3 *
Fuse holders -insulation material.
Fuse holders -metallic clamp.4
Inaccessible power(?_ 400 V) cables (e.g., installed underground In conduit, duct bank or direct buried) not subject to 10 CFR 50.49 EQ requirements.
Metal enclosed bus -bus I connections.
Metal enclosed bus -enclosures assemblies (elastomers, external surfaces).
enclosed bus -insulation I insulators.
Switchyard bus and connections.
Transmission conductors and connections.
Uninsulated ground conductors.5 Commodity Groups Not Subject to AMR Electrical and l&C Penetration Assemblies All Waterford 3 electrical and l&C penetration assemblies are in the EQ program (1 O CFR 50.49). Waterford 3 electrical and l&C penetration assemblies in the EQ program are subject to replacement based on their qualified life, so they are not subject to aging management review. Non-EQ cables and connections to electrical and l&C penetrations are evaluated in the insulated cable and connection commodity group. Fuse Holders -Metallic Clamp A review of Waterford 3 documents (e.g., drawings, procedures, FSAR, Waterford 3 Equipment Database (Asset Suite) functional location list, and electrical design basis documents) identified fuse holders. No circuits with an LR intended function with fuse holders were identified needing 2. Waterford 3 electrical cables and connections subject to 10 CFR 50.49 EQ requirements are not subject to aging management review (STAMR) since the components are subject to replacement based on qualified life.
3. All Waterford 3 electrical and l&C penetration assemblies are in the EQ Program (10 CFR 50.49). Waterford 3 EiC penetration assemblies in the EQ Program are not STAMR since the components are subject to replacement based on qualified life. 4. Waterford 3 fuse holders (metallic clamp) are part of an active component and are.not STAMR. 5. Waterford 3 uninsulated ground conductors limit equipment damage in the event of a circuit failure, but do not perform a license renewal intended function. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information further evaluation. From reviewing the fuses and associated drawings, a determination was made that each fuse holder was part of an active component.. Uninsulated Ground Conductors A review of the Waterford 3 FSAR did not identify a license renewal intended function for uninsulated ground conductors. These components are not safety-related and are not credited for mitigation of regulated events .. Industry and plant-specific operating experience for uninsulated ground conductors does not indicate credible failure modes that would adversely affect an intended function; therefore, credible uninsulated ground conductor failures that could prevent satisfactory accomplishment of safety functions are hypothetical. As di.scussed in Section 2.1.3.1.2 of NUREG-1800 and Section 111.c(iii) of the Statements of Consideration (60FR22467), hypothetical failures that are not part of the current licensing basis and have not been previously experienced are not required to be considered for license renewal scoping. Table 2.5-1 lists the component types that require aging management review. Table 3.6.2-1 provides the results of the aging management review. 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2.5-1 Electrical and Instrumentation and Control Systems Components Subject to Aging Management Review Structure and/or Component/Commodity Intended Function Cable connections (metallic parts) Conducts electricity Insulation material for electrical cables and connections Insulation. (electrical) (including terminal blocks, fuse holders, etc.) not subject to 10 CFR 50.49 EQ requirements Insulation material for electrical cables not subject to 10 CFR Insulation (electrical) 50.49 EQ requirements used in instrumentation circuits Fuse holders (not part of active equipment): insulation material Insulation (electrical) Fuse holders (not part of active equipment): metallic clamps Conducts electricity High voltage insulators (for SBO recovery) Insulation (electrical) Conductor insulation for inaccessible power cables (:::_ 400 V) Insulation (electrical) not subject to 10 CFR 50.49 EQ requirements Metal enclosed bus: bus/connections Conducts electricity Metal enclosed bus: enclosure assemblies Conducts electricity Metal enclosed bus: insulation/insulators Insulation (electrical) Switchyard bus and connections (for SBO recovery) Conducts electricity Transmission conductors and connectors (for SBO recovery) Conducts electricity Connector contacts for electrical connectors exposed to borated Conducts electricity water leakage 2.0 Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review and Implementation Results Page 2.5-5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.0 AGING MANAGEMENT REVIEW RESULTS This section provides the results of the aging management review (AMR) for structures and components identified in Section 2 as subject to aging management review. Tables 3.0-1, 3.0-2, and 3.0-3 provide descriptions of the mechanical, structural, and electrical service environments, respectively, used in the AM Rs to determine aging effects requiring management. Results of the AM Rs are presented in the following two table types.
Table 3.x.1 where 3 indicates the table pertaining to a Section 3 aging management review. x indicates the table number from NUREG-1800 (Ref. 3.0-1). 1 indicates that this is the first table type in Section 3.x. For example, in the reactor coolant system section, this is Table 3.1.1, and in the engineered safety features section, this is Table 3.2.1. For ease of discussion, these table types will hereafter be referred to as "Table 1." These tables are derived from the corresponding tables in NUREG-1800 and present summary information from the AM Rs.
Table 3.x.2-y where 3 indicates the application section number. x indicates the table number from NUREG-1800. 2 indicates that this is the second table type in Section 3.x. y indicates the system table number. For example, within the reactor coolant system section, the AMR results for the reactor vessel are presented in Table 3.1.2-1, and the results for the reactor vessel internals are in Table 3.1.2-2. In the engineered safety features section, the containment spray system results are presented in Table 3.2.2-1, and the safety injection system is in Table 3.2.2-2. For ease of discussion, these table types will hereafter be referred to as "Table 2." These tables present the results of the AM Rs. 3.0 Aging Management Review Results Page 3.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information TABLE DESCRIPTION Table 1 The purpose of a Table 1 is to provide a summary comparison of how the WF3 AMR results align with the corresponding table of NUREG-1800. These tables are essentially the same as Tables 3.1-1 through 3.6-1 provided in NUREG-1800 as amended by applicable Interim Staff Guidance documents, with the following exceptions.
The "ID" (identification) column is labeled "Item Number and the number has been expanded to include the table number.
The "Type" column has been deleted. Items applicable to BWRs only are noted as such.
The "Rev 2 Item" and "Rev 1 Item" columns have been replaced by a "Discussion" column. The "Item Number" column provides a means to cross-reference to Table 1 from the Table 2s. Information in the following columns of Table 1 is taken directly from NUREG-1800.
Component
Aging Effect/Mechanism
Aging Management Programs
Further Evaluation Recommended Further information is provided in the "Discussion" column. The Discussion column explains, in summary, how the WF3 evaluations align with NUREG-1800 and NUREG-1801 (Ref. 3.0-2). The following are examples of information that might be contained within this column:
Any "Further Evaluation Recommended" information or reference to the location of that information.
The name of a plant-specific program being used.
Exceptions to the NUREG-1800 and NUREG-1801 assumptions.
A discussion of how the line item is consistent with the corresponding line item in NUREG-1800, when it may not be intuitively obvious.
A discussion of how the line item is different from the corresponding line item in NUREG-1800, when it may appear to be consistent. 3.0 Aging Management Review Results Page 3.0-2 Table 2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 2s provide the results of the aging management reviews for those structures and components identified in Section 2 as being subject to aging management review. There is a Table 2 for each aging management review within a system group. For example, the engineered safety features system group contains tables specific to the containment spray system, safety
injection system, and containment penetrations. Table 2s also provide a comparison of the AMR results with the AMR results in NUREG-1801. Comparison to NUREG-1801 is performed by considering the component type, material, environment, aging effect requiring management, and aging management program (AMP) listed in each Table 2 line item to determine the degree of consistency with an appropriate NUREG-1801 line item, if one exists. The comparison is documented in columns 7, 8, and 9, as discussed below. Each Table 2 consists of the following nine columns. Component Type Column 1 identifies the component types from Section 2 of this application that are subject to aging management review, with the addition of insulated piping components. The term "piping" in component lists includes pipe and pipe fittings (such as elbows, flued heads, reducers, tees, etc.). The term "Insulated piping components" may include insulated indoor tanks with capacity less than or equal to 100,000 gallons. Intended Function Column 2 identifies the license renewal intended functions (using abbreviations* where necessary) for the listed component types. Definitions and abbreviations of intended functions are listed in Table in Section 2. Material Column 3 lists the particular materials of construction for the component type being evaluated. Environment Column 4 lists the environment to which the component types are exposed. Internal and external service environments are indicated using (int) or (ext), respectively. A description of these environments is provided in Tables 3.0-1, 3.0-2, and 3.0-3 for mechanical, structural, and electrical components, respectively. 3.0 Aging Management Review Results Page 3.0-3 Aging Effect Requiring Management Wate,rford Steam Electric Station, Unit 3 License Renewal Application Technical Information Column 5 lists the aging effeGts requiring management for material and environment combinations for each component type. Aging Management Programs (AMP) Column 6 lists the programs used to manage the aging effects requiring management. NUREG-1801 Item Each combination of the following faCtors listed in.Table 2 is compared to NUREG-1801 to identify consistencies.
Component type
Material
Environment
Aging effect requiring management
Aging management program Column 7 documents identified consistencies by noting the NUREG-1801 item number. If there is no corresponding item number in NUREG-1801 for a particular combination of factors, column 7 is left blank. . '. Comparisons of system and structure aging result!:! to NUREG-1801 items are generally within the corresponding system group and preferably within the specific system or structure. For* example, aging management results for the safety injection system will generally .
be compared to NUREG-1801 ESF system results iri Chapter V, and preferably to items in . Table V.01 for the 'emergency core cooling systems for PWRs. In _some cases where a particular aging management review result has _no valid comparison _within the system group, a comparison is outside the system group. For example, a material, environment, aging effect, and
program combint;iti_on in the safety injection system aging management result!; may have no comparable item in the ESF system results, but a match can be found in the auxiliary systems tables .. fable 1 Jtem Column 8 lists the corresponding line item from Table 1. If there is no corresponding item in NUREG-1800, then column 8 is left blank. Each combination of the following that ht;is an identified NUREG-1801 item number also has a Table 1 line item reference number.
Component type
Material 3.0 Aging Management Review Results Page 3.0-4
Environment *
Aging effect requiring management
Aging management program Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Column 9 contains notes that are used to describe the degree of consistency with the line items in NUREG-1801. Notes that use letter designations are standard notes based on Table 4.2-2 of NEI 95-10 (Ref. 3.0-3). Notes that use numeric designators are specific to the plant site. Some of the NUREG-1801 evaluations refer to plant-specific programs. In these cases, Note E is used for correlations between the combination in Table 2 ahd a combination for a line item in NUREG-1801. FURTHER EVALUATION REQUIRED The Table 1s in NUREG-1800 indicate that further evaluation is necessary for certain aging effects and other issues discussed in NUREG-1800. Section 3 includes discussions Of these issues numbered in accordance with the discussions in NUREG-1800. The discussions explain ) the site's approach to these areas requiring further evaluation. 3.0 Aging Management Review Results Page 3.0-5 REFERENCES Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.0-1 NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U. S. Nuclear Regulatory Commission, December 2010. 3.0-2 NUREG-1801, Generic Aging. Lessons Learned (GALL) Report, Revision 2, U. S. Nuclear Regulatory Commission, December 2010. 3.0-3 NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54 -The License Renewal Rule, Nuclear Energy Institute (NEI), Revision 6, June 2005. 3.0 Aging Management Review Results Page 3.0-6 Table 3.0-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor Air in an environment protected from ... Air -indoor uncontrolled precipitation. .. Air -indoor uncontrolled > 35°C (> 95°F) Air with borated water leakage Air with metal temperature up to 2aa0c (550°F) Air with reactor coolant leakage Air with steam or water leakage '-, System temperature up to 340°C (644 °F) Air .:... outdoor The outdoor environment consists of atmqspheric Air -outdoor. air, ambient temperature and humidity, and exposure to precipitation. Concrete Components in contact with concrete. Concrete. Condensation Air and condensation on surfaces bf indoor Condensation systems with temperatures below dew point; condensation is considered untreated water due to potential for surface contamination. For compressed air systems with dryers, condensation may be conservatively identified as the internal environment. Exhaust gas Gases, fluids, particulates present in diesel Diesel* exhaust engine exhaust. Fuel oil. Diesel oil, No. 2 oil, or other liquid hydrocarbons Fuel oil used to fuel diesel engines, boilers; etc. Gas Internal dry non-corrosive gas environments such Gas as nitrogen, carbon dioxide, Freon, and Halon. Lube oil Lubricating oils are low-to medium-viscosity Lubricating oil hydrocarbons used for bearing, gear, and engine lubrication. An oil analysis program may be credited to preclude water contamination. 3.0 Aging Management Review Results Page 3.0-7 Table 3.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1S01 Environment . Description Environments Neutron fluence Neutron flux integrated time. Neutron Neutron flux fluence is specified as an environment for the High fluence (> 1 *x 1021 n/cm2, limiting reactor vessel components with material E > 0.1 million electron volts properties that may be significantly affected by [MeV]) neutron irradiation. Raw water Consists of untreated surface or ground water, Raw water whether fresh, brackish, or saline in nature, or water not treated by a chemistry program such as water supplied from an off-site source for fire protection. Soil External environment for components buried .in Soil the soil; exposure to ground water is assumed in soil environments Steam Steam, subject to a water chemistry program. In Steam determining aging effects, steam is Reactor coolant treated water. Treated borated Treated 6r demineralized borated water. Treated borated water water Reactor coolant Treated borated Treated or demineralized borated water above Treated borated water > 60°C water> 140°F stress corrosion cracking (SCC) threshold for (> 140°F) ,* stainless steel. . Reactor coolant > 60°C (> 140°F) Treated borated Treated or demineralized borated water above Treated borated water > 250°C water> 482°F thermal embrittlement thi"e$hold for cast . (> 482°F). austenitic stainless steel (CASS). Reactor coolant > 250°C (> 482°F) Treated water Treated water is demineralized water and is the Treated water base water for all* clean systems.1 . Closed-cycle cooling water Secondary feedwater Raw water (potable) Treated water Treated water above the SCC threshold for Treated.water> 60°C (> 140°F) > 14Q°F stainless steel Closed-cycle cooling water > 60°C (> 140°F) 3.0 Aging Management Review Results Page 3.0-8 Table 3.0-1 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Mechanical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environment$ Waste water Water in liquid waste drains such as in liquid Waste water radioactive waste systems, oily waste systems, floor drainage systems, chemical waste water systems, and secondary waste water systems. Waste waters may contain contaminants, including oil and boric acid, as well as treated water not monitored by a chemistry program. 1. For the aging management review process, and the Table 2 presentation of review results, "treated water" encompasses a range of water types, all of which were chemically treated or demineralized. These. water types include treated water, reactor coolant, raw (potabie) water, and closed cycle cooling water as defined in NUREG-1801. In the Table 2 results, tile type of water can normally be inferred from the context of the result (e.g., if Water Chemistry Control -Closed Treated Water Systems [Section B.1.40] is the aging management program, then tile treated water is equivalent to closed cycle cooling water as defined by NUREG-1801), Where such an inference is not clear, a plant-specific note identifies the water type. . . . . For the comparison of the aging management review results with those of NUREG-1801, as presented in the last three Table 2 columns, and for the summary of results discu.ssed in Table 1, the NUREG-1801 definitions of water types were used. In other words, the "treated water" listed in the results was compared to the corresponding water type of NUREG-1801. The discussions in Table 1, and in the text sections *
referenced in Table 1 for further evaluatio!1, use the water types defined by NUREG-1801. In these discussions, "treated water refers only to water controlled by the Water Chemistry Control -Primary and Secondary Program (Section B.1.41). " *'
3.0 Aging Management Review Result$ Page 3.0-9 Table 3.0-2 Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Service Environments for Structural Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor Air with temperature less than 150°F, humidity up Air -indoor uncontrolled uncontrolled to 100 percent and protected from precipitation. The Air -indoor uncontrolled (External) environment is for indoor locations that are sheltered or protected from weather. Humidity levels up to 100 percent are assumed and the surfaces of components in this environment may be wet. This environment may contain aggressive chemical species including oxygen, halides, sulfates, or other aggressive corrosive substances that can influence the nature, rate, and severity of corrosion effects. It is assumed that these contaminants can concentrate to levels that will promote corrosive effects because of factors such as cyclic (wet-dry) condensation, contaminated insulation, accidental contamination, or leakage areas. Air -outdoor Exposed to the weather with air temperature less Air -outdoor than 115°F, humidity up to 100 percent. This . environment is subject to periodic wetting and wind. This environment may contain aggressive chemical species including chlorides, oxygen, halides, sulfates, or other aggressive corrosive substances that can influence the nature, rate, and severity of corrosion effects. Concrete This environment consists of components Concrete embedded in concrete. 3.0 Aging Management Review Results Page 3.0-10 Table 3.0-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Structural Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Exposed to fluid Fluid environment for structures at WF3 is Ground water environment defined as raw water or treated water. Treate_d "Yater
Raw water -Water from the Mississippi River Treated water> 140°F provides the source of raw water utilized at WF3. Water -flowing Raw water is also rain or ground water.* Raw water is water that has not been demineralized or Water -standing chemically treated to any significant extent. Raw water may contain contaminants. WF3 building sumps may be exposed to a variety of untreated water that is classified as raw water for the determination of aging effects. ..
Treated water -Treated water is demineralized water .or chemically purified water and is ttie base water for clean systems. Treated water could be deaerated and include corrosion inhibitors, biocides, or some combination of these treatments.
Soil External environment for co_mponents at the air/ Soil soil interface, buried in the soil, or exposed to groundwater in the soil. This environment can be "aggressive" or "non-aggressive" depending on its soil properties as defined in NUREG-1801. 3.0 Aging Management Review Results Page 3.0-11 Table 3.0-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Electrical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Air-indoor This environment is one to which the specified Air -indoor controlled controlled internal or external surface of the component or structure is exposed; a humidity-controlled (i.e., air conditioned) environment_. For electrical purposes, control must be sufficient to eliminate the 'cited aging effects of contamination and oxidation without affecting the resistance. Air-indoor Uncontrolled indoor air is associated with Air -indoor uncontrolled uncontrolled systems with temperatures higher.than the dew point (i.e., condensation can occur, but only rarely; equipment surfaces are normally dry). Air -outdoor The outdoor environment consists of moist, Air -outdoor possibly salt-laden atmospheric air, ambient temperatures and humidity, and exposure to weather, including precipitation.and wind. The component is exposed to air and local weather conditions, including salt water spray (if present). . . A component is considered susceptible to a wetted environment when it is submerged, has the potential to collect water, or is subject to external condensation. Air with borated Air and untreated borated water leakage on Air with borated water leakage water leakage indoor or outdoor systems with temperatures either above or below the dew point. The water from leakage is considered to be untreated, due to the potential for water contamination at the surface (germane to PWRs). Heat, moisture, Condition in a limited plant area that is Adverse localized environment or radiation and significantly more severe than the plant design caused by heat, radiation or air environment for the cable or connection moisture insulation materials caused by heat, radiation, or *moisture, and air. 3.0 Aging Management Review Results Page 3.0-12 Table 3.0-3 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Service Environments for Electrical Aging Management Reviews Corresponding NUREG-1801 Environment Description Environments Significant Condition in a limited plant area that is Adverse localized environment moisture significantly more severe than the plant design caused by significant moisture environment for the cable or connection insulation materials caused by significant moisture (moisture that lasts more than a few days-e.g., cable in standing water) 3.0 Aging Management Review Results Page 3.0-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1 REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM 3.1.1 Introduction This section provides the results of the aging management reviews for components in the reactor vessel, internals and reactor coolant system that are subject to aging management review. The following component groups are addressed in this section (component group descriptions are available in the referenced sections). * -* * *
Reactor Vessel (Section 2.3.1.1)
Reactor Vessel Internals (Sedtion 2.3.1.2)
Reactor Coolant Pressure Boundary (Section 2.3.1.3)
Steam *Generators (Section 2.3.1.4)
RCS systems in scope for 1 O CFR 54.4(a)(2) (Section 2.3.1.5) Table 3.1.1, Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801, provides the summary .of the programs evaluated in NUREG-1801 for the reactor co_olant system (RCS) component groups. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.1.2 Results The following tables summarize the results of aging management reviews and the NUREG-1801 comparison for the reactor vessel, internals and reactor coolant system components ..
Table 3.1.2-1 Reactor Vessel_;_Summary of Aging Management Evaluation
Table 3.1.2-2 Reactor Vessel Internals-Summary of Aging Management Evaluation
Table 3.1.2-3 Reactor Coolant Pressure Boundary-Summary of Aging Management Evaluation
Table 3.1.2-4 Steam Generators-Summary of Aging Management Evaluation RCS Systems in Scope for 10 CFR 54.4(a)(2) . ,
Table 3.1.2-5-1 Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Review
Table 3.1.2-5-2 Steam Generators, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Review 3.0 Aging Management Review Results Page 3.1-1.

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the reactor vessel, internals and reactor coolant system components. Programs are described in Appendix B. Further details are provided in Tables 3.1.2-1 through 3.1.2-5-2. 3.1.2.1.1 Reactor Vessel Materials Reactor vessel components are constructed of the following materials. Carbon steel Carbon steel clad with stainless steel High strength steel Low alloy steel

Nickel alloy Stainless steel Environments Reactor vessel components are exposed to the following environments. Air-indoor Neutron fluence Treated borated water Treated borated water > 140°F Aging Effects Requiring Management The following aging effects associated with the reactor vessel require management. Cracking Cracking -fatigue Loss of material Loss of material -wear Loss of preload Reduction of fracture toughness 3.0 Aging Management Review Results Page 3.1-2 Aging Management Programs Waterford Steam Electric Station, Unit 3 L_icense Renewal Application Technical Information The following aging management programs manage the aging effects for t_he reactor vessel components. Bolt\ng Integrity Boric Acid Corrosion lnservice Inspection Reactor Head Closure Studs Reactor Vessel Surveillance Water Chemistry Control -Primary and Secondary 3.1.2.1.2 Reactor-Vessel Internals Materials Reactor vessel internals components are constructed of the following materials. CASS Nickel alloy Stainless steel Zircaloy Environments .. Reactor vessel internals components are exposed to the following environments. Neutron fluence Treated borated water Treated borated water> 140°F Treated borated water> 482°F Aging Effects Requiring Management The following aging effects-associated with the reactor vessel internals require management. Change. in dimension*s Cracking Cracking -fatigue Loss of material Loss of material -wear Loss of preload Reduction of fracture toughness 3.0 Aging Management Review Results Page 3.1-3 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the reactor vessel internals components. Reactor Vessel Internals Water Chemistry Control -Primary and Secondary 3.1.2.1.3 Reactor Coolant Pressure Boundary Materials Reactor coolant pressure boundary components are constructed of the following materials. *
Carbon steel Carbon steel clad with nickel alloy Carbon steel clad with stainless steel CASS Copper alloy Copper alloy > 15% zinc or > 8% aluminum. High strength steel Nickel alloy Stainless steel Environments coolant pressure boundary components are exposed to the following environments. Air-indoor Lube oil Steam Treated borated water Treated borated water> 140°F Treated borated water> 482°F
Treated water Aging Effects Requiring Management The following aging effects associated with the reactor coolant pressure boundary require management. Cracking Cracking -fatigue 3.0 Aging .Management Review Results Page 3.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Loss of material Loss of preload *
Reduction of fracture toughness Aging Management Programs The following aging management programs manage the aging effects for the reactor coolant pressure boupdary components. Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring lnservice Inspection Nickel Alloy Inspection Oil Analysis One-Time Inspection One-Time Inspection -Small-Bore Piping
Selective Leaching
Thermal Aging Embrittlement of CASS Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.1.2.1.4 Steam Generators Materials Steam generator components are constructed of the following materials. Carbon steel Carbon steel clad with nickel alloy Carbon steel clad with stainless steel Nickel alloy Stainless steel Environments Steam generator components are exposed to the following environments. Air-indoor Treated borated water Treated borated water> 140°F Treated water Treated water> 140°F 3.0 Aging Management Review Results Page 3.1-5 Aging Effects Requiring Management Waterford Steam Electric Station, Unit 3 License Renewal Application Information The following aging effects associated with the steam generators require management. Cracking Cracking -fatigue Loss of material Loss of material -erosion Loss of material -FAC Loss of material -wear Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the steam generator components. Bolting Integrity Boric Acid Corrosion Flow-Accelerated Corrosion lnservice Inspection One-Time Inspection Stea.m Generator Integrity Water Chemistry Control -Primary and Secondary 3.1.2.1.5 RCS Components in Scope for 1 O CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.1.2-5-x tables. Materials Nonsafety-related components affecting safety-related systems are constructed of the following materials. *Aluminum Carbon steel Glass Stainless steel 3.0 Aging Management Review Results Page 3.1-6 Waterford Steam. Eledric station, Unit 3 License Renewal Application Technical Information Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments. Air-indoor Lube oil
Treated borated water Treated borated water> 140°F Wastewater Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. Cracking Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for related components affecting safety-related systems. *
Bolting Integrity . Boric Acid Corrosion
External Surfaces Monitoring _ . Internal Surfaces in Miscellaneous Piping and Ducting Components Oil Analysis
One-Time Inspection Periodic Surveillance and Preventive Maintenance Water Chemistry Control -Primary and Secondary 3.1.2.2 Further.Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.1.2.2 of NUREG-1800. The following sections are numbered in accordancewith the discussions in NUREG-1800 and explain the WF3 approach to these areas requiring further evaluation. Programs are described in Appendix B. 3.1.2.2.1 Cumulative Fatigue Damage. Fatigue is considered a time-limited aging analysis (TLAA) as defined in 10 CFR 54.3 for the reactor vessel, selected components of the reactor vessel internals and most 3.0 Aging Management Review Results Page 3.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information components of the reactor coolant pressure boundary including the reactor coolant pumps, pressurizer and steam generators. TLAAs are evaluated in accordance with 10 CFR 54.21 (c). The evaluation of fatigue. for the reactor vessel is discussed in Section 4.3.1.1. The evaluation of fatigue TLAAs for the ASME Class 1 portions of the reactor coolant
pressure boundary piping and components, including those for interconnecting systems, is discussed in Sections 4.3.1.3 through 4.3.1.7. 3.1.2.2.2 Loss of Material Due to General. Pitting. and Crevice Corrosion 1. Loss of material due to general, pitting, and crevice corrosion for the steel steam generator upper and lower shell and transition cone exposed to secondary feedwater and steam is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The steam generators have been replaced with Westinghouse Model Delta-110 generators. The replacement steam generators do not have the high-stress region at the shell to transition cone weld found in Model 44 and 51 generators. 2. This paragraph in NUREG-1800 pertains to plants where partial steam generator replacements have been made. The original steam generators were replaced with Westinghouse Model Delta-110 generators ... 3.1.2.2.3 Loss of Fracture Toughness due to Neutron Irradiation Embrittlement *1. Neutron irradiation embrittlement is a TLAA evaluated for the period of extended' operation in accordance with 10 CFR 54.21(c). The evaluation of loss of fracture toughness for the reactor vessel beltline shell and welds is discussed in Section . 4.2. 2. The Reactor Vessel Surveillance Program manages reduction in fracture toughness due to neutron embrittlement of reactor vessel beltline materials. This program monitors changes in the fracture toughness properties of ferritic *materials in the reactor pressure vessel (RPV) beltline region. As described.in Appendix B, the Reactor Vessel Surveillance Program is consistent with the program described in NUREG-1801, Section Xl.M31, Reactor Vessel Surveillance, including recommendations to submit the proposed withdrawal schedule for approval prior to implementation. 3. This paragraph in NUREG-1800 pertains to a plant-specific TLAA.for Babcock arid Wilcox reactor internals and is therefore not applicable to WF3. 3.0 Aging Management Review Results Page 3.1-8 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.2.4 Cracking due to Stress Corrosion Cracking CSCC) and lntergranular Stress Corrosion Cracking CIGSCC) Both paragraphs in NUREG-1800 apply to BWRs only. 3.1.2.2.5 Crack Growth due to Cyclic Loading Crack growth due to cyclic loading could occur in reactor vessel shell forgings clad with stainless steel using a high-heat-input welding process. The major portion of the reactor vessel material protected by cladding from. exposure to reactor coolant is SA-533, Grade B, Class 1 plate which, as discussed in Regulatory Guide 1.43, is immune to underclad cracking. Cladding performed on SA-508, Class 2 forging material (vessel flange, and nozzles including safe ends) uses low-heat input welding processes controlled to minimize heating of the base metal. Low-heat-input welding processes are not known to induce underclad cracking. 3.1.2.2.6 Cracking due to Stress Corrosion Cracking 1. Cracking due to sec of the non-Class 1 stainless steel reactor vessel closure head flange leak detection line will be managed by the One-Time Inspection Program. The One-Time Inspection Program will use visual or other
nondestructive examination (NOE) techniques to verify the absence of significant cracking of the line. The WF3 vessel has no bottom-mounted instrument guide tubes. 2. Cracking due to SCC of cast austenitic stainless steel Class 1 piping, piping -components, and piping elements exposed to reactor coolant'will be managed by the Water Chemistry Control -Primary and Secondary and lnservice Inspection Programs. The Water Chemistry Control -Primary and Secondary Program minimizes contaminants which promote SCC. The, lnservice Inspection Program provides qualified inspection techniques to monitor cracking. SlJsceptibility tO thermal aging embrittlement will be evaluated in the Thermal Aging Embrittlement of CASS Program. Aging management for components that are determined to be susceptible to thermal aging embrittlement is accomplished using either enhanced visual examinations or component-specific flaw tolerance evaluations. Additional inspection or evaluations are not required for components that are determined not to be* susceptible to thermal aging embrittlement. 3.1.2.2.7 Cracking due to Cyclic Loading This paragraph in NUREG-1800 applies to BWRS only. 3.0 Aging Management Review Results Page 3.1-9 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.1.2.2.8 Loss of Material due to Erosion This paragraph in pertains to loss of material due to erosion in steel steam generator feedwater impingement plates and supports. The WF3 steam generators do not have feedwater impingement plates. 3.1.2.2.9 Removed as a result ofLR-ISG-2011-04 This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.1.2.2.10 Removed as a result of LR-ISG-2011-04 This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.1.2.2.11 Cracking_ due to Primarv Water Stress Corrosion Cracking CPWSCC) 1. Foreign operating experience in steam generators with a similar,design to that of Westinghouse Model 51 has identified extensive cracking due to primary water stress corrosion cracking (PWSCC) in steam generator divider plate assemblies fabricated of Alloy 600 and/or the associated Alloy 600 weld materials. The divider plate assemblies and the associa.ted welds oflhe WF3 replacement steam generators use Alloy 600 materials in limited applications and none is exposed to reactor coolant. The primary head is clad with stainless steel with the exception of areas near junctions with the tubesheet and partition plate which are clad with Alloy 690. The partition plate is composed of Alloy 690 and the tubesheet is clad with Alloy 690. WF3 replacement steam generators (RSGs) use Alloy 600 as a

cladding buffer between the channel head and the Alloy 690 weld build-up in the area of the partition plate. The area under the partition plate is filled with Alloy 600 with weld build-up of Alloy 690 over the Alloy 600. Also, a zone approximately 14.50 inches wide centered on the tubesheet 90°-270° axis is buttered with Alloy 600 and followed by subsequent layers of Alloy 690 filler metal. All nickel alloy in contact with primary coolant is Alloy 690. 2. Cracking due to PWSCC could occur in steam generator nickel alloy tube-to-* tubesheet welds exposed to reactor coolant. The WF3 replacement steam generators use Alloy 690 steam generator tubes with Alloy 690 tubesheet cladding. Cracking of nickel alloy tube to tubesheet welds is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. 3.1.2.2.12 Removed as a result of LR-ISG-2011-04 . This paragraph was removed from NUREG-1800 by LR-ISG-2011-04. 3.0 Aging Management Review Results Page 3.1-10 3.1.2.2.13 Removed as a result of LR-ISG-2011-04 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This paragraph was removed from._NUREG-1.800 by LR-ISG-2011-04. 3.1.2.2.14 Removed as a result of LR-ISG-2011:.04 This paragraph was removed from NUREG-1_800 by LR-ISG-2011-04. 3.1.2.2.15 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section B.0:3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3. 1.2.2.16 Ongoing Review of Operating Experience See Appendix B Section B.0.4 for discussion *of WF3 operating experience review .programs. Time-Limited Aging Analyses TLAAs identified for the reactor coolant syster:n include reactor vessel neutron embrittlement and metal fatigue. These topics are addressed in Section 4. * ' 3.1.3 Conclusion The vessel, internals and reactor coolant system components that are subject to aging management review havebe_en identified in accordance with the-requirements of 1OCFR54.21. The aging management programs selected to manage the aging *effects for the reactor vessel, internals anq reactor coolant system components are identified in Section 3.1.2: 1 and in the following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of *extended operation . . Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the reactor vessel, internals and reactor coolant system components will *be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the currehtlicensing basis during the period of extended operation. 3.0 Aging Management Review Results . Page3.1-11 Table 3.1.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Further Evaluation Number Component Mechanism Programs Recommended Discussion 3.1.1-1 High strength, low-alloy Cumulative fatigue Fatigue is a TLAA, Yes, TLAA Fatigue is a TLAA. steel top head closure damage due to fatigue evaluated for the period See Section 3.1.2.2.1. stud assembly exposed to of extended operation air with potential for (See SRP, Sec 4.3 reactor coolant leakage "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) 3.1.1-2 Nickel alloy tubes and Cumulative fatigue Fatigue is a TLAA Yes, TLAA Fatigue is a TLAA. sleeves exposed to damage due to fatigue evaluated for the period See Section 3.1.2.2.1. reactor coolant and of extended operation secondary feedwater/ (See SRP, Sec 4.3 steam "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1)) 3.1.1-3 Stainless steel or nickel Cumulative fatigue Fatigue is a TLAA, Yes, TLAA Fatigue is a TLAA. alloy reactor vessel damage due to fatigue evaluated for the period See Section 3.1.2.2.1. internal components of extended operation exposed to reactor (See SRP, Section 4.3 coolant and neutron flux "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) 3.0 Aging Management Review Results Page 3.1-12 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-4 Steel pressure vessel Cumulative fatigue support skirt and damage due to fatigue attachment welds 3.1.1-5 Steel, stainless steel, or Cumulative fatigue steel (with stainless steel damage due to fatigue or nickel alloy cladding) steam generator components, pressurizer relief tank components or piping components or bolting 3.1.1-6 BWRonly 3.1.1-7 BWRonly 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA, evaluated for the period of extended operation (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) Fatigue is a TLAA evaluated for the period of extended operation (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1 )) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA The WF3 reactor vessel does not use a support skirt. Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Page 3.1-13 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-8 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), or stainless steel; or nickel alloy steam generator components exposed to reactor coolant 3.1.1-9 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), stainless steel; nickel alloy RCPB piping; flanges; nozzles & safe ends; pressurizer shell heads & welds; heater sheaths & sleeves; penetrations; thermal sleeves exposed to reactor coolant 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA evalu!'lted for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 1 O CFR 54.21 (c)(1 )) Fatigue is a TLAA evaluated for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 1 O CFR 54.21(c)(1)) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Fatigue is a TLAA. Section 3.1.2.2.1. Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Page 3.1-14 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-10 Steel (with or without Cumulative fatigue nickel-alloy or stainless damage due to fatigue steel cladding), stainless steel; nickel alloy reactor vessel flanges; nozzles; penetrations; pressure housings; safe ends; thermal sleeves; vessel shells, heads and welds exposed to reactor coolant 3.1.1-11 BWR only 3.1.1-12 Steel steam generator Loss of material due to components: upper and general, pitting, and lower shells, transition crevice corrosion cone; new transition cone closure weld exposed to secondary feedwater or steam 3.0 Aging Management Review Results Aging Management Programs Fatigue is a TLAA evaluated for the period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21(c)(1)) Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD," and Chapter Xl.M2, "Water Chemistry," and, for Westinghouse Model 44 and 51 SIG, if corrosion of the shell is found, additional inspection procedures are developed Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Fatigue is a TLAA. See Section 3.1.2.2.1. Yes, detection of Consistent with NUREG-1801. aging effects is _to be Loss of material for steam evaluated generator head, shell and transition cone components exposed to secondary feedwater or steam is managed by the I nservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The WF3 replacement steam generators are Westinghouse Model Delta-110. See Section 3.1.2.2.2, Items 1 and 2 Page 3.1-15 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-13 Steel (with or without Loss of fracture stainless steel cladding) toughness due to reactor vessel beltline neutron irradiation shell, nozzles, and welds embrittlement exposed to reactor coolant and neutron flux 3.1.1-14 Steel (with or without Loss of fracture cladding) reactor vessel toughness due to beltline shell, nozzles, and neutron irradiation welds; safety injection embrittlement nozzles 3.1.1-15 Stainless steel Babcock & Reduction of ductility and Wilcox (including CASS, fracture toughness due martensitic SS, and PH to neutron irradiation SS) and nickel alloy embrittlement, and for reactor vessel internal CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement 3.1.1-16 BWR only 3.1.1-17 BWR only 3.0 Aging Management Review Results Aging Management Programs TLAA is to be evaluated in accordance with Appendix G of 10 CFR Part 50 and RG 1.99. The applicant may choose to demonstrate that the materials of the nozzles are not controlling for the TLAA evaluations Chapter Xl.M31, "Reactor Vessel Surveillance" Ductility -Reduction in fracture toughness is a TLAA to be evaluated for the period of extended operation. See the SRP, Section 4.7, "Other Plant-Specific TLAAs," for acceptable methods of meeting the requirements of 10 CFR 54.21 (c). Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, TLAA Neutron irradiation embrittlement is a TLAA. See Section 3.1.2.2.3, Item 1. Yes, plant specific or Consistent with NUREG-1801. integrated The Reactor Vessel surveillance program Surveillance Program will manage loss of fracture toughness of the recictor vessel beltline materials. See Section 3.1.2.2.3 Item 2. Yes, TLAA The WF3 reactor vessel internals were designed by Combustion Engineering. See Section 3.1.2.2.3, Item 3. Page 3.1-16 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-18 Reactorvessel shell Crack growth due to fabricated of SA508-CI 2 cyclic loading forgings clad with stainless steel using a high-heat-input welding process exposed to reactor coolant 3.1.1-19 Stainless steel reactor Cracking due to stress vessel closure head corrosion cracking
flange leak detection line and bottom-mounted instrument guide tubes (external to reactor vessel) 3.0 Aging Management Review Results Aging Management . Programs Growth of intergranular separations is a TLAA evaluated for the period of extended operation. The Standard Review Plan, Section 4.7, Plant-Specific Time-Limited Aging Analysis," provides guidance for ** meeting the requirements of 10 CFR 54.21 (c). A plant-specific aging management program is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion . Yes, TLAA Most reactor vessel material protected by cladding is SA-533, Grade B, Class 1 plate. Cladding performed on SA-508, Class 2 forging material (vessel flange, and nozzles including safe ends) used low-heat.input welding processes. See Section 3.1.2.2.5. Yes, plant-specific Cracking of the stainless steel reactor vessel closure head \ flange leak detection line will be managed by the One-Time Inspection Program. The WF3 reactor vessel has no bottom-mounted instrument guide tubes. See Section 3.1.2.2.6, Item 1. Page 3.1-17 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-20 Cast austenitic stainless Cracking due to stress Chapter Xl.M2, "Water steel Class 1 piping, corrosion cracking Chemistry" and, for piping components, and CASS components that piping elements exposed do not meet the NUREG-to reactor coolant 0313 guidelines, a plant specific aging management program 3.1.1-21 BWR only 3.1.1-22 Steel steam generator Loss ofmaterial due to A plant-specific aging feedwater impingement erosion management program is plate and support exposed to be evaluated to secondary feedwater 3.1.1-23 [There is no 3.1.1-23 in NUREG-1800 as modified by the ISGs.] 3.1.1-24 [There is no 3.1.1-24 in NUREG-1800 as modified by the ISGs.] 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific Cracking of cast austenitic stainless steel Class 1 piping, piping components, and piping elements exposed to reactor coolant will be managed by the lnservice Inspection, Thermal Aging Embrittlement of CASS and Water Chemistry Control -Primary and Secondary Programs. See Section 3.1.2:2.6, Item 2. Yes, plant-specific The WF3 steam generators do not have steel steam generator feedwater impingement plates. See Section 3.1.2.2.8. Page 3.1-18 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-25 Steel (with nickel-alloy Cracking due to primary Chapter Xl.M2, "Water cladding) or nickel alloy water stress corrosion Chemistry" steam generator primary cracking side components: divider plate and tube-to-tube sheet welds exposed to reactor coolant .. 3.1.1-26 [There is no 3.1.1-26 in NUREG-1800 as modified by the ISGs.] 3.1.1-27 [There is no 3.1.1-27 in NUREG-1800 as modified by the ISGs.] 3.1.1-28 Stainless steel Loss of material due to Chapter Xl.M16A, "PWR Combustion Engineering wear; cracking due to Vessel Internals," and "Existing Programs" stress-corrosion Chapter Xl.M2, "Water components exposed to cracking, irradiation-Chemistry" (for SCC reactor coolant and assisted stress-mechanisms only) neutron flux corrosion cracking, or fatigue 3.1.1-29 BWRonly 3.1.1-30 BWRonly 3.1.1-31 BWRonly 3.0 Aging Management Review Results / -Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific Cracking of nickel alloy tube to tubesheet welds is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. Cracking of the nickel alloy (Alloy 690) steam generator primary side divider plate exposed to reactor coolant is managed by the Water Chemistry Control -Primary and Secondary Program. See Section 3.1.2.2.11, Items 1and2 No The WF3 reactor vessel internals design does not include thermal shield positioning pins. Page 3.1-19 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-32 Stainless steel, nickel Cracking, or loss of alloy, or CASS reactor material due to wear vessel internals, core support structure (not already referenced as ASME Section XI Examination Category 8-N-3 core support structure components in MRP-227-A}, exposed to reactor coolant and neutron flux 3.1.1-33 Stainless steel, steel with Cracking due to stress stainless steel cladding corrosion cracking Class 1 reactor coolant pressure boundary components exposed to reactor coolant 3.1.1-34 Stainless steel, steel with Cracking due to stress stainless steel cladding corrosion cracking pressurizer relief tank (tank shell and heads, flanges, nozzles) exposed to treated borated water >60°C {>140°F) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" or Chapter Xl.M16A, "PWR Vessel Internals," invoking applicable 10 CFR 50.55a and ASME Section XI inservice inspection requirements for these components Chapter Xl.M1, "ASME Section XI lnservicei Inspection, Subsections IWB, IWC, and IWD" for ASME components, and Chapter Xl:M2, "Water Chemistry" Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for ASME components, and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Cracking and loss of material due to wear of the reactor vessel internals core support structure components is managed by the Reactor Vessel Internals Program which uses ASME Section XI lnservice Inspection, Subsection IWB as required. These AMR results are compared to other table items (3.1.1-52a, 3.1..1-52b, 3.1.1-52c, 3.1.1-55b and 3.1.1-56c). No Consistent with NUREG-1801. Cracking of stainless steel reactor coolant pressure boundary components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. No The nonsafety-related relief tank is not subject to ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD. Page 3.1-20 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-35 Stainless steel, steel with Cracking due to cyclic stainless steel cladding loading reactor coolant system cold leg, hot leg, surge line, and spray line piping and fittings exposed to reactor coolant 3.1.1-36 Steel, stainless steel Cracking due to cyclic pressurizer integral loading support exposed to air with metal temperature up . to 288°C (550°F) 3.1.1-37 Steel reactor vessel flange Loss of material due to wear 3.1.1-38 Cast austenitic stainless Loss of fracture steel Class 1 pump toughness due to thermal ca,sings, and valve bodies aging embrittlement and bonnets exposed to reactor coolant >250 deg-C (>482 deg-F) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components Chapter Xl.M1, "ASME Section XI Inspection, Subsections IWB, IWC, arid IWD" for Class 1 components Chapt.er Xl.M1, "ASME , Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD".for Class 1 components. For pump casings and valve bodies, screening for susceptibility to thermal aging is not necessary. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No with NUREG-1801. Cracking of Class 1 reactor coolant piping is managed by the lnseivice Inspection Program. No Consistent with NUREG-1801. Cracking of the pressurizer support skirt is managed by
the lnservice Inspection Program. No Consistent with NUREG-1801. Loss. of material due to wear, of the vessel flange is managed by the lnservice Inspection Program .. No . Consistent with NUREG-1801. The lnservice Inspection Program manages the reduction of fracture toughness in cast austenitic stainless ste'el pump casings and valve bodies in the reactor coolant pressure boundary. Page 3.1-21 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-39 Steel, stainless steel, or Cracking due to stress steel with stainless steel corro.sion cracking, cladding Class 1 piping, intergranular stress fittings and branch corrosion cracking (for connections < NPS 4 stainless steel only), and exposed to reactor thermal, mechanical, and coolant vibratory loading .. 3.1.1-40 Steel with stainless steel* Cracking due to cyclic or nickel alloy cladding; or loading stainless steel pressurizer components exposed to reactor coolant . 3.1.1-40.5 Nickel alloy core support Cracking due to primary pads;. core guide lugs water stress corrosion exposed tp reactor coolant cracking 3.0 Aging Management Review Results Aging Management Programs . Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, Chapter Xl.1\112, "Water Chemistry," and Xl.M35, "One-Time Inspection of ASME Code Class 1 Small-bore Piping" . Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M1, "ASME Section XI lnservice
Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Cracking in stainless steel components of the reactor coolant pressure boundary exposed to reactor coolant is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs .. The One-Time Inspection -Small-Bore Piping Program will verify the effectiveness of the water chemistry program and will manage cracking in piping and fittings < 4" NPS. No Consistent with NUREG-1801. Cracking of Class 1 pressurizer components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking of nickel alloy vessel internal attachments is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Page 3.1-22 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-41 BWRonly 3.1.1-42 Steel with stainless steel Cracking due to stress or nickel alloy cladding or corrosion cracking; stainless steel primary primary water stress side components; steam corrosion cracking generator upper and lower heads, and tube sheet weld; or pressurizer components exposed to reactor coolant 3.1.1-43 BWRonly 3.1.1-44 Steel steam generator Loss of material due to secondary manways and erosion handholes (cover only) exposed to air with leak.ing secondary-side water and/ or steam -, 3.0 Aging Management Review Results / Aging Management Programs Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 1 components, and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M1, "ASME
Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" for Class 2 components Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of steel with stainless steel or nickel alloy cladding and stainless steel pressurizer components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. WF3 uses recirculating steam generators. No Consistent with NUREG-1801 for manways and handholes without seal welded diaphragms. The lnservice Inspection Program manages loss of material due to erosion for steel secondary side steam generator manway and handhole covers. Page 3.1-23 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.1.1-45 Nickel alloy and steel with Cracking due to primary Chapter Xl.M1, "ASME nickel-alloy cladding water stress corrosion Section XI ISi, IWB, IWC reactor coolant pressure cracking & IWD," and Chapter boundary components Xl.M2, "Water exposed to reactor coolant Chemistry," and, for nickel-alloy, Chapter Xl.M118, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced Corrosion in RCPB Components (PWRs Only)" 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for nickel alloy (Alloy 600) components. Cracking of nickel alloy (Alloy 600) components is managed by the lnservice Inspection, Nickel Alloy Inspection and Water Chemistry Control -Primary and Secondary Programs. For other nickel alloy (Alloy 690) components, cracking is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Loss of material due to boric acid corrosion in steel external surfaces near nickel alloy (Alloy 600) pressure boundary components is addressed in Item 3.1.1-48. Page 3.1-24 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-46 Stainless steel, nickel-Cracking due to stress alloy, riickel-alloy welds corrosion cracking, and/or buttering control primary water stress rod drive head penetration corrosion cracking pressure housing or nozzles safe ends and welds (inlet, outlet, safety injection) exposed to. reactor coolant 3.1.1-47 Stainless steel, nickel-Cracking due to stress alloy control rod drive corrosion cracking, head penetration pressure primary water stress housing exposed to corrosion cracking reactor coolant 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M1, "ASME Section XI ISi, IWB, IWC & IWD," and Chapter Xl.M2, "Water Chemistry," and, for nickel-alloy, Chapter Xl.M11 B, "Cracking of
Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced* corrosion in RCPB Components (PWRs Only)" Chapter Xl.M1, "ASME Section XI ISi, IWB, IWC & IWD," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended -Discussion No_ The control element drive mechanism (CEDM) motor housing lower end fitting is composed of Alloy 690. Cracking of this component is managed.by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. The reactor vessel safe ends are carbon steel clad with stainless steel and are compared to Item 3 .1.1-33. No Consistent with NUREG-1801. Cracking of the stainless CEDM motor housing components is managed by the lnservice Inspection and Water Chemistry Control -Primary and Secondary Programs. Nickel alloy components are compared to Item 3.1.1-46. Page 3.1-25 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-48 Steel external surfaces: Loss of material due to reactor vessel top head, boric acid corrosion reactor vessel bottom head, reactor coolant pressure boundary piping or components adjacent to dissimilar metal (Alloy 82/ 182) welds exposed to air with borated water leakage 3.1.1-49 .Steel reactor coolant Loss of material due to pressure boundary boric acid corrosion external surfaces or closure bolting exposed to a!r with borated water leakage 3.1.1-50 Cast austenitic stainless Loss of fracture steel Class 1 piping, toughness due to thermal piping component, and aging embrittlement piping elements and control rod drive pressure housings exposed to reactor coolant >250 deg-C (>482 deg-F) 3.0 Aging Management Review Result!? Aging Management Programs Chapter Xl.M10, "Boric Acid Corrosion," and Chapter Xl.M11 B, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in RCPB Components (PWRs Only)" . Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M12, * "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)" .. " *. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Loss of material due to boric acid corrosion in steel external surfaces near nickel alloy (Alloy 600) pressure boundary components, is managed by. the Boric Acid Corrosion and Nickel Alloy Inspection Programs. No Consistent with NUREG-1801. Loss of material due to boric acid corrosion in steel components is managed by the Boric Acid Corrosion Program. No Consistentwith NUREG-1801. Loss of fracture toughness in CASS components is managed by the Thermal Aging Embrittlement of CASS Program. Page 3. 1-26.

Table 3.1.1 : Reactor Coolant Item " Aging Effect/ Number Component Mechanism 3.1.1-51a Stainless steel or nickel Cracking (jue to stress alloy Babcock & Wilcox corrosion cracking, reactor internal "Pr.imary" irradiation-assisted components exposed to

stress corrosion reactor coolant and . . cracking, *or fatigue neutron flux 3.1.1-51b Stainless steel or nickel Cracking due to stress alloy Babcock *& Wilcox. corrosion cracking, reacfor internal
irradiation-assisted "Expansion" components stress corrosion exposed to reactor cracking, fatigue, or coolant and neutron flux overload 3.1.1-52a Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering ,reactor '*irradiation-assisted intern;al "Primary" stress corrosion components exposed to . cracking, or fatigue reactor coolarit and neutron flux '* 3.p Agirig Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals,. and . Chapter Xl.M2, "Water Chemistry" (for SCC * , mechanisms only) ... Chapter Xl.M16A, "PWR *. Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and . Chapter Xl.M2, ."Water Chemistr-Y" (for SCC mechani.sms only) .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801 for stainless steel "Primary" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Contra! -Primary a.nd Secondary Programs.
There are no nickel alloy "Primary" internals components. Page 3.1-27
Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-52b Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering reactor irradiation-assisted internal "Expansion" stress corrosion components exposed to cracking, or fatigue reactor coolant and . neutron flux 3.1.1-52c Stainless steel or nickel Cracking due to stress alloy Combustion corrosion cracking, Engineering reactor irradiation-assisted internal "Existing stress corrosion Programs" components cracking, or fatigue exposed to reactor coolant and neutron flux 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Expansion" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Control -Primary and Secondary Programs. There are no nickel alloy "Expansion" internals components. No Consistent with NUREG-1801 for stainless steel "Existing Programs" components. Cracking of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals and Water Chemistry Control -Primary and Secondary Programs. There are no nickel alloy "Existing Programs" internals components. Page 3.1-28 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-53a . Stainless steel or nickel Cracking due to stress alloy Westinghouse corrosion cracking, reactor internal "Primary" irradiation-assisted components exposed to stress corrosion reactor coolant and cracking, or fatigue neutron flux 3.1.1-53b Stainless steel Cracking due to stress Westinghouse reactor corrosion cracking, internal "Expansion" irradiation-assisted components exposed to stress corrosion reactor coolant and cracking, or fatigue flux 3.1.1-53c Stainless steel or nickel Cracking due to stress alloy Westinghouse corrosion cracking, reactor internal "Existing irradiation-assisted Programs" components stress corrosion exposed to reactor cracking, or fatigue coolant and neutron flux 3.1.1-54 Stainless steel bottom Loss of material due to mounted instrument wear system flux thimble tubes (with or without chrome plating) exposed to reactor coolant and neutron flux Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," and Chapter Xl.M2, "Water Chemistry" (for SCC mechanisms only) Chapter Xl.M16A, "PWR Vessel Internals," or Chapter Xl.M37, "Flux Thimble Tube Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation -Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. No The Combustion Engineering designed reactor vessel does not use bottom mounted instrument system flux thimble tubes. 3.0 Aging Management Review Results Page 3.1-29 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-55a Stainless steel or nickel No additional aging alloy Babcock and Wilcox management for reactor reactor internal "No internal "No Additional Additional Measures" Measures" components components exposed to unless required by ASME reactor coolant and Section XI, Examination neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A. 3.1.1-55b Stainless steel or nickel No additional aging alloy Combustion management for reactor Engineering reactor internal "No Additional internal "No Additional Measures" components Measures" components unless required by ASME exposed to reactor Section XI, Examination coolant and neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A. 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801 for stainless steel or nickel alloy "No Additional Measures" components. The Reactor Vessel Internals Program manages aging effects for these components. The Water Chemistry Control -Primary and Secondary Program supplements the Reactor Vessel Internals Program for the prevention of stress corrosion cracking. Page 3.1-30 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component
Mechanism 3.1.1-55c Stainless steel or nickel No additional aging alloy Westinghouse. management for reactor reactor internal "No internal "No Additional . Additional Measures" Measures" components components exposed to unless required by ASME
reactor coolant and Section XI, Examination neutron flux Category B-N-3 or relevant operating experience invalidates MRP-227-A'. 3.1.1-56a Stainless steel (SS, Loss of fracture including CASS, PH SS or. toughness due to martensitic SS) or nickel neutron irradiation alloy Combustion embrittlement and for Engineering reactor CASS, martensitic SS, internal "Primary" and PH SS due to components exposed to
thermal aging reactor coolant and embrittlement; or neutron flux changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss o,f material. due to wear ' ' 3.0 Aging Management Review Results ( Aging Management Programs Chapter Xl.M16A, "P.WR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No Consistent with NUREG-1801
for stainless steel "Primary" components. Reduction of fracture toughness and changes in dimension of stainless steel reactor vessel internals components are . managed by the Reactor Vessel Internals Program. There are no nickel alloy "Primary" internals components. Page 3.1-31 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-56b Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) neutron irradiation Combustion Engineering embrittlement and for "Expansion" reactor CASS, martensitic SS, internal components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Expansion" components. Reduction of fracture toughness and changes in dimension of stainless steel reactor vessel internals components is managed by the Reactor Vessel Internals Program. Page 3.1-32 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-56c Stainless steel (SS, Loss offracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Combustion embrittlement and for Engineering reactor CASS, martensitic SS, internal "Existing and PH SS due to Programs" components thermal aging exposed to reactor embrittlement; or coolant and neutron flux changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.1.1-57 [There is no 3.1.1-57 in NUREG-1800.] 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" ,---Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for stainless steel "Existing" components. Reduction of fracture toughness, loss of preload and loss of material due to wear of stainless steel and Zircaloy reactor vessel internals components is managed by the Reactor Vessel Internals Program. There are no nickel alloy "Existing" internals components. Page 3.1-33 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-58a Stainless steel (SS, Loss offracture including CASS, PH SS or toughness due to martensitic SS) or nickel
neutron irradiation alloy Babcock & Wilcox embrittlement and for reactor internal "Primary" CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to wear; or loss of material due to wear 3.1.1-58b Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Babcock & Wilcox embrittlement and for reactor internal CASS, martensitic SS, "Expansion" components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. No The WF3 reactor vessel internals were designed by Combustion Engineering. Page 3.1-34 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechariism 3.1.1-59a Stainless steel (SS, Loss of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Westinghouse embrittlement and for reactor. internal "Primary" CASS, martensific SS, components exposed to . and PH SS due to reactor coolant and thermal aging
neutron. flux
embrittlement; or changes in oimensions due _to void swelli'ng or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material. due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" " Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. ' Page 3.1-35

. Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-59b Stainless steel (SS,

Loss of fracture including CASS, PH SS or toughness due to martensitic SS) neutron irradiation Westinghouse reactor embrittlement and for internal "Expansion" CASS, martensitic SS, components exposed to and PH SS due to reactor coolant and thermal aging neutron flux embrittlement; or ' changes in dimensions . due to void swelling or distortion; or loss of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information. Further Evaluation Recommended Discussion No The WF3 reactor vessel internals were designed by Combustion Engineering. Page 3.1-36 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-59c Stainless steel (SS, Loss -of fracture including CASS, PH SS or toughness due to martensitic SS) or nickel neutron irradiation alloy Westinghouse embrittlement and for reactor internal "Existing CASS, martensitic SS, Programs" components and PH SS due to exposed to reactor thermal aging coolant and neutron flux embrittlement; or changes in dimensions due to void swelling or . distortion; or los*s of preload due to thermal and irradiation enhanced stress relaxation or creep; or loss of material due to wear 3.1.1-60 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M16A, "PWR Vessel Internals" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The WF3 reactOr vessel internals were designed by Combustion Engineering. Page 3.1-37 Table 3.1.1: Reactor Coolant Systein Item Aging Effect/ Number Component Mechanism 3.1.1-61 Steel steam generator Wall thinning due to flow-steam nozzle and safe accelerated corrosion end, feedwater nozzle and safe end, AFW nozzles and safe ends exposed to secondary feedwater/ steam 3.1.1-62 High-strength, low alloy Cracking due to stress steel, or stainless steel corrosion cracking closure bolting; stainless steel control rod drive head penetration flange bolting exposed to air with reactor coolant leakage 3.1.1-63 BWRonly 3.1.1-64 Steel closure bolting Loss of material due to exposed to air -indoor general, pitting, and uncontrolled crevice corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M17, "Flow-Accelerated Corrosion" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for the steam generator blowdown nozzles. The Flow-Accelerated Corrosion Program manages loss of material due to FAC for these nozzles. The steam generator outlet nozzles use nickel alloy flow inserts which protects the steel nozzle from flow accelerated corrosion (FAC). The feedwater nozzles contain a nickel alloy thermal sleeve that isolates the carbon steel nozzle from feedwater flow, so the feedwater nozzles are not susceptible .to FAC. No Consistent with NUREG-1801. Cracking of stainless steel and high-strength steel bolting is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Loss of material for steel closure bolting is managed by the Bolting Integrity Program. Page 3.1-38 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism .3.1.1-65 Stainless steel control rod Loss of material due to drive head penetration wear flange bolting exposed to air with reactor coolant leakage 3.1.1-66 IC?W alloy Loss of preload due to steel, or stainless steel thermal effects.gasket ' closure bolting; stainless creep, and self-steel control rod drive loosening head penetration flange ; bolting exposed to air with ; reactor coolant leakage 3.1.1-67 Steel or stainless steel Loss of preload due to closure bolting exposed to thermal effects, gasket air ""'" indoor with potential creep, and * . for reactor coolant leakage 3.1.1-68 Nickel alloy steam
qhanges in dimension generator tubes exposed ("denting") due to
to secondary feedwater or corrosion of carbon steel . steam* . tube support plate 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Boltin!;J Integrity" Chapter Xl.M18, "Bolting Integrity"_ ; Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water C.hemistry" Waterford Steam Electric Station, Unit 3 License Renewal*.Application . Technical* Information Further Evaluation Recommended Discussion No WF3 does not use bolting for the control rod drive head *.* penetration flange .. No . Consistentwith NUREG-1801. Loss of preload for steel, high-strength steel and stainless steel closure bolting is managed by the 1;3olting Integrity Program. No Consistent with NUREG-1801. Loss of preload for steel closure bolting is managed by the Bolting Integrity Program. Loss:of preload for stainless . steel closure bolting is compared to Item 3.1.1-66. No The WF3 replacement steam generators do not use carbon steel tube support plates. Page 3.1-39 Table 3.1.1 : Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-69 Nickel alloy steam Cracking due to outer generator tubes and diameter stress corrosion sleeves exposed to cracking and secondary feedwater or intergranular attack steam 3.1.1-70 Nickel alloy steam Cracking due to primary generator tubes, repair water stress corrosion sleeves, and tube plugs cracking exposed to reactor coolant 3.1.1-71 Steel, chrome plated Cracking due to stress steel, stainless steel, corrosion cracking or nickel alloy steam other mechanism(s); loss generator U-bend of material due general supports including anti-(steel only), pitting, and vibration bars exposed to crevice corrosion secondary feedwater, or steam 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam, Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter ,XlM2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Cracking of nickel alloy steam generator components is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking of nickel alloy steam generator components is managed by the Steam Generator Integrity and Water -Chemistry Control -Primary and Secondary Programs. No Consistent with NUREG-1801. Cracking and loss of material for steam generator tube support components is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. Page 3.1-40 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-72 Steel steam generator Loss of material due to tube support plate, tube erosion, general, pitting, bundle wrapper, supports and crevice corrosion, and mounting hardware ligament cracking due to exposed to secondary. corrosion feedwater or steam -* . 3.1.1-73 Nickel alloy steam Loss of material due to generator tubes and wastage and pitting sleeves exposed to . corrosion phosphate chemistry in secondary feedwater or steam 3.1.1-74 Steel steam generator Wall thinning due to flow-upper assembly and accelerated corrosion separators including feedwater inlet ring and support exposed to secondary feedwater or steam 3.1.1-75 Steel steam generator Wall thinning due to flow-tube support lattice bars accelerated corrosion exposed to secondary and general corrosion feedwater or steam 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Chapter Xl.M19, "Steam Generators," and Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information I Further Evaluation
Recommended Discussion No Consistent with NUREG-1801. Loss of material for carbon steel steam generator support
components exposed to secondary feedwater or steam is managed by the Steam Generator Integrity and Water Chemistry Control -Primary and Secondary Programs. The WF3 replacement steam generators do not use carbon
steel tube support plates. No ' WF3 does not use phosphate chemistry in the secondary feedwater. No The WF3 replacement steam generator steel feedwater piping components are composed of alloy steel (Cr-* Mo) which is.resistant to FAC. No The WF3 replacement steam generators do not use carbon steel tube support lattice bars. Page 3.1-41 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-76 Steel, chrome plated Loss of material due to steel, stainless steel, fretting nickel alloy steam generator U-bend supports including anti-vibration bars exposed to secondary feedwater or steam 3.1.1-77 Nickel alloy steam Loss of material due to generator tubes and wear and fretting sleeves exposed to secondary feedwater or steam 3.1.1-78 Nickel alloy steam Cracking due to stress generator components corrosion cracking such as, secondary side nozzles (vent, drain, and instrumentation) exposed to secondary feedwater or steam 3.1.1-79 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M19, "Steam Generators" Chapter Xl.M19, "Steam Generators" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection," or Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD." Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to fretting (wear) for steel, stainless steel and nickel alloy steam generator tube support components is managed by the Steam Generator Integrity Program. No Consistentwith NUREG-1801. Loss of material due to fretting (wear) nickel alloy steam generator tubes is managed by the Steam Generator Integrity Program. No Consistent with NUREG-1801. Cracking of nickel alloy steam generator components exposed to secondary feedwater or steam is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-42 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-80 Stainless steel or steel Cracking due to stress with stainless steel corrosion cracking cladding pressurizer relief
tank: tank shell and heads, flanges, nozzles (none-ASME Section XI components) exposed to treated borated water >60°C (>140°F) 3.1.1-81 Stainless steel pressurizer Cracking due to stress spray head exposed to corrosion* cracking reactor coolant 3.1.1-82 Nickel alloy pressurizer Cracking due to stress spray head exposed to corrosion cracking, reactor coolant primary water stress corrosi.on cracking 3.0 Aging Management Review Resuits Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" ' Chapter Xl.M2, "Water Chemistry," and Chapter XLM32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information *Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless s.teel non-Class 1 components is managed by the Water Chemistry Control ...,. Primary and Secondary Program. The One-Time Inspection Program . will the effectiveness of the water chemistry program. No The pressurizer spray head components are made of nickel alloy. No
ConsistentwithNUREG-1801. Cracking of nickel alloy spray head components is managed by tlie Water Chemistry
Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-43 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-83 Steel steam generator Loss of material due to shell assembly exposed to general, pitting, and secondary feedwater or crevice corrosion steam 3.1.1-84 BWRonly 3.1.1-85 BWRonly 3.1.1-86 Stainless steel steam Cracking due to stress generator primary side corrosion cracking divider plate exposed to reactor coolant 3.1.1-87 Stainless steel or nickel-Loss of material due to alloy PWR reactor internal pitting and crevice components exposed to corrosion reactor coolant and neutron flux 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry" Chapter Xl.M2, "Water Chemistry" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistentwith NUREG-1801. Loss of material of steel steam generator components exposed to secondary feedwater or steam is managed by the Water Chemistry Control -Primary and Secof1dary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No The steam generator primary side divider plate is made of nickel alloy (Alloy 690). No Consistentwith NUREG-1801. Loss of material of stainless steel or nickel alloy reactor vessel internal components is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.1-44 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-88 Stainless steel; steel with Loss of material due to nickel-alloy or stainless pitting and crevice steel cladding; and nickel-corrosion alloy reactor coolant pressure boundary components exposed to reactor coolant . 3.1.1-89 Steel piping, piping Loss of material due to components, and piping general, pitting, and elements exposed to crevice corrosion closed cycle cooling water 3.1.1-90 Copper alloy piping, piping Loss of material due to components, and piping pitting, crevice, and elements exposed to galvanic corrosion closed cycle cooling water 3.1.1-91 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry" Chapter Xl.M21A,, "Closed Trea.ted Water Systems" *
Chapter Xl.M21A, "Closed Treated Water Systems" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of steel with nickel alloy or stainless steel cladding, stainless steel, and nickel-alloy components exposed to reactor coolant is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No Consistentwith NUREG-1801. Loss of material of steel components exposed to closed cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems. Program. No Consistent with NUREG-1801. Loss of material of copper alloy components exposed to closed cycle cooling water is managed by the Water . Chemistry Control -Closed Treated Water Systems Program.

Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-92 High-strength low alloy Cracking due to stress steel closure head stud corrosion cracking; loss* . assembly exposed to air of material due to with potential for reactor general, pitting, and coolant leakage crevice corrosion, or wear(PWR) 3.1.1-93 Copper alloy >15% Zn or Loss of material due to > 8% [aluminum] Al piping, selective leaching piping components, and piping elements exposed to closed cycle cooling water 3.1.1-94 BWRonly 3.1.1-95 BWRonly 3.1.1-96 BWRonly 3.1.1-97 BWRonly 3.1.1-98 BWRonly 3.1.1-99 BWRonly 3.1.1-100 BWRonly 3.1.1-101 BWRonly 3.1.1-102 BWRonly 3.1.1-103 BWRonly 3.1.1-104 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M3, "Reactor Head Closure Stud Bolting" Chapter Xl.M33, "Selective Leaching" ,, Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking, loss of material, and loss of material due to wear of the closure head stud assembly is*managed by the Reactor Head Closure Studs Program. No Consistent with NUREG-1801. Loss of material of copper alloy >15% Zn or> 8% Al components exposed to closed cycle cooling water is managed by the Selective Leaching Program. Page 3.1-46 Table 3.1.1: Reactor Coolant System Item Aging Effect/ Number Component Mechanism 3.1.1-105 Steel piping, piping None components and piping element exposed to . concrete 3.1.1-106 Nickel alloy piping, piping None components and piping element exposed to air.-indoor, uncontrolled, or air with borated water leakage 3.1.1-107 Stainless steel piping, None piping components and piping element exposed to gas, concrete, air with borated water leakage, air -indoors, uncontrolled 3.1.1-108 [There is no 3.1.1-108 in NUREG-1800.] 3.1.1-109 [There is no 3 .. in NUREG-1800.] 3.1.1-f10 BWRonly 3.0 Aging Management Review Results Aging Management Programs None, provided 1) attributes of the concrete are consistent with [American Concrete Institute] ACI 318 or ACI 349 (low water-to-cement

ratio, low permeability", and adequate air entrainment) as cited in NUREG-1557, and 2) plant"[operating experience] OE indicates no degradation of the concrete None Waterford Steam Electric Station,. Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No, if conditions are No steel reactor coolant met. system or reactor coolant pressure boundary piping components are embedded in concrete. NA -No [aging effecU Consistent with NUREG-1801. mechanism] AEM or AMP '. None NA -No AEM or AMP Consistent-with NUREG-1801 for components exposed to air. There are no stainless steel RCS components exposed to gas or concrete in the scope of license renewal. ... ,, Page 3.1-47 Notes for Tables 3.1.2-1 through 3.1.2-5-2
Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 .fine item. AMP is consistent with f\JUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 101. The One-Time Inspection Program wiil verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 102. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 103. This component is not composed of Alloy 600/82/182 materials. Alloy 690 is not considered susceptible to primary water stress corrosion cracking. 104. Nuts and washers are high strength steel but stud materials are not high strength steel. Measured yield strength of stud material < 150 kilo-pounds per square inch (ksi). 105. High component surface temperature precludes moisture accumulation that could result in corrosion. 3.0 Aging Management Review Results Page 3.1-48 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Reactor vessel Pressure components boundary Reactor vessel Pressure components boundary
Closure head stud assemblies Bolting Pressure ICl/HJTC-CET boundary assemblies
Swageloc modified, bodies
Compression collar
Hold down nuts Closure head Pressure
Center dome boundary 3.0 Aging Management Review Results Table 3.1.2-1 Reactor Vessel Summary of Aging Evaluation
Aging Effect Aging Requiring Management Material Environment Management Programs Carbon steel, Treated borated Cracking-TLAA-metal Carbon steel water (int) fatigue fatigue clad with stainless steel, Nickel alloy, Stainless steel Low alloy Air -indoor (ext) Cracking-TLAA-metal steel *fatigue fatigue Stainless Air-indoor (ext) Loss of preload Bolting Integrity steel** .. Carbon steel Treated borated Loss of material Water Chemistry clad with water> 140°F Control -Primary stainless steel (int) and Secondary / Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-219 3.1.1-10 A IV.A2.RP-54 3.1.1-1 A, 104 IV.A2.R-80 3.1.1-66 B IV.A2.RP-28 3.1.1-88 A Page 3.1-49 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Material Environment Closure head Pressure Carbon steel Treated borated
Center dome boundary clad with water > 140°F stainless steel (int) Closure head Pressure Carbon steel Air-indoor (ext)
Center dome boundary Closure head Pressure Carbon steel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon s.teel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon steel Treated borated
Flange boundary clad with water> 140°F stainless steel (int) Closure head Pressure Carbon steel Air-indoor (ext)
Flange boundary Closure head Pressure Nickel alloy Treated borated penetrations boundary (Alloy 690) water (int)
Vent pipe nozzle
CEDM and ICI nozzles 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material lnservice -wear Inspection Loss of material Boric Acid Corrosion Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-87 3.1.1-37 A IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A Page 3.1-50 Table 3.1.2-1: Reactor Vessel Intended Component Type Function Material Environment Closure head Pressure Nickel alloy Treated -borated penetrations boundary (Alloy 690) water (int)
Vent pipe nozzle
CEDM and ICI nozzles Closure head Pressure Nickel alloy Air -indoor (ext) penetrations boundary (Alloy 690)
Vent pipe nozzle
CEDM and ICI nozzles Closure head bolting Pressure High strength Air -indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure High strength Air-indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure High strength Air-indoor (ext) *Nuts boundary steel *Washers Closure head bolting Pressure Low alloy Air -indoor (ext)
Studs boundary steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary None None Loss of material Boric Acid Corrosion Reactor Head Closure Studs Loss of material Reactor Head -wear Closure Studs Cracking Reactor Head Closure Studs Loss of material Boric Acid Corrosion Reactor Head Closure Studs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-90 3.1.1-45 E, 103 IV.E.RP-378 3.1.1-106 A IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.R-17 3.1.1-49 IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.RP-52 3.1.1-92 A, 104 IV.A2. RP-53 3.1.1-92 A, 104 IV.A2.R-17 3.1.1-49 Page 3.1-51 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function Material Environment Closure head bolting Pressure Low alloy Air-indoor (ext)
Studs boundary steel Control rod drive Pressure Stainless Treated borated assembly boundary steel water> 140°F
CEDM motor (int) housing (tube) and Pressure Stainless Treated borated upper end fitting boundary steel water> 140°F
Versa vent assembly (int) ICI assembly
Flange adaptor *Seal plug Pressure Stainless Air-indoor (ext)
Swageloc modified boundary steel body
Compression collar/ nut Control rod drive Pressure Nickel alloy Treated borated assembly boundary (Alloy 690) water (int)
CEDM motor housing lower end fitting Control rod drive Pressure Nickel alloy Treated borated assembly boundary (Alloy 690) water (int)
CEDM motor housing lower end fitting Flow skirt Pressure Nickel alloy Treated borated boundary water (inUext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Reactor Head -wear Closure Studs Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondarv Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-53 3.1.1-92 A, 104 IV.A2.RP-28 3.1.1-88 c IV.A2.RP-55 3.1.1-47 A IV.E.RP-04 3.1.1-107 c IV.A2.RP-28 3.1.1-88 A IV.A2.RP-234 3.1.1-46 E, 103 IV.A2.RP-28 3.1.1-88 c Page 3.1-52 Table 3.1.2-1: Reactor Vessel Intended Component Type Function Material Environment Flow skirt Pressure Nickel alloy Treated borated boundary water (int/ext) Nozzles (including Pressure Carbon steel Treated borated safe ends) boundary clad with water> 140°F Inlet I outlet stainless steel (int) Nozzles (including Pressure Carbon steel Treated borated safe ends) boundary clad with water > 140°F
Inlet I outlet stainless steel (int) Nozzles (including Pressure Carbon steel Air -indoor (ext) safe ends) boundary
Inlet I outlet Vessel external Structural Carbon steel Air-indoor (ext) attachment support '
Vessel support pads Vessel external Pressure Carbon steel Air-indoor (ext) attachment boundary
Closure head lifting lugs 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-57 3.1.1-40.5 c IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.R-17 3.1.1-49 A IV.A2.R-17 3.1.1-49 A Page 3.1-53 Table 3.1.2-1: Reactor Vessel Intended Component Type Function . Material Environment Vessel internal Structural Nickel alloy Treated borated attachments support water (ext)
Core.stabilizing lugs
Core stop lugs Vessel internal Structural Nickel alloy Treated borated attachments support water (ext)
Core stabilizing lugs
Core stop lugs Vessel flange Pressure Carbon steel Treated borated (including core barrel boundary clad with water> 140°F support ledge) Structural stainless steel (int) support Vessel flange Pressure Carbon steel. Treated borated (including core barrel boundary clad with water> 140°F support ledge) Structural stainless steel (int) support
Vessel flange Pressure Carbon steel Treated borated (including core barrel bounda,ry clad with water> 140°F support ledge) Structural stainless steel (int) support Vessel flange Pressure
Carbon steel Air -indoor (ext) (including core barrel boundary support ledge) Structural support 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary -' and Secondary Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material lnservice -wear Inspection Loss-of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.RP-28 3.1.1-88 c IV.A2.RP-57 3.1.1-40.5 A IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-87 3.1.1-37 A IV.A2.R-17 3.1.1-49 A Page 3.1-54 Table 3.1.2-1 : Reactor Vessel Intended Component Type Function '.Material Environment
Vessel shell .assembly Pressure Carbon steel Treated borated (including welds) boundary clad with water.> 140°F
Bottom head stainless steel (int) -Torus -Dome Vessel shell assembly Pressure Carbon steel
Treated borated (including welds) boundary clad with water> 140°F
Bottom head stainless steel (int) -Torus -Dome Vessel shell assembly Pressure Carbon steel Air-indoor (ext) (including welds) boundary
Bottom head -Dome Vessel shell assembly Pressure Carbon steel Treated borated' (including welds) boundary : clad with water > 140°F *Upper shell stainless steel (int)
Intermediate shell *Lower shell Vessel shell assembly Pressure Carbon steel Treated borated (including welds) boundary clad with water> 140°F *Upper shell stainless steel (int}
Intermediate shell
Lowershell 3.0 Aging Management Review Results Aging Effect Aging Requiring Management . Management Programs Loss of material Water Chemistry . Control -Primary ' . and Secondc:iry Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of ma_terial Boric Acid Corrosion ' Loss of material
Water Chemistry Control -Primary and Secondary Cracking* lnservice. Inspection Water Chemistry Control.-Primary and Secondary Waterford Steam Electric StatiorJ, Unit 3 License Renewal Application Technical Information NU REG-Table 1 18.01 Item Item *Notes IV.A2.RP-28 3.1.1-88 A IV.C2.R-30 3.1.1-33 c IV.A2.R-17 3.1.1-49 A IV.A2.RP-28 3.1.1-88 A IV.C2*.R-30 3.1, 1-33 c Page 3.1-55 Table 3.1.2-1: Reactor Vessel Aging Effect Intended Requiring Component Type Function Material Environment Management Vessel shell assembly Pressure Carbon steel Treated borated Reduction of (including welds) boundary clad with water > 140°F fracture
Upper shell stainless steel (int) toughness
Intermediate shell Neutron fluence
Lower shell Vessel shell assembly Pressure Carbon steel Air -indoor (ext) Loss of material (including welds) boundary
Upper shell
Intermediate shell *Lower shell 3.0 Aging Management Review Results Aging Management Programs TLAA -neutron fluence Reactor Vessel Surveillance Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.A2.R-84 3.1.1-13 A IV.A2.RP-229 3.1.1-14 IV.A2.R-17 3.1.1-49 A Page 3.1-56 Table 3.1.2-2 Reactor Vessel Internals Summary of Aging Management Evaluation Table 3.1.2-2: Reactor Vessel Internals Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program Reactor vessel Structural Stainless Treated borated Cracking-TLAA -metal fatigue internals components support* steel, nickel water fatigue Flow alloy, CASS distribution Lower support Structural Stainless Treated borated Cracking Reactor Vessel structure assembly support steel water> 140°F Internals (P)
Core support plate Flow Neutron fluence Water Chemistry distribution Control -Primary and Secondary Lower support Structural Stainless Treated borated Loss of material Water Chemistry structure assembly support steel water> 140°F Control -Primary
Core support plate Flow Neutron fluence . and. Secondary distribution Lower support Structural Stainless Treated borated Change in Reactor Vessel structure assembly support steel water> 140°F dimension Internals (N)
Core support plate Flow Neutron fluence Lower support Structural Stainless Treated borated Reduction of Reactor Vessel structure assembly support steel water > 140°F fracture lnternais (P).
Core support plate Flow Neutron fluence toughness distribution 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV. 83. RP-339 3.1.1-3 A 83. RP-343 3.1.1-52a A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-365 3.1.1-56a A Page 3.1-57 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Reactor vessel Structural Stainless Treated borated internal connector support .steel water > 140°F components: Neutron fluence
Bolts
Studs *Nuts Structural Stainless Treated borated *Washers support steel water> 140°F
Locking bars Neutron fluence
Locking caps
Locking keys Structural
Stai.nless Treated borated *Dowels support steel water> 140°F *Cap screws Neutron fluence Structural Stainless Treated borated *support steel water> 140°F
Neu.tron fluence Structural Stainless Treated borated support steel water > 140°F Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Fuel alignment pins Neutron fluence Lower support Strucfural Stainless Treated borated structure assembly support steel water> 140°F
Fuel alignment pins Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals. (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vess.el Internals (N) Reduction of Reactor Vessel fracture Internals (N) Cracking Reactor Vessel* Internals (X) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control ....: Primary and Secondary Waterford Steam Electric l)tation, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A rv. B3. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-334 3.1.1-52c A IV.83.RP-24 3.1.1-87 A Page 3.1-58 Table 3.1.2-2: Reactor Vessel Internals Intended . Compor:ient Type Function Material Environment Lower support Structural Stainless Treated borated structure assembly support *steel . water> 140°F
Fuel alignment pins Neutron fluence Lower support Structural
Stainless Treated borated structure assembly support steel . water> 140°F
Fuel alignment pins Neutron fluence Low.er support Structural . Stainless Treated borated structure assembly support water> 140°F ,
Core support column . Neutron fluence welds lower support Structural Stainless Treated borated structure assembly support steel water> 140°F*
Core support column Neutron fluence welds Lower support Structural Stainless Treated borated structure assembly support steel water > 140°F
Core support column Neutron fluence welds Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management
Management Program Loss of material Reactor Vessel -wear Internals (X) Reduction of Reactor Vessel fracture Internals (X) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture internals (P) toughness Cracking Reactor Vessel Internals (E) .. .. Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information NU Table 1 1801 Item Item Notes IV. 83. RP-336 3.1.1-56c A IV. 83. RP-336 3.1.1-56c A IV.83.RP-363 A IV.83.RP-24 '3.1.1-87 A IV.83.RP-364 3.1.1-56a A IV. 83. 3.1.1-52b A Page 3.1"59 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Core support beams Neutron fluence Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Lower support Structural Stainless Treated borated structure assembly support steel water> 140°F
Deep core support Neutron fluence beams Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper cylinder, Neutron fluence including welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of . Reactqr Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-335 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-331 3.1.1-56b c IV. 83. RP-329 3.1.1-52b A Page 3.1-60 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper cylinder, Neutron fluence including welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper cylinder, Neutron fluence including welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder girth Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower cylinder axial Neutron fluence welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (P) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b c 362b IV.83.RP-3.1.1-52a A 362a IV.83.RP-24 3.1.1-87 A IV.83.RP-362 3.1.1-56a A IV.83.RP-3.1.1-52b A 362c Page 3.1-61 Table 3.1.2-2: Reactor Vessel Internals Intended 'Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower cylinder axial Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower cylinder axial Neutron fluence welds Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Upper section flange weld 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (E) toughness Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (X) Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b A 362b IV.83.RP-329 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-332 3.1.1-56c A IV. 83. RP-327 3.1.1-52a A Page 3.1-62 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Upper section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower section flange Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Lower section flange Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water > 140°F
Lower section flange weld Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys 3.0 Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Loss of material Water Chemistry
Control -*Primary and Secondary Cracking Reactor Vessel Internals (E) Water Chemistry Control -Primary and Loss of material Water Chemistry Control -Primary and Secondary Cracking Reactor Ves*sel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material
Water Chemistry Control -Primary and Secondary Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV. 83. RP-333 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-328 3.1.1-52a A IV.83.RP-24' 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A Page 3.1-63 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys Core support barrel Structural Stainless Treated borated assembly support steel water> 140°F
Alignment keys Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly shims and pins Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A Page 3.1-64 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment. Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Core support barrel Structural Nickel alloy Treated borated assembly support water
Snubber assembly bolt Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Upper guide structure support plate assembly Upper internals Structural Stainless Treated borated assembly support steel water > 140°F
Upper guide structure support plate assembly 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vessel Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A . Page 3.1-65 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals Structural Stainless Treated borated assembly support steel water> 140°F .
Upper guide structure support plate assembly Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel water> 140°F
Fuel alignment plate Neutron fluence Upper internals Structural Stainless Treated borated assembly support steel *water> 140°F
Fuel alignment plate Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Reactor Vessel *-wear Internals (X) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (N) Reduction of Reactor Vessel fracture Internals (N). toughness Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-332 3.1.1-56c c IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b . A Page 3.1-66 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core shroud assembly Structural Stainless Treated borated
Shroud vertical support steel water> 140°F plates Neutron fluence
Former plates
Axial and horizontal weld seams near the Structural Stainless Treated borated central flange and support steel water> 140°F horizontal stiffeners Neutron fluence Structural Stainless Treated borated support steel water> 140°F Neutron fluence Structural Stainless Treated borated support steel water> 140°F Neutron fluence 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Change in Reactor Vessel dimension Internals (P) Reduction of Reactor Vessel fracture Internals (P) toughness Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-3.1.1-52a A 326a IV.83.RP-24 3.1.1-87 A IV. 83. RP-326 3.1.1-56a A IV. 83. RP-326 3.1.1-56a A Page 3.1-67 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Gore shroud assembly Structural Stainless Treated borated
Shroud vertical plate support steel water > 140°F to former plate axial Neutron fluence and horizontal weld seams in extended area around core Structural Stainless Treated borated *-midplane support steel water> 140°F Neutron fluence Structural* Stainless . Treated borated support steel water> 140.°F Neutron fluence Structural Stainless Treated borated support steel . water> 140°F Neutron fluence Core shroud assembly Structural Stainless Treated borated
Weld between upper support steel water> 140°F and lower vertical Neutron fluence ring sections Core shroud assembly Structural Stainless Treated borated
Weld between upper support steel water > 140°F .and lower vertical Neutron fluence ring sections 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Reactor Vessel Internals. (E) Water Chemistry Control -Primary ' and Secondary Loss of material Water Chemistry Control -Primary and Secondary Change in Reactor Vessel dimension Internals (E) Reduction of Reactor Vessel fracture Internals (P) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Seconda,.Y Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-*Table 1 1801 Item Item Notes IV.83.RP-323 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV.83.RP-3.1.1-56b c '359a IV. 83. RP-326 3.1.1-56a A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A .. Page .3.1-68 Table 3.1.2-2: Reactor Vessel Internals Intended Component tvpe Function Material Environment Core shroud assembly Structural Stainless Treated borated*
Weld between upper support steel water> 140°F and lower vertical Neutron fluence ring sections Core shroud assembly Structural Stainless Treated borated *
Weld between upper support steel water> 140°F and lower vertical
Neutron fluence ring sections Core shroud lug and Structural Stainless* Treated borated lug* inserts support steel water> 140°F fluence, ' Core shroud lug and Structural Stainless Treatedborated lug inserts supp.ort steel water> 140°F ' ,. Neutron fluence Core shroud lug and Structural Stainless Treated borated* lug inserts support steel water> 140°F Neutron* fluence Core shroud lug and Structural .Stainless Treated borated lug inserts support i;;teel water > 140°F Neutron fluence Core shroud lug and Structural Stainless Treated borated. lug inserts suppqrt steel water> 140°F Neutron fluence
3.0 Aging Management Review Results r' ) Aging Effect Aging Requiring Management Management.* Program. Change in Reactor Vessel dimension Internals (P) Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary toss of material Water Chemistry . Control -Primary and Secondary ,, . Loss of material Reactor Vessel -wear. Internals (X) *t*. Change in. Reactor Vessel dimension Internals (N) Loss of preload
Reactor Vessel Internals (X) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV. 83. RP-326 3.1.1-56a A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-319 3.1.1-56c A IV.83.RP-306 3.1.1-55b A IV.83.RP-319 3.1.1-56c A Page 3.1-69 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Core shroud lug and Structural Stainless Treated borated lug inserts support. steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Core shroud lug dowel Structural Stainless Treated borated pins support steel water> 140°F Neutron fluence Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water> 140°F
Peripheral Neutron fluence instrument tubes 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (X) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Reactor Vessel -wear Internals (X) Change in Reactor Vessel dimension Internals (N) Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (P) Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-306 3.1.1-55b A IV.83.RP-320 3.1.1-52c A IV.83.RP-24 3.1.1-87 A IV.83.RP-319 3.1.1-56c A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-312 3.1.1-52a A Page 3.1-70 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals CEA Structural Stainless Treated .borated shroud assembly suppqrt steel water > 140°F
Peripheral Neutron. fluence instrument tubes Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water> 140°F
Peripheral .. Neutron fluence instrument tubes Upper internals CEA Structural Stainless Treated borated shroud assembly support steel water > 140°F
Non-peripheral Neutron-fluence instrument tubes Upper internals CEA Structural Stainless Treated .borated shroud assembly support steel water > t40°F
Non-peripheral Neutron fluence instrument tubes Upper internals CEA Structural Stainless . Treated borated shroud assembly support steel water>_ 140°F
Non-peripheral Neutron fluence instrument tubes Upper internals Flow* CASS(CF8 Treated borated assembly distribution Casting) water > 482°F
Flow bypass insert Neutron fluence assembly 3.0 Aging Management Review Results \._ Aging Effect Aging Requiring Manageme_nt Management Program Loss of material . Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel lntern*a1s (E) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary* Reduction of Reactor Vessel fracture Internals (N) toughness .. Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary \ . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-313 3.1.1-52b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A . Page 3.1-71 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment Upper internals Flow CASS(CFB Treated borated assembly distribution Casting) water> 482°F
Flow bypass insert Neutron fluence assembly Upper internals Flow CASS(CFB Treated borated assembly distribution Casting) water> 482°F
Flow bypass insert Neutron fluence assembly Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) Upper internals Structural Precipitation Treated borated assembly support hardened SS water > 482°F
Socket head cap (AMS 5736-F Neutron fluence screw (CEA shroud or A286) bolts) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness . Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of preload Reactor Vessel Internals (N) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A Page 3.1-72 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment CEA shroud assembly Structural CASS(ASTM Treated borated
Modified shroud ext. support
A351-72 water > 4S2°F shaft guide sub-Grade CFS) assembly
Extension shaft *guide CEA shroud assembly Structural CASS(ASTM Treated borated
Modified shroud ext. support A351-72 water > 4S2°F shaft guide sub-Grade CFS) assembly
Extension shaft guide CEA shroud assembly Structural CASS (ASTM Treatedbora.ted
Modified shroud ext. support A351-72 water > 4S2°F shaft guide sub-. Grade CFS) assembly
Extension shaft guide CEA .extension shaft Structural Stainless Treated borated guides support steel water> 140°F CEA extension shaft Structural Stainless Treated borated guides support steel water> 140°F 3.0 Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry . Control -Primary an*d Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -*Primary . and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-' Table 1 1801 Item Item Notes IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-S7 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-S7 A Page 3.1-73 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment CEA extension shaft Structural Treated borated guides support steel water> 140°F CEA shroud assembly Structural CASS (CPF8 Treated borated *Tube support 304 SS water > 482°F casting) Neutron fluence CEA shroud assembly Structural CASS(CPF8 Treated borated *Tube* support 304SS water > 482°F casting) Neutron fluence CEA shroud assembly Structural CASS(CPF8 Treated borated *Tube support 304 SS water> 482°F casting) Neutron fluence Holddown spring Structural Stainless Treated borated ' support steel water> 140°F *, Holddown spring Structural Stainless Treated borated support steel water> 140°F Holddown spring Structural Stainless Treated borated support steel water> 140°F Holddown spring Structural Stainless Treated borated support steel water> 140°F 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Program Loss of material Reactor Vessel -wear Internals (N) Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and *secondary Loss of material Reactor Vessel -wear Internals (N) Loss of preload Reactor Vessel Internals (N) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1ao11tem Item Notes IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A ' IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV. 83. RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A .Page 3.1-74 Table 3.1.2-2: Reactor Vessel Internals Intended Component Type Function Material Environment lncore Instrumentation Structural Zircaloy Treated borated
Thimble -lower part support water > 140°.F Neutron fluence Reactor vessel Structural . Stainless Treated borated internal components support steel water > 140°F not addressed in Flow Neutron fluence* another line item distribution Reactor vessel Structural* Stainless Treated borated internal components support steel water> 140°F not addressed in Flow Neutron fluence another line item distribution Reactor vessel Structural Stainless Treated borated internal components support steel water > 140°F not addressed in Flow Neutron fl.uence another line item distribution Reactor vessel Structural Nickel alloy Treated borated internal components support water not addressed in Neutron fluence another line item Reactor vessel
Structural . Nickel alloy Treated borated internal components support water not addressed in Neutron fluence another line item .. 3.0 Aging Management Review Results I \ Aging Effect Aging Requiring Management Management Program Change in Reactor Vessel dimension Internals (X) Cracking Reactor Vessel
l,nternals (N) Water Chemistry Control --Primary and Secondary Loss of material Water Chemistry . Control -Primary and Secondary Reduction of Reactor Vessel fracture Internals (N) toughness Cracking Reactor Vessel Internals (N) Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----H IV.83.RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A IV.83.RP-306 3.1.1-55b A IV. 83. RP-306 3.1.1-55b A IV.83.RP-24 3.1.1-87 A Page 3.1-75 Table 3.1.2-3 Reactor Coolant Pressure Boundary Summary of Aging Management Evaluation Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program .Bolting Pressure Carbon steel, Air-indoor Cracking -fatigue TLAA-metal boundary Stainless (ext) fatigue steel RCS pressure Pressure Carbon steel, T(eated borated Cracking -fatigue TLAA-metal boundary boundary Carbon steel water> 140°F fatigue components clad with (int) stainless steel, Carbon steel clad with nickel alloy, CASS, Nickel alloy, Stainless steel Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity bound.ary (ext) Boric Acid Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload* Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-18 3.1.1-5 A IV.C2.R-223 3.1.1-9 A IV.C2.RP-166 3.1.1-64 B IV.C2.RP-167 3.1.1-49 A IV.C2.R-12 3.1.1-66 B IV.C2.R-11 3.1.1-62 B *Page 3.1-76 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Bolting Pressure High strength Air-indoor boundary steel (ext) Bolting Pressure High strength Air-indoor boundary steel (ext) Bolting Pressure Stainless Air-indoor boundary steel (ext) Bolting Pressure Stainless Air-indoor boundary steel (ext) Flow element (non-Pressure Stainless Air-indoor Class 1) boundary steel (ext) Flow element (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Flow element (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Heat exchanger coil Pressure Copper alloy Lube oil (ext) (RCP lower oil boundary cooler) Heat exchanger coil Pressure Copper alloy Treated water (RCP lower oil boundary (int) cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Bolting Integrity Boric Acid Corrosion Loss of preload Bolting Integrity Cracking Bolting Integrity Loss of preload Bolting Integrity None None Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-166 3.1.1-64 B IV.C2.RP-167 3.1.1-49 A IV.C2.R-12 3.1.1-66 B IV.C2.R-11 3.1.1-62 B IV.C2.R-12 3.1.1-66 B IV.E.RP-04 3.1.1-107 A IV. C2. RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c Page 3.1-77 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger -Pressure Stainless Treated borated water jacket boundary steel water> 140°F (seal heat (ext) exchanger) Heat exchanger -Pressure Stainless Treated borated water jacket boundary steel water> 140°F (seal heat (ext) exchanger) Heat exchanger -Pressure Stainless Treated water water jacket boundary steel (int) (seal heat exchanger) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) (RCP upper oil cooler) Heat exchanger Pressure ' Carbon steel Treated water (channel head) boundary (int) (RCP upper oil cooler) Heat exchanger Pressure Carbon steel Air-indoor (shell) boundary (ext) (RCP upper oil cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-09 3.1.1-33 c IV.C2.RP-23 3.1.1-88 c V.A.EP-93 3.2.1-31 c Vll.F1.AP-41 3.3.1-80 c IV.C2.RP-221 3.1.1-89 c Vll.F1.AP-41 3.3.1-80 c Page 3.1-78 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel Lube oil (int) (shell) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Lube oil (int) (tube sheet) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Treated water (tube sheet) boundary (ext) (RCP upper oil cooler) Heat exchanger Pressure . Copper alloy Lube oil (ext) (tubes) boundary (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) (RCP upper oil cooler) Heat exchanger Pressure Copper alloy Air-indoor (tubes) boundary (ext) (RCP motor air cooler) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Oil Analysis Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material Oil Analysis Loss of material Water Chemistry Control -Closed Treated Water Systems None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s Vll.H2.AP-131 3.3.1-98 C, 102 V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c V.A.EP-76 3.2.1-50 C, 102 IV.C2.RP-222 3.1.1-90 c V.F.EP-10 3.2.1-57 c Page 3.1-79 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) (RCP motor air cooler) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) (RCP motor air cooler) Heat exchanger Pressure Carbon steel Treated water (channel head) boundary (int) (RCP motor air cooler) Heat exchanger Pressure Copper alloy Air-indoor (tube sheet) boundary (ext) (RCP motor air cooler) Heat exchanger Pressure Copper alloy Treated water (tube sheet) boundary (int) (RCP motor air cooler) Orifice Pressure Nickel alloy Air-indoor boundary (Alloy 690) (ext) Flow control 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems None None Loss of material Water Chemistry Control -Closed Treated Water Systems None No.ne Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-222 3.1.1-90 c Vll.F1.AP-41 3.3.1-80 c IV.C2.RP-221 3.1.1-89 c V.F.EP-10 3.2.1-57 c IV.C2.RP-222 3.1.1-90 c IV.E.RP-03 3.1.1-106 A Page 3.1-80 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Orifice Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Flow control Orifice Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Flow control Orifice Pressure Stainless Air-indoor boundary steel (ext) Flow control Orifice Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Piping 4" NPS Pressure Carbon steel Air-indoor boundary clad with (ext) stainless steel Piping 4" NPS Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Nickel Alloy Inspection Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-30 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV. C2. RP-380 3.1.1-48 A IV.C2.R-30 3.1.1-33 A Page 3.1-81 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component type Function Material Environment Piping 4" NPS Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel Piping 4" NPS Pressure CASS Air-indoor boundary (ext) Piping 4" NPS Pressure CASS Treated borated boundary water (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Piping 4" NPS Pressure CASS Treated borated boundary water> 482°F (int) Piping < 4" NPS Pressure CASS Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Thermal Aging Embrittlement of CASS Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of Thermal Aging fracture Embrittlement of toughness CASS None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1-88 A IV.C2.R-52 3.1.1-50 A IV.E.RP-04 3.1.1-107 A Page 3.1-82 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management Piping < 4" NPS Pressure CASS Treated borated Loss of material boundary water (int) Piping < 4" NPS Pressure CASS Treated borated Cracking boundary water> 140°F (int) Piping < 4" NPS Pressure CASS Treated borated Loss of material boundary water> 140°F (int) Piping < 4" NPS Pressure CASS Treated borated Reduction of boundary water> 482°F fracture (int) toughness Piping ;:: 4" NPS Pressure Stainless Air-indoor None boundary steel (ext) Piping ;:: 4" NPS Pressure Stainless . Treated borated Cracking boundary steel water> 140°F (int) Piping ;:: 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary lnservice Inspection Thermal Aging Embrittlement of CASS Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Thermal Aging Embrittlement of CASS None lnservice Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1-88 A IV.C2.R-52 3.1.1-50 A IV.E.RP-04 3.1.1-107 A IV.C2.R-30 3.1.1-33 A IV.C2.R-56 3.1.1-35 IV.C2.RP-23 3.1.1-88 A Page 3.1-83 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management Piping < 4" NPS Pressure Stainless Air-indoor None boundary steel (ext) Piping < 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water (int) Piping < 4" NPS Pressure Stainless Treated borated Cracking boundary steel water > 140°F (int) Piping < 4" NPS Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) Piping (non-Class 1) Pressure Stainless Air-indoor None boundary steel (ext) Piping (non-Class 1) Pressure Stainless Treated borated Loss of material boundary steel water (int) Piping (non-Class 1) Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Piping (non-Class 1) Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Management Program None Water Chemistry Control -Primary and Secondary lnservice Inspection One-Time Inspection -Small-Bore Piping Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.RP-235 3.1.1-39 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A V.A.EP-41 3.2.1-22 A, 101 IV.C2.RP-383 3.1.1-80 C, 101 V.A.EP-41 3.2.1-22 C, 101 Page 3.1-84 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Piping (non-Class 1) Pressure Copper alloy Air-indoor (RCP lower oil boundary > 15% Zn or (ext) cooler) >8%AI Piping (non-Class 1) Pressure Copper alloy Treated water (RCP lower oil boundary >15%Znor (int) cooler) >8%AI Piping (non-Class 1) Pressure Copper alloy Treated water (RCP lower oil boundary >15%Znor (int) cooler) >8%AI Piping (non-Class 1) Pressure Stainless Air-indoor RV flange leak off boundary steel (ext) lines Piping (non-Class 1) Pressure Stainless Treated borated RV flange leak off boundary steel water (int) lines Piping (non-Class 1) Pressure Stainless Treated borated RV flange leak off boundary steel water (int) lines Pressurizer heater Pressure Stainless Treated borated sheath boundary steel water > 140°F (ext) 3.0 Aging M*anagement Review Results Aging Effect Aging Requiring Management Management Program None None Loss of material Selective Leaching Loss of material Water Chemistry Control -Closed Treated Water Systems None None Cracking One-Time Inspection Loss of material One-Time Inspection Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s V.F.EP-10 3.2.1-57 c IV.C2.RP-12 3.1.1-93 A IV.C2.RP-222 3.1.1-90 A IV.E.RP-04 3.1.1-107 A IV.A2.R-74 3.1.1-19 E ----H IV.C2.R-217 3.1.1-33 A IV.C2.R-58 3.1.1-40 Page 3.1-85 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer heater Pressure Stainless Treated borated* sheath boundary steel water> 140°F (ext) Pressurizer heater Pressure Stainless Air-indoor sleeve end caps boundary steel (ext) Pressurizer heater Pressure Stainless Treated borated sleeve end caps boundary steel water> 140°F (int) Pressurizer heater Pressure Stainless Treated borated sleeve end caps boundary steel water> 140°F (int) Pressurizer heater Pressure Nickel alloy Air-indoor plug, heater sleeves boundary (Alloy 690) (ext) and heater sheath to sleeve welds PrE!ssurizer heater Pressure Nickel alloy Treated borated plug, heater sleeves boundary (Alloy 690) water (int) and heater sheath to sleeve welds Pressurizer heater Pressure Nickel alloy Treated borated plug, heater sleeves boundary (Alloy 690) water (int) and heater sheath to sleeve welds 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary an_d Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A Page 3.1-86 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer heater Structural Nickel alloy Treated borated internal support support water (ext) structure Pressurizer heater Structural Nickel alloy Treated borated internal support support water (ext) structure Pressurizer heater Structural Stainless Treated borated internal support support steel water> 140°F structure (int) Pressurizer heater Structural Stainless Treated borated internal support support steel water > 140°F structure (int) Pressurizer Pressure Nickel alloy Air-indoor instrument nozzle boundary (Alloy 690) (ext) Pressurizer Pressure Nickel alloy Treated borated instrument nozzle boundary (Alloy 690) water (int) Pressurizer Pressure Nickel alloy Treated borated instrument nozzle boundary (Alloy 690) water (int) Pressurizer lower Pressure Carbon steel Air-indoor head boundary clad with (ext) nickel alloy 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 A IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A Page 3.1-87 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer lower Pressure Carbon steel Treated borated head boundary clad with water (int) nickel ailoy Pressurizer lower Pressure . Carbon steel Treated borate.d head boundary clad with water (int) nickel alloy Pressurizer manway Pressure Carbon steel Air-indoor cover boundary (ext) Pressurizer manway Pressure Stainless Steam (int) gasket retainer plate boundary steel
Pressurizer manway Pressure Stainless Steam (int) gasket retainer plate boundary steel Pressurizer nozzles Pressure Carbon steel Air-indoor (spray nozzle, surge boundary clad with (ext) nozzle, safety stainless nozzle) st43el Pressurizer nozzles Pressure Carbon steel Treated borated (spray nozzle, surge boundary clad with water> 14.0°F' nozzle, safety .. stainless (int) nozzle) steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secon9ary Loss of material* Water Chemistry Control -Primary and Secondary .Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 -A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.)-40 Page 3.1-88 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer nozzles Pressure Carbon steel Treated borated (spray nozzle, surge boundary clad with water> 140°F
nozzle, safety stainless (int) nozzle) steel Pressurizer shell Pressure Carbon steel Air-indoor and upper head boundary clad with (ext) stainless steel Pressurizer shell Pressure Carbon steel Treated borated and upper head boundary clad with water> 140°F stainless (int) steel Pressurizer shell Pressure Carbon steel Treated borated and upper head boundary clad with water > 140°F stainless (int) steel Pressurizer spray Flow control Nickel alloy Treated borated head water (int) Pressurizer spray Flow control Nickel alloy Treated borated head water (int) Pressurizer support Structural Carbon steel Air-indoor skirt support (ext) Pressurizer support Structural Carbon steel Air-indoor skirt support (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking lnservice Inspection Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.C2.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A IV.C2.RP-40 3.1.1-82 A, 101 IV.C2.RP-23 3.1.1-88 A IV.C2.R-19 3.1.1-36 A IV.C2.R-17 3.1.1-49 A Page 3.1-89 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pressurizer welds -Pressure Nickel alloy Air-indoor instrument sleeve to boundary (Alloy 690) (ext) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pressurizer welds -Pressure Nickel alloy Treated borated instrument sleeve to boundary (Alloy 690) water (int) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pressurizer welds -Pressure Nickel alloy Treated borated instrument sleeve to boundary (Alloy 690) water (int) instrument; and nozzle to safe-end weld overlays RCS piping hot leg -overlay welds Pump casing Pressure CASS Air-indoor (RCP) boundary. (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-03 3.1:1-106 A IV.C2.RP-37 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.U-107 A Page 3.1-90 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Pump casing Pressure CASS Treated borated (RCP) boundary water> 140°F (int) Pump casing Pressure CASS Treated borated (RCP) boundary water> 140°F (int) Pump casing Pressure CASS Treated borated (RCP) boundary water> 482°F (int) Pump cover Pressure Carbon steel Air-indoor (RCP) boundary clad with (ext) stainless steel Pump cover Pressure Carbon steel Treated borated (RCP) boundary clad with water> 140°F stainless (int) steel Pump cover Pressure Carbon steel Treated borated (RCP) boundary clad with water> 140°F stainless (int) steel RCS cold leg welds Pressure Nickel alloy Air-indoor boundary (alloy 600) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary
Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
NUREG-1801 Table 1 Note Item Item s IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-08 3.1.1-38 A IV.C2.R-17 3.1.1-49 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A Page 3.1-91 Table 3.1.2-3: Reactor Coolant Pressure Boundary Aging Effect Intended Requiring Component Type Function Material Environment Management RCS cold leg welds Pressure Nickel alloy Treated borated Cracking boundary (alloy 600) water (int) RCS cold leg welds Pressure Nickel alloy Treated borated Loss of material boundary (alloy 600) water (int) Safe end Pressure Stainless Air-indoor None (pressurizer spray, boundary steel (ext) drain, pressurizer instrument nozzles) Safe end Pressure
Stainless Treated borated Cracking (pressurizer spray, boundary steel water> 140°F drain, pressurizer (int) instrument nozzles) Safe end Pressure Stainless Treated borated Loss of material (pressurizer spray, boundary steel water> 140°F drain, pressurizer (int) instrument nozzles) 3.0 Aging Management Review Results Aging Management Program lnservice Inspection Nickel Alloy Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary None lnservice Inspection Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-159 3.1.1-45 A IV.C2.RP-23 3.1:1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-25 3.1.1-42 A IV.C2.R-58 3.1.1-40 IV.C2.RP-23 3.1.1-88 A Page 3.1-92 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material .Environment Safe end Pressure CASS Air -indoor. (hot leg and (ext) pressurizer surge, shutdown cooling and pressurizer safety) Safe end Pressure CASS Treated borated (hot leg and boundary water > 140°F pressurizer surge, (int) shutdown cooling and pressurizer safety) '* Safe end Pressure CASS Treated borated' (hot leg and boundary > 140°F (int). pressurizer surge, shutdown cooling and pressurizer safety) Safe end Pressure CASS Treated borated* (hot leg and boundary water :> 482°F pres'st1rizer (int) shutdown cooling and pressurizer '. safety) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None ' Cracking .lnservice Inspection Thermal Aging Embrittleinent of CASS Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary ' . and Se96ndary ' Reduction of Thermal Aging fracture Embrittlement of toughness CASS ,. Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.E.RP-04 3.1.1-107 A IV.C2.R-05 3.1.1-20 E IV.C2.RP-23 3.1.1,-88 A IV.C2.R-52 3.1.1-50 A Page 3.1-93 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Thermal sleeve Structural Nickel alloy Treated borated (charging, SI, surge, integrity water (int) pressurizer spray) Thermal sleeve Structural Nickel alloy Treated borated (charging, SI, surge, integrity water (int) pressurizer spray) Thermowell Pressure Nickel alloy Air-indoor boundary (Alloy 690) (ext) Thermowell Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Thermowell Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubing (non-Class Pressure Stainless Air-indoor 1) boundary steel (ext) Tubing (non-Class Pressure Stainless Treated borated 1) boundary steel water (int) Tubing (non-Class Pressure Stainless Treated borated 1) boundary steel water> 140°F (int) Tubing (non-Class Pressure Stainless Treated borated 1) bound.ary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry ,.. Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-03 3.1.1-106 A IV.C2.RP-159 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.RP-23 3.1.1-88 A IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 A Page 3.1-94 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component ,Type Function Material Environment
Valve body NPS Pressure CASS Air-indoor boundary (ext) Valve body NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body NPS Pressure CASS Treated borated boundary water> 482°F (int) Valve body NPS Pressure Stainless Air-indoor boundary steel (ext) Valve body NPS Pressure Stainless* Steam (int) boundary steel Valve body NPS Pressure Stainless Steam (int) boundary steel Valve body NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Cracking lnservice Inspection . Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking ' lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item . Item s IV.E.RP-04 3.1.1-107 A \ IV.C2.R-09 3.1.1-33 A --IV.C2.RP-23 3.1.1-88 A IV.C2.R-08 . 3.1.1-38 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.C2.R-09 3.1.1-33 A Page 3.1-95 Table 3.1.2-3: Reactor Coolant Pressure Boundary ' Intended Component Type Function Material Environment Valve body <::4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body <4" NPS Pressure CASS Air-indoor boundary (ext) Valve body <4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body <4" NPS Pressure CASS Treated borated boundary water> 140°F (int) Valve body <4" NPS Pressure CASS Treated borated boundary water> 482°F (int) Valve body <4" NPS Pressure Stainless Air-indoor boundary steel (ext) Valve body <4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body <4" NPS Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body (non-Pressure CASS Air-indoor Class 1) boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of lnservice Inspection fracture toughness None None Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A 3.1.1-88 A IV.C2.R-08 3.1.1-38 A IV.E.RP-04 3.1.1-107 A IV.C2.R-09 3.1.1-33 A IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A Page 3.1-96 Table 3.1.2-3: Reactor Coolant Pressure Boundary Intended Component Type Function Material Environment Valve body (non-Pressure CASS Treated borated Class 1) boundary water> 140°F (int) Valve body (non-Pressure CASS Treated borated Class 1) boundary water > 140°F (int) Valve body (non-Pressure Stainless Air -*indoor Class 1) boundary steel (ext) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water (int) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) Valve body (non-Pressure Stainless Treated borated Class 1) boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Note Item Item s V.A.E-12 3.2.1-20 C, 101 IV.C2.RP-23 3.1.1-88 A IV.E.RP-04 3.1.1-107 A V.A.EP-41 3.2.1-22 A, 101 IV.C2.RP-383 3.1.1-80 C, 101 V.A.EP-41 3.2.1-22 C, 101 Page 3.1-97 Table 3.1.2-4: Steam Generators Intended Component Type Function Steam generator Pressure components boundary Steam generator Pressure components boundary 3.0 Aging Management Review Results Table 3.1.2-4 Steam Generators Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Material Environment Management Program Carbon steel, Air-indoor Cracking -fatigue TLAA-metal stainless (ext) fatigue steel, nickel alloy (Alloy 690), carbon steel clad with stainless steel, carbon steel clad
with nickel alloy (Alloy 690) Carbon steel, Treated borated Cracking -fatigue TLAA-metal stainless water> 140°F fatigue steel, nickel (int) alloy (Alloy 690), carbon steel clad with stainless steel, carbon steel clad with nickel alloy (Alloy 690) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.R-18 3.1.1-5 c IV.D1 .R-221 3.1.1-8 A 'IV.01 .R-46 3.1.1-2 Page 3.1-98 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Steam generator Pressure Carbon steel, Treated water > components boundary stainless 140°F (int) steel, nickel alloy (Alloy 690) Pressure boundary Pressure Carbon steel Air-indoor closure bolting boundary (ext) Pressure boundary Pressure Carbon steel Air-indoor closure bolting boundary (ext) Tubesheet Pressure Carbon steel Air-indoor boundary clad with (ext) nickel alloy (Alloy 690) Tubesheet Pressure Carbon steel Treated borated boundary clad with water (int) nickel alloy (Alloy 690) Tubesheet Pressure Carbon steel Treated borated boundary clad with water (int) nickel alloy (Alloy 690) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking -fatigue TLAA-metal fatigue Loss of material Bolting Integrity Boric Acid Corrosion Loss of preload Bolting Integrity Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.R-33 3.1.1-5 A 'IV.01 .R-46 3.1.1-2 IV.C2.RP-166 3.1.1-64 D IV.C2.RP-167 3.1.1-49 c IV.01 .RP-46 3.1.1-67 B IV.01.R-17 3.1.1-49 A IV.01 .RP-36 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 c Page 3.1-99 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tubesheet Pressure Carbon steel Treated water boundary clad with (int) nickel alloy (Alloy 690) Tube to tubesheet Pressure Nickel alloy Treated borated weld boundary (Alloy 690) water Tube to tubesheet Pressure Nickel alloy Treated borated weld boundary (Alloy 690) water Channel head Pressure Carbon steel Air-indoor boundary . clad with (ext) stainless steel or nickel alloy (Alloy 690) Channel head Pressure Carbon steel Treated borated boundary clad with water> 140°F stainless (int) steel or nickel alloy (Alloy 690) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking In service Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-372 3.1.1-83 C, 101 IV.01 .RP-385 3.1.1-25 A IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A IV.C2.R-25 3.1.1-42 c Page 3.1-100 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Channel head Pressure Carbon steel Treated borated boundary clad with water > 140°F stainless (int) steel or nickel alloy (Alloy 690) Partition plate Pressure Nickel alloy Treated borated boundary (Alloy 690) water Partition plate Pressure Nickel alloy Treated borated boundary (Alloy 690) water Primary inlet and Pressure Carbon steel Air-indoor outlet nozzle boundary clad with (ext) transition pieces stainless steel Primary inlet and Pressure Carbon steel Treated borated outlet nozzle boundary clad with water> 140°F transition pieces stainless (int) steel Primary inlet and Pressure Carbon steel Treated borated outlet nozzle boundary clad with water> 140°F transition pieces stainless (int) steel Primary side Pressure Nickel alloy Air-indoor pressure nozzle boundary (Alloy 690) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -*Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.RP-23 3.1.1-88 c IV.01 .RP-367 3.1.1-25 A IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A IV.01 .RP-232 3.1.1-33 A IV.C2.RP-23 3.1.1-88 c IV.E.RP-378 3.1.1-106 A Page 3.1-101 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary side Pressure Nickel alloy Treated borated pressure nozzle boundary (Alloy 690) water (int) Primary side Pressure Nickel alloy Treated borated pressure nozzle boundary (Alloy 690) water (int) Inlet and outlet Pressure Nickel alloy Treated borated nozzle dam rings boundary (Alloy 690) water Inlet and outlet Pressure Nickel alloy Treated borated nozzle dam rings boundary (Alloy 690) water Primary manway Pressure Stainless Treated borated drain tube boundary steel water> 140°F Primary manway Pressure Stainless Treated borated drain tube boundary steel water> 140°F Primary manway Pressure Carbon steel Air-:--indoor cover boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking In service Inspection Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.RP-36 3.1.1-45 E, 103 IV.C2.RP-23 3.1.1-88 c IV.C2.RP-40 3.1.1-82 C, 101 IV.C2.RP-23 3.1.1-88 c IV.01 .RP-232 3.1.1-33 c IV.C2.RP-23 3.1.1-88 c IV.01.R-17 3.1.1-49 A Page3.1-102 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary manway Pressure Stainless Treated borated insert boundary steel water> 140°F (int) Primary manway Pressure Stainless Treated borated insert boundary steel water> 140°F (int) Tubes Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubes Pressure Nickel alloy Treated borated boundary (Alloy 690) water (int) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) Tubes Pressure Nickel alloy Treated water boundary (Alloy 690) (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.C2.RP-383 3.1.1-80 C, 101 IV.C2.RP-23 3.1.1-88 c IV.01.R-44 3.1.1-70 A IV.C2.RP-23 3.1.1-88 c IV.01.R-47 3.1.1-69 A IV.01 .RP-226 3.1.1-71 c IV.01 .RP-233 3.1.1-77 A Page 3.1-103 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tubes Heat transfer Nickel alloy Treated borated (Alloy 690) water (int) Tubes Heat transfer Nickel alloy Treated water (Alloy 690) (ext) Tube plugs Pressure Nickel alloy Treated borated boundary (Alloy 690) water Tube plugs Pressure Nickel alloy Treated borated boundary (Alloy 690) water Secondary shell Pressure Carbon steel Air-indoor (elliptical head with boundary (ext) integral steam nozzle, upper, intermediate and lower shells, transition cone) Secondary shell Pressure Carbon steel Treated water (elliptical head with boundary (int) integral steam nozzle, upper, intermediate and lower shells, transition cone) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program None None Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material In service Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes --H ----H IV.01.R-40 3.1.1-70 A IV.C2.RP-23 3.1.1-88 c ----G, 105 IV.01.RP-368 3.1.1-12 A Page 3.1-104 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Flow limiter insert Flow control Nickel alloy Treated water (Alloy 690) Flow limiter insert Flow control
Nickel alloy Treated water (Alloy 690) Feedwater nozzle Pressure Carbon steel Air-indoor boundary (ext) Feedwater nozzle Pressure Carbon steel Treated water boundary (int) Feedwater nozzle Pressure Nickel alloy Treated water thermal sleeve boundary (Alloy 690) Feedwater nozzle Pressure Nickel alloy Treated water thermal sleeve boundary (Alloy690) Instrument and Pressure Carbon steel Air-indoor sampling nozzles boundary (ext) Instrument and Pressure Carbon steel Treated water sampling nozzles boundary (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D2.R-36 3.1.1-78 C, 101 Vlll.81.SP-157 3.4.1-16 C, 101 ----G, 105 IV.01 .RP-368 3.1.1-12 c IV.02.R-36 3.1.1-78 C, 101 Vlll.81 .SP-157 3.4.1-16 C, 101 ----G, 105 IV.01 .RP-368 3.1.1-12 c Page 3.1-105 Table 3.1.2-4: Steam Generators Aging Effect Intended Requiring Component Type Function Material Environment Management. Slowdown nozzle. Pressure Carbon steel Air-indoor None boundary (ext) Slowdown nozzle Pressure Carbon steel Treated water Loss of material boundary (int) Slowdown nozzle Pressure Carbon steel Treated water Loss of material -boundary (int) FAG Secondary manway, Pressure Carbon steel Air-indoor None handhole, inspection boun.dary (ext) .. port, and recirculation nozzles Secondary manway, Pressure Carbon steel Treated water Loss of material handhole, inspection boundary (int) port, and recirculation nozzles Secondary manway, Pressure Carbon steel Air-indoor None handhole, inspection boundary (ext) port, and recirculation nozzle cover plates 3.0 Aging Management Review Results Aging Management Program None lnservice Inspection Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion None lnservice Inspection Water Chemistry Control -:-Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes ----G, 105 IV.01.RP-368 3.1.1-12 c IV.01.R-37 3.1.1-61 c ---G, 105 IV.01 .RP-368 3.1.1-12 c ----G, 105 Page 3.1-106 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Secondary manway, Pressure Carbon steel Treated water handhole, inspection boundary (int) port, and recirculation nozzle cover plates Secondary manway, Pressure Carbon steel Treated water handhole, inspection boundary (int) port, and recirculation nozzle cover plates Handhole and Pres.sure Carbon steel Air-indoor inspection port (with boundary (ext) seal welded diaphragms) cover plates Handhole and Pressure Nickel alloy Air-indoor inspection port boundary (Alloy 690) (ext) diaphragms Handhole and Pressure Nickel alloy Treated water inspection port boundary (Alloy 690) diaphragms Handhole and Pressure Nickel alloy Treated water inspection port boundary (Alloy 690) diaphragms External shell Pressure Carbon steel Air -indoor attachments boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material lnservice Inspection Water Chemistry Control -Primary and Secondary Loss of material -lnservice erosion Inspection None None None None Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01.RP-368 3.1.1-12 c IV.02.R-31 3.1.1-44 c ----G, 105 IV.E.RP-03 3.1.1-106 A IV.02.R-36 3.1.1-78 C, 101 Vlll.81.SP-157 3.4.1-16 C, 101 ----G, 105 Page 3.1-107 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Tube support plates, Structural Stainless Treated water > anti-vibration integrity steel 140°F assembly bars Wrapper barrel, Structural Carbon steel Treated water associated integrity components Recirculation nozzle Structural Nickel alloy Treated water sleeve, wrapper integrity (Alloy 690) plug seal plates 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-384 3.1.1-71 A IV.01 .RP-226 3.1.1-71 A IV.01 .RP-225 3.1.1-76 A IV.01.RP-161 3.1.1-72 A IV.01 .RP-384 3.1.1-71 c Page 3.1-108 Table 3.1.2-4: Steam Generators Intended Component Type Function Material* Environment Recirculation nozzle Structural Nickel alloy Treated water sleeve, wrapper integrity (Alloy 690) plug seal plates Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim Anti-vibration Structural Nickel alloy Treated water assembly end caps, integrity (Alloy 690) retaining rings, retaining bars, stayrod washer, tube support plate shim 3.0 Aging Management Review Results ( Aging Effect Aging Requiring . Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D1 .RP-226 3.1.1-71 c IV.01 .RP-384 3.1.1-71 A IV.01 .RP-226 3.1.1-71 A IV.D1 .RP-225 3.1.1-76 A Page 3.1-109 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Stayrods, wedges, Structural Carbon steel Treated water tube support integrity components Stayrods, wedges, Structural Carbon steel Treated water tube support integrity components Feedwater header Structural Carbon steel Treated water and support integrity components Feedwater spray Structural Nickel alloy Treated water nozzles, nozzle integrity (Alloy 690) caps, filler plates Feedwater spray Structural Nickel alloy Treated water nozzles, nozzle integrity (Alloy 690) caps, filler plates 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material -Steam Generator wear Integrity Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-226 3.1.1-71 A IV.01.RP-225 3.1.1-76 A IV.01.RP-226 3.1.1-71 c IV.01 .RP-384 3.1.1-71 c IV.01 .RP-226 3.1.1-71 c Page 3.1-110 Table 3.1.2-4: Steam Generators Intended Component Type Function Material Environment Primary separator Structural Carbon steel Treated water assembly integrity components Drain bucket Structural Stainless Treated water assembly integrity steel > 140°F components Drain bucket Structural Stainless Treated water assembly integrity steel > 140°F . components Lower deck Structural Carbon steel Treated water components integrity Middle deck Structural Carbon steel Treated water components integrity 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Cracking Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Loss of material Steam Generator Integrity Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.D1 .RP-226 3.1.1-71 c IV.D1 .RP-384 3.1.1-71 c IV.D1 .RP-226 3.1.1-71 c IV.D1.RP-226 3.1.1-71 c IV.D1.RP-226 ,3.1.1-71 c Page 3.1-111 Table 3.1.2-4: Steam Generators Aging Effect Intended Requiring Component Type Function Material Environment Management Sludge collector Structural Carbon steel Treated water Loss of material assembly integrity Secondary Structural Carbon steel Treated water Loss of material separator integrity components Pedestal support Structural Carbon steel Air-indoor Loss of material support (ext) Snubber lug, key Structural Carbon steel Air-indoor None bracket support (ext) 3.0 Aging Management Review Results Aging Management Program Steam Generator Integrity Water Chemistry Control -Primary and Secondary Steam Generator Integrity Water Chemistry Control -Primary and Secondary Boric Acid Corrosion None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes IV.01 .RP-226 3.1.1-71 c IV.01.RP-226 3.1.1-71 c IV.01.R-17 3.1.1-49 A . ----G, 105
Page 3.1-112 Table 3.1.2-5-1 Reactor Coolant System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related* systems Summary of Aging Management Evaluation Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity IV.C2.R-12 3.1.1-66 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity IV.C2.RP-166 3.1.1-64 B boundary (ext} Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.RP-167 3.1.1-49 A boundary (ext) Corrosion Filter housing Pressure Aluminum Air-indoor None None V.F.EP-3 3.2.1-56 c boundary (ext) Filter housing Pressure Aluminum Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-162 3.3.1-99 C, 102 boundary Filter housing Pressure steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Filter housing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Flex hose Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Flex hose Pressure Stainless Lube oil (int) Loss of material Oil Analysis V.01.EP-80 3.2.1-50 C, 102 boundary steel Orifice Pressure Stainless Air-indoor None ". None IV.E.RP-04 3.1.1-107 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.1-113 )

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging* Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Orifice Pressure Stainless Lube oil (int) Loss of material Oil Analysis V.01.EP-80 3.2.1-50 C, 102 boundary steel Piping Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Piping Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary

Piping Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion 3.0 Aging Management Review Results Page 3.1-114 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Pump casing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Rupture disc Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Rupture disc Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Rupture disc Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Sight glass Pressure Glass Air-indoor None None V.F.EP-15 3.2.1-60 c boundary (ext) Sight glass Pressure Glass Treated borated None None V.F.EP-30 3.2.1-60 c boundary water (int) Sight glass Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Sight glass Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary. steel water> 140°F Control -Primary (int) and Secondary Sight glass Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Strainer housing Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion 3.0 Aging Management Review Results Page 3.1-115 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Strainer housing Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Strainer housing Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Strainer housing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 c boundary steel (ext) Tank Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Tubing Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary water> 140°F Control -: Primary (int) and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material Boric Acid IV.C2.R-17 3.1.1-49 A boundary (ext) Corrosion Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.1-116 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.1.2-5-1: Reactor Coolant System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis V.A.EP-77 3.2.1-49 C, 102 boundary Valve body Pressure Stainless Air-indoor None None IV.E.RP-04 3.1.1-107 A boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Treated borated Cracking Water Chemistry IV.C2.RP-383 3.1.1-80 C, 101 boundary steel water> 140°F Control -Primary (int) and Secondary Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 C, 101 boundary steel water > 140°F Control -Primary (int) and Secondary Valve body Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.1-117 Table 3.1.2-5-2 Steam Generators Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.1.2-6: Steam Generators, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring . Management NUREG-1801 Table 1 Component Type Function .. Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity IV.01 .RP-46 3.1.1-67 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity IV.C2.RP-166 3.1.1-64 D boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces V.A.E-26 3.2.1-40 c boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.1-118 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.2 ENGINEERED SAFETY FEATURES 3.2, 1 Introduction This section provides the results of the aging management reviews for components in the ESF systems that are subject to aging management review. The following systems are addressed in this section (system descriptions are available in the referenced sections).
Containment Spray (Section 2.3.2.1)
Safety Injection (Section 2.3.2.2)
Containment Penetrations (Section 2.3.2.3)
ESF Systems in Scope for 10 CFR 54.4(a)(2) (Section 2.3.2.4) Table 3.2.1, Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the engineered safety features component groups. This table uses the format described in the introdu.ction to Section 3. Hyperlinks are provided to the program evaluations in
Appendix B. 3.2.2 Results The following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for systems in the ESF system group.
Table 3.2.2-1 Containment Spray System-Summary of Aging Management Evaluation
Table 3.2.2-2 Safety Injection Systerh---Summary of Aging Management Evaluation
Table 3.2.2-3 Containment Penetrations-Summary of Aging Management Evaluation ESF Systems in Scope for*10 CFR 54.4(a)(2)
Table 3.2.2-4-1 Containment Spray System;*Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation
Table 3.2.2-4-2 Safety Injection System, Nonsafety-Relc;1ted Con:iponents Affecting Safefy-Related Systems-Summary of Aging Management Evaluation 3.2.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the ESF systems. Programs are described in Appendix B. Further details are provided in the system tables.
3.0 Aging Management Review Results Page 3.2-1 _

3.2.2.1.1 Containment Spray Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment spray system components are constructed of the following materials. * *

Carbon steel Carbon steel clad with stainless steel Carbon steel with internal coating Stainless steel Environments Containment spray system components are exposed to the following environments.
Air -indoor
Lube oil
Treated borated water
Treated borated water> 140°F _
Treated water Aging Effects Requiring Management The following aging effects associated with the containment spray system require management. *
* * *
Cracking Cracking -fatigue Loss of coating integrity Loss of material Los;s of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the effects of aging on the containment spray system components. * * * * *
Bolting Integrity Boric Acid Corrosion Coating Integrity External Surfaces Monitoring Oil Analysis One-Time Inspection 3.0 Aging Management Review Results Page 3.2-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.2.2.1.2 Safety Injection Materials* Safety injection system components are constructed of the following materials.
Carbon steel
Carbon steel clad with stainless steel
Carbon steel with internal coating
High strength steel
Nickei alloy
Stainless steel Environments Safety injection system components are exposed to the following environments.
Air -indoor
Gas
Treated borated water * *Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects .associated with the safety injection system require management. * * * * *
Cracking Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results Page 3.2-3 Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Aging Management Programs The following aging management programs manage the effects of aging on the safety injection system components. * * * * * *
Bolting Integrity Boric Acid Corrosion Coating Integrity External Surfaces Monitoring One-Time I nspectiori Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.2.2.1.3 Containment Penetrations Materials Containment penetrations components are constructed of the following materials.
Carbon steel
Stainless steel Environments Containment penetrations components are exposed to the following environments.
Air -indoor
Treated borated water
Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects associated with the containment penetrations require management.
Cracking
Cracking -fatigue
Loss of material
Loss of preload 3.0 Aging Management Review Results Page 3.2-4 Waterford Steam Electric Station, Unit 3 /. License Renewal Application (, Technical Information Aging Management Programs The following aging management programs manage the effects of aging on the containment penetrations components.
Bolting Integrity
External Surfaces Monitoring
One-Time Inspection * . Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.2.2.1.4 ESF Systems in Scope for 1 O CFR 54.4CalC2) The following lists encompass materials, envrronments, aging effects requiring management, and aging management programs for the series 3.2.2-4-x tables. Materials Nonsafety-related components affecting safety-related systems are constructed of the following materials. *
Carbon steel
Staf nless steel Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments.
Air -indoor
Treated borated water
Waste water Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. *
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the effects of aging on nonsafety-related components affecting safety-related systems. 3.0 Aging Management Review Results Page 3.2-5

( Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information * *

*
Bolting Integrity Boric Acid Corrosion Internal Surfaces in Piping andDucting Components One-Time Inspection Water Chemistry Control -Primary and Secondary 3.2.2.2 Further Evaluation of Aging Management as Recommended _by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.2.2.2 of NUREG-1800. The following sections are numbered in. accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further evaluation. Programs are described in Appendix B. 3.2.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management, the analysis of fatigue is a TLAA as defined in 10 CFR 54.3. _ TLAAs are evaluated in accordance with 1*0 CFR 54.21 (c). Evaluation of this TLAA is addressed in Section 4.3. 3.2.2.2.2 Loss of Material due to Cladding [Breach] This paragraph in NUREG-1800 pertains to steel charging pump casings with stainless steer cladding .. Loss of material could occur for the steel casing material if exposed to treated borated water due to a cladding breach. The WF3 safety injection system pump.s have solid stainless steel casings.
3.2.2.2.3 Loss of Material due to Pitting and Crevice Corrosion 1. This paragraph in NUREG-1800 pertains to loss of material. due to pitting and crevice corrosion in partially encased stainless steel tanks exposed to raw water due to cracking of the perimeter seal from weathering. At WF3, ESF system tanks included in the scope of license renewal are located indoors. There are no stainless steel tanks exposed to raw water in the ESF systems. 2. Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping components, piping elements, and tanks exposed to outdoor air, .including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including.chemical manufacturers. Chloride contamination of components exposed to outdoot air may However, at WF3 there are no ESF system components exposed to outdoor air in the scope of license renewal. At WF3, there are no stainless steel ESF system components located indoors near unducted air intakes. 3.0 Aging Management Review Results Page 3.2-6 3.2.2.2.4 Loss of Material due to Erosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Loss of material due to erosion could occur in the stainless steel pump miniflow recirculation orifice of a high-pressure safety injection (HPSI) pump used for normal char!;ling. The HPSI pumps at WF3 are not used for normal charging. 3.2.2.2.5* Loss of Material due to General Corrosion and Fouling that Leads to Corrosion This paragraph in NUREG-1800 applies to 8WRs only. 3.2.2.2.6 . Cracking due to Stress* Corrosion Cracking
Cracking due to stress. corrosion cracking could occur for stainless steel piping, piping components, piping elements and tanks exposed to outdoor air, including air which ha.s recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. However, at WF3 *_there are no ESF system components exposed to outdoor air in the scope of license renewal. At WF3, there are no stainless steel ESF system components located indoors near unducted air intakes. 3.2.2.2.7 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix 8 Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.2.2.2.8 Ongoing Review of Operating Experience Se.e Appendix 8 Section 8.0.4 for discussion of WF3 operating experience review programs. 3.2.2.2.9 Loss of Material due to Recu,rring Internal Corrosion A review of 1 O years of plant operating experience identified no conditions of recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in the piping components of the engineered safety features systems in the scope of license renewal. *
3.2.2.3 Time-Limited Ag_il')g.Analyses The only time-limited aging analysis identified for ttie ESF systems components is metal fatigue. This is evaluated in Section 4.3.
3.2.3 Conclusion The ESF system components that are subject to aging management review have been identified in accordance with the requirements of 1 O CFR 54.21. The aging management programs 3.0 Aging Management Review Results Page 3.2-7 \ ,I Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information selected to manage the effects of aging on ESF components are identified in Section 3.2.2.1 and in the following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the ESF components will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.2-8 Table 3.2.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of NUREG-1801 Table 3.2.1: Engineered Safety Features Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-1 Stainless steel, steel piping, Cumulative fatigue Fatigue is a time-limited Yes, TLAA Fatigue is a TLAA. piping components, and damage due to aging analysis (TLAA) to be. piping elements exposed to fatigue evaluated for the period of See Sectio"n 3.2.2.2.1. treated water (borated) extended operation: See theSRP, Section 4.3 "Metal Fatigue," for acceptable methods for meeting the requirements of 10 CFR 54.21 (c)(1 ). 3.2.1-2 Steel (with stainless steel Loss of material due A plant-specific aging Yes, verify that The WF3 safety injection system cladding) pump casings to cladding breach management program is to plant-specific pump casings are solid stainless exposed to treated water be evaluated Reference program steel. (borated) NRG Information Notice 94-addresses clad 63, "Boric Acid Corrosion-of breach See Section 3.2.2.2.2. Charging Pump Casings Caused by Cladding Cracks." 3.0 Aging Management Review Results Page 3.2-9 /

Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-3 Stainless steel partially-Loss of material due encased tanks with to pitting and crevice breached moisture barrier corrosion exposed to raw water 3.2.1-4 Stainless steel piping, piping Loss of material due components, and piping to pitting and crevice elements; tanks exposed to corrosion Air -outdoor 3.2.1-5 Stainless steel orifice Loss of material due (miniflow recirculation) to erosion exposed to treated water (borated) 3.2.1-6 BWRonly 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated for pitting and crevice corrosion of tank bottom because moisture and water can egress under the tank due to cracking of the perimeter seal from weathering. Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" A plant-specific aging management program is to be evaluated for erosion of the orifice due to extended use of the centrifugal HPSI pump for normal charging. See LER 50-275/94-023 for evidence of erosion. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-There are no stainless steel specific tanks exposed to raw water in the EFW systems in the scope of license renewal. See Section 3.2.2.2.3, Item 1. Yes, There are no ESF syster:n environmental components exposed to outdoor conditions need to air in the scope of license be evaluated renewal. See Section 3.2.2.2.3, Item 2. Yes, plant-The WF3 HPSI pumps are not specific used for normal charging. See Section 3.2.2.2.4. Page 3.2-10 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component 3.2.1-7 Stainless steel piping, piping Cracking due to components, and piping stress corrosion elements; tanks exposed to cracking air -outdoor. 3.2.1-8 Aluminum, copper alloy Loss of material due {> 15% Zn or >8% Al) piping, to boric acid piping components, and corrosion piping elements exposed to air with borated water leakage 3.2.1-9 Steel external surfaces, Loss. of due bolting exposed to air with to boric acid borated water leakage corrosion 3.2.1-10 Cast austenitic stainless Loss of fracture steel piping, piping toughness due to components, and piping thermal aging elements exposed to treated embrittlement . water (borated) >250°C (>482°F), treated water >250°C {>482°F) 3.2.1-11 BWRonly 3.0 Aging Management Review Results Aging Management Programs_ Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M10, "Boric

Acid Corrosion" Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)" Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, There are no ESF system environmental components exposed to outdoor conditions need to air in the scope of license be evaluated renewal. See Section 3.2.2.2.6. No There are no aluminum or copper alloy ESF components exposed to air with borated water leakage, in the scope of license renewal. No* Consistent with NUREG-1801. Loss of material for steel external sur:faces and bolting exposed to air with borated water leakage is managed by the Boric Acid Corrosion Program. No There are no CASS components exposed to water > 482°F in the ESF systems. Page 3.2-11 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-12 Steel, high-strength closure Cracking due to bolting exposed to air with cyclic loading, stress steam or water leakage corrosion cracking 3.2.1-13 Steel; stainless steel bolting, Loss of material due closure bolting exposed to to general (steel air-outdoor (external), air-only), pitting, and indoor, uncontrolled crevice corrosi,on (external) 3.2.1-14 Steel closure bolting Loss of material due exposed to air with steam or to general corrosion water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of high strength steel bolting exposed to air with steam or water leakage is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Loss of material for steel closure bolting exposed to indoor air is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, the Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. No As stated in Item Number 3.2.1-13, loss of material of steel
bolting exposed to air in the ESF systems is managed by the Bolting Integrity Program. However, steam or water leakage is not considered as a separate aspect of the indoor air environment. Page 3.2-12 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.2.1-15 Copper alloy, nickel alloy, Loss of preload due Chapter Xl.M18, "Bolting steel; stainless steel, to thermal effects, Integrity" stainless steel, steel; gasket creep, and stainless steel bolting, self-loosening closure bolting exposed to any environment, air -outdoor (external), raw water, treated borated water, fuel oil, treated water, air -indoor, uncontrolled < (external) 3.2.1-16 Steel containment isolation Loss of material due Chapter Xl.M2, "Water piping and components to general, pitting, . Chemistry," and Chapter (internal surfaces), piping, and crevice corrosion Xl.M32, "One-Time piping components, and
Inspection" piping elements exposed *to treated water ' 3.2.1-17 BWRonly 3.0 Aging Management Review Results ---"" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Lqss of preload for steel and stainless steel bolting is managed by the Bolting Integrity Program. There is no copper alloy or nickel alloy bolting included in the scope of license renewal for ESF systems. No Loss of material for steel containment isolation
components exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. However, these steel containment isolation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. Page 3.2-13 Waterford Steam Electric Station, Unit 3 , License Renewal Application Technical Information Table 3.2.1: Engineered Safety Features Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-18 Stainless steel containment Loss of material due Chapter Xl.M2, "Water No Loss of material for stainless isolation piping and to pitting and crevice Chemistry," and Chapter steel components exposed to components (internal corrosion Xl.M32, "One-Time treated water is managed by the surfaces) exposed to treated Inspection" Water Chemistry Control -water Primary and Secondary Program. The One-Time Inspection Program will verify . the effectiveness of the water .. chemistry control program to manage loss of material. However, these stainless steel containment isolation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. 3.2.1-19 Stainless steel heat Reduction of heat Chapter Xl.M2, "Water No Consistent with NUREG-1801. exchanger tubes exposed to transfer due to Chemistry," and Chapter Reduction of heat transfer for treated water, treated water fouling Xl.M32, "One-Time stainless steel heat exchanger (borated) Inspection" tubes exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time ' Inspection Program will verify the effectiveness of the water chemistry control program to manage reduction. of heat , transfer. 3.0 Aging Management Review Results Page 3.2-14 Table 3.2.1: Engineered Safety Features Item Number Component 3.2.1-20 Stainless steel piping, piping . components, and piping elements; tanks exposed to treated water >60°C (>140°F) 3.2.1-21 Steel (with stainless steel or, nickel-alloy cladding) safety injection tank (accumulator) exposed to treated water (borated) >60°C {>140°F) 3.2.1-22 Stainless steel piping, piping components, and piping elements; tanks exposed to treated water (borated) ,. 3.0 Aging Management Review Results / \ Aging Effect/ Mechanism Cracking due to stress corrosion cracking ' Cracking due to stress corrosion cracking Loss of material due t6 pitting and crevice corrosion Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless steel components exposed to treated borated water >140°F is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. No The WF3 safety injection tanks are maintained at containment ambient conditions (<140°F). . No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. Page 3.2-15 (

Table 3.2.1: Safety Item . Aging Effect/ Number Component

Mechanism 3.2.1-23 Steel heat exchanger Loss of material due conipohents, containment to general, pitting, isolation piping and crevice, and components (internal microbiologically surfaces) exposed to raw influenced corrosion; water fouling that leads to corrosion 3.2.1-24 Stainless steel piping, piping Loss of material due components, and piping to pitting, crevice, elements exposed to raw and water microbiologically-*influenced corrosion 3.2.1-25 Stainless steel heat Loss of material due exchanger components, to pitting, crevice, containment isolation piping and microbiologically and components (internal influenced corrosion; surfaces) exposed to raw fouling that leads to water corrosion 3.2.1-26 BWR.only 3.2.1-27 Stainless steel, steel heat Reduction of heat exchanger tubes exposed to transfer due to raw water fouling *' 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-. Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no steel ESF components exposed to raw water in the scope of license renewal. No There are no stainless steel ESF components exposed to raw water in the scope of license renewal. No There are nc;> stainless steel ESF components exposed to raw . water in the scope *ot license renewal. No There are no steel or stainless steel ESF components exposed to raw water in the scope of license renewal. Page 3.2-16 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management. Number Component Mechanism Progr;;ams 3.2.1-28 Stainless steel piping, piping Cracking due to Chapter Xl.M21A, "Closed components, and piping stress corrosion Treated Water Systems" elements exposed to closed-cracking cycle cooling water >60°C {>140°F) 3.2.1-29 Steel piping, piping Loss of material due . Chapter Xl.M21A, "Closed components, and piping to general, pitting, Treated Water Systems" elements exposed to closed-and crevice corrosion cycle cooling water 3.2.1-30
Steel heat exchanger Loss of material due Chapter Xl.M21A, "Closed components exposed to to general, pitting, Treated Water Systems" closed-cycle cooling water crevice, and galvanic . corrosion 3.2.1-31 Stainless steel heat. Loss of material due Chapter Xl.M21A, "Closed exchanger components, . to pitting and crevice Treated Water Systems" piping, piping components, corrosion and piping elements exposed to closed-cycle cooling water 3.0 Aging Management Review Results
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no stainless steel ESF components exposed to closed-cycle cooling water >140°F in the scope of license renewal. No There are no steel ESF components exposed to closed-cycle cooling water in the scope of license renewal, other than the heat exchanger components compared to item 3.2.1-30 below. Nb Consistent with NUREG-1801. Loss of material of steel heat exchanger components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material .of stainless steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closec;I Treated Water Systems Program. Page 3.2-17 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-32 Copper alloy heat exchanger Loss of material due components, piping, piping to pitting, crevice, components, and piping and galvanic elements exposed to corrosion cycle cooling water 3.2.1-33 Copper alloy, stainless steel Reduction-of heat Heat exchanger tubes transfer due to exposed to closed-cycle fouling cooling water 3.2.1-34 Copper alloy (>15% Zn or Loss of material due >8% Al) piping, piping to selective leaching components, and piping elements, heat exchanger components exposed to closed-cycle cooling water 3.2.1-35 Gray cast iron motor cooler Loss of material due exposed to treated water to selective leaching 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M33, "Selective Leaching" Chapter Xl.M33, "Selective Leaching" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no copper alloy ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel ESF system heat exchanger tubes exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. There are no copper alloy ESF heat exchanger tubes exposed to closed-cycle cooling water in the scope of license renewal. No There are no copper alloy (>15% Zn or >8% Al) ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No There are no gray cast iron ESF system components exposed to closed-cycle cooling water in the scope of license renewal. Page 3.2-18 Table 3.2.1: Engineered Safety Features Item Aging Effect/ . . Number Component Mechanism 3.2.1-36 Gray cast iron piping, piping Loss of material due components, and piping to selective leaching elements exposed to closed-cycle cooling water 3.2.1-37 Gray cast iron piping, piping Loss of material due components, and piping to selective leaching elements exposed to soil 3.2.1-38 BWRonly 3.2.1-39 Steel containment isolation Loss of material due piping and components to general corrosion. (external surfaces) .exposed to condensation (external) 3.0 Aging Management Review Results \ Aging Management Programs Chapter Xl.M33, "Selective Leaching" Chapt.er Xl.M33, Leaching" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical. Information Further Evaluation Recommended .Discussion No There are no gray cast iron ESF system components exposed to closed-cycle cooling water in the scope of license renewal. No There are no gray cast iron ESF system components exposed to soil in.the scope of license renewal. No Loss of material for steel components externally exposed to condensation is managed by the External Surfaces Monitoring Program. However, these steel containment is9lation components were evaluated as part of their respective systems and were compared to other NUREG-1801 line items. Page 3.2-19 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-40 Steel ducting, piping, and Loss of material due components (external to general corrosion ' surfaces), ducting, closure bolting, containment isolation piping and components (external surfaces) exposed to air -indoor, uncontrolled (external) 3.2.1-41 Steel external surfaces Loss of material due exposed to air -outdoor to general corrosion (external) 3.2.1-42 Aluminum. piping, piping Loss of material due comf:!onents, and piping to pitting and crevice elements exposed to air -corrosion outdoor 3.2.1-43 BWRonly 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of external surfaces of steel components exposed to indoor air is managed by the External Surfaces Monitoring Program. No There are no steel ESF system components exposed to outdoor air in the scope of license renewal. No -There are no aluminum ESF system components exposed to outdoor air in the scope of license renewal. Page 3.2-20 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component. Mechanism Programs 3.2.1-44 Steel piping and Loss of materic;il due Chapter Xl.M38, components (internal ta general corrosion "Inspection of Internal surfaci;!s), ducting and Surfaces in Miscellaneous components (internal Piping and Ducting* surfaces) exposed to air-Components" * . indoor, uncontrolled (internal) " 3.0 Aging Management Review Results \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for many components. Loss of material from the internal surfaces of steel components exposed to air -indoor is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. For the fire protection system portable smoke exhaust fan housing (Table 3.3.2-6), and for abandoned piping in the secondary sampling system (Table 3.3.2-15-34), loss of material from the internal surface is managed by the Periodic SuNeillance and Preventive Maintenance Program. The External Surfaces Monitoring Program manages loss of material for external carbon steel components by visual inspection of external surfaces. Page 3.2-21 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-45 Steel encapsulation Loss of material due components exposed to air -to general, pitting, indoor, uncontrolled and crevice corrosion (internal) 3.2.1-46 BWR only 3.2.1-47 Steel encapsulation Loss of material due components exposed to air to general, pitting, with borated water leakage crevice, and boric (internal) acid corrosion .. 3.2.1-48 Stainless steel piping, piping Loss of material due components, and piping to pitting and crevice elements (internal corrosion tanks exposed to condensation (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion (continued) For those components where internal carbon steel surfaces are exposed to the same environment as external surfaces (Tables 3.3.2-X), external surface conditions will be representative of internal surfaces. Thus,* loss of material on internal carbon steel surfaces is also managed by the External
Surfaces Monitoring Program. No The WF3 containment spray system does not use encapsulation components. No The WF3 containment spray system does not use encapsulation components. -No There are no stainless steel ESF system components internally exposed to condensation in the scope of license renewal. Page 3.2-22 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.2.1-49 Steel piping, piping Loss of material due Chapter Xl.M39, components, and piping to general, pitting, "Lubricating Oil Analysis," elements exposed to and crevice corrosion and Chapter Xl.M32, "One-lubricating oil Time Inspection" 3.2.1-50 Copper alloy, stainless steel Loss of material due Chapter Xl.M39, piping, piping components,
to pitting and crevice "Lubricating Oil Analysis," . and piping elements . corrosion and Chapter Xl.M32, "One-exposed to lubricating oil Time Inspection" 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended , Discussion No Consistent with NUREG-1801. Loss of material for steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for copper alloy and stainless steel components exposed to lube oil (Tables 3.1.2-X) is managed by the Oil Analysis Program. The One-Time Inspection Program will
verify the effectiveness* of the Oil Analysis Program* to manage loss of material. Page 3.2-23 Table 3.2.1 :. Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-51 Steel, copper alloy, stainless Reduction of heat steel heat exchanger tubes transfer due to exposed to lubricating oil fouling 3.2.1-52 Steel (with coating or Loss of material due wrapping) piping, piping to general, pitting, components, and piping crevice, and elements to soil or microbiologically-concrete influenced corr9sion 3.2.1-53 Stainless steel, nickel alloy Loss of material due piping, piping components, to pitting and crevice and piping elements corrosion exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Qhapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground .Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for steel, and stainless steel heat exchanger tubes exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage reduction of heat transfer. There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the ESF systems in the scope of license renewal. No There are no steel ESF system components exposed to soil or concrete in the scope of license renewal. No There are no ESF system piping components exposed to soil or concrete in the scope of license renewal. Page 3.2-24 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-53.5 Steel; stainless steel, nickel Loss of material due alloy underground piping, to general (steel piping components, and only), pitting and piping elements exposed to crevice corrosion air-indoor uncontrolled or (external) 3.2.1-54 BWRonly 3.2.1-55 , Steel piping, piping None components, and piping elements exposed to concrete 3.2.1-56 Aluminum piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (internal/external) 3.2.1-57 Copper alloy piping*, piping None components, and piping elements exposed to air -indoor, uncontrolled (external), gas 3.0 Aging Management Review.Results Aging Management Programs Chapter Xl.M41, "Buried . and Underground Piping and Tanks" None, provided 1) attributes of the concrete are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG-1557, and 2) plant* OE indicates no degradation ,of the concrete None None Waterford Steam Electric Station, Unit 3 License .Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no ESF system underground piping components in the scope of license renewal. No, if conditions There are no ESF system are met. components* embedded in concrete in the scope of license renewal. NA-NoAEM or Con'sistent with NUREG-1801. AMP This item applies to components in Table 3.1.2-5-1. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air) environments. This item applies to components in Table 3.1.2-3. Page 3.2-25 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-58 Copper alloy (S15% Zn and None S8% Al) piping, piping components, and piping elements exposed to air with borated water leakage 3.2.1-59 Galvanized steel ducting, None piping, and components exposed to air-indoor, controlled (external) 3.2.1-60 Glass piping elements None exposed to air -indoor, uncontrolled (external), lubricating oil, raw water, treated water, treated water (borated), air with borated water leakage, condensation (internal/external), gas, closed-cycle cooling water, air -outdoor 3.2.1-61 Nickel alloy piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (external) 3.2.1-62 Nickel alloy piping, piping None components, and piping elements exposed to air with borated water leakage 3.0 Aging Management Review Results Aging Management Programs None None None None None 1* Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion NA-NoAEM or There are no copper alloy ESF AMP system components exposed to air with borated water leakage in the scope of license renewal. NA-NoAEM or Galvanized steel is evaluated as AMP steel. NA-NoAEM or Consistent with NUREG-1801. AMP for relevant (indoor air and treated borated water) environments. This item applies to components in Table 1. NA-NoAEM or Consistent with NUREG-1801. AMP NA-NoAEM or Consistent with NUREG-1801. AMP Page 3.2-26 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-63 Stainless steel piping, piping None components, and piping elements exposed to air -indoor, uncontrolled (external), air with borated water leakage, concrete, gas, air -indoor, uncontrolled (internal) . 3.2.1-6"4 Steel pipir19, piping None components, and piping elements exposecl to air -indoor, controlled (external), gas 3.2.1-65 Any material, piping, piping Wall thinning due to. components, and piping erosion elements exposed to treated : water, treated water *' (borated) 3.2.1-66 Metallic piping, piping Loss of material due components, and tanks to recurring internal exposed to raw water or corrosion wastewater . 3.0 Aging Review Results ( Aging Management Programs None None ,. Chapter Xl.M17, "Flow-* Accelerated Corrosion" .. A plant-specific aging management program is to be evaluated to address recurring internal corrosion Waterford Steam Station, Unit 3 License Renewal Application Technical Information . Further Evaluation Recommended Discussion NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air, air with borated water.leakage and gas) environments. ' NA-NoAEM or There are no steel ESF system AMP components exposed to controlled indoor air or gas in the scope of license renewal. No " The materials, environments and operating conditions of ESF system components are not conducive to erosion. Yes, plant-specific Recurring internal corrosion was not identified in*the WF3 engineered safety features systems in the scope of license renewal. . See Section 3.2.2.2.9 . Page 3.2-27 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-67 Stainless steel or aluminum Cracking due to tanks (within the scope of stress corrosion Chapter Xl.M29, cracking "Aboveground Metallic Tanks") exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist air, condensation 3.2.1-68 Steel, stainless steel, or Loss of material due aluminum tanks (within the to general (steel scope of Chapter Xl.M29, only), pitting, and "Aboveground Metallic crevice corrosion Tanks") exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist .air, condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, . "Aboveground Metallic Tanks" Chapter Xl.M29, "Aboveground Metallic Tanks" : Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. No -At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Page 3.2-28 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-69 Insulated steel, stainless Loss of material due steel, copper alloy, or to general (steel, and aluminum, piping, piping copper alloy only), components, and tanks pitting, and crevice exposed to condensation, corrosion C!ir-outdoor 3.2.1-70 Steel, stainless steel or Loss of material due aluminum tanks (within the to general (steel scope of Chapter Xl.M29, only}, pitting and "Aboveground Metallic crevice corrosion. Tanks") exposed to treated water, treated borated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, "Aboveground Metallic Tanks," (for tanks only)-Chapter Xl.M29, "Aboveground Metallic Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for insulated stainless steel components exposed to condensation. Loss of material is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy > 15% Zn or > 8% Al piping components or tanks exposed to condensation or outdoor air in the WF3 engineered safety features systems in the scope of license renewal. No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Page 3.2-29 Table 3.2.1: Engineered Safety Features Item Aging Effect/ Number Component Mechanism 3.2.1-71
Insulated stainless steel, Cracking due to aluminum, or copper alloy (> stress corrosion 15% Zn) piping, piping cracking components, and tanks exposed to condensation, air-outdoor 3.2.1-72 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks *with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-cycle delamination, cooling water; raw water, rusting, or physical treated water, *treated damage, and spalling water, or for CE!mentitious oil coc:ltings/linings 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, "Aboveground Metallic Tanks," (for tanks only) / Chapter Xl.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat . and Tanks" ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further-Evaluation Recommended Discussion No Consistent with NUREG-1801 for insulated stainless steel components exposed to condensation. Cracking is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy > 15% Zn or> 8% Al piping components or tanks exposed* to condensation or outdoor air in the WF3 engineered safety features systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of coating or lining integrity for metallic components with internal coating or linings is managed by the Coating Integrity Program. Page Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Table 3.2.1: Engineered Safety Features ' Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.2.1-73 Metallic piping, piping Loss of material. due Chapter Xl.M42, "lntemal No* Consistentwith NUREG-1801. components, heat*
to general, pitting, Coatings/Linings for In-Loss of material for metallic exchangers, tanks with crevice, and
Scope Piping, Piping components with internal
internal coatings/linings microbiologically Components, Heat coating or linings is managed by exposed to closed-cycle
influenced corrosion; Exchangers, and Tanks" the Coating Integrity Program. . cooling water, raw water *. fouling that leads to treated water, treated corrosion borated water, or lubricating oil 3.2.1-74 . Gray cast iron piping Loss of material due Chapter Xl.M42, "Internal No There are no gray cast iron components with internal to selective leachi.ng Coatings/Linings for In-components with internal coatings/linings exposed to Scope Piping, Piping coatings or linings in the ESF closed-cycle cooling water, Components, He.at
systems in the scope of license raw water, or treated water Exchangers, and Tanks" renewal. 3.0 Aging Management Review Results Page 3.2-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Notes for Tables 3.2.2-1 through 3.2.2-4-2 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801.identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and. environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 201. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 202. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 3.0 Aging Management Review Results Page 3.2-32 Table 3.2.2-1 Containment Spray System 'Summary of Aging Management Evaluation Table 3.2.2-1: Containment Spray System Aging Effect , Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air -indoor , Loss. of material Bolting Integrity
boundary, (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion .. Bolting. Pressure Carbon steel , Air...: indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary . steel (ext) * '* Flow element Pressure Stainless Air-indoor ., None None boundary steel (ext) Flow element Pressure Stainless Treated borated Loss of material
Water Chemistry boundary steel water (int) Control -Primary and Secondary Heat exchanger Pressure Carbpn steel Air-indoor Loss of material *Boric Acid (channel head) . clad with (ext) Corrosion *stainless steel Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (channel head) . boundary clad with (ext) Monitoring stainless steel *' Heat exchanger Pressure
Carbon steel Treated borated Cracking Water Chemistry (channel head) .. boundary . clad with water> 140°F Control -Primary *stainless steel (int) and Secondary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1so11tem ,Item Notes V.E.EP-70 3.2.1-13 B V.E.E-41 " 3.2.1-9 A V.E.EP-69 3.2.1-15 B V.E.EP-69 . 3.2.1-15 B V.F.EP-18 3.2.1-63 A . V.A.EP-41 3.2.1-22 A, 201 3.2.1-9. A V.E.E-44 3.2.1-40 A V.A.E-12 3.2.1-20 C, 201 Page 3.2-33 Table 3.2.2-1 : Containment Spray System Aging Effect Intended Requiring Component Type Function Material Environment Management Heat exchanger Pressure Carbon steel Treated borated Loss of material (channel head) boundary clad with water> 140°F stainless steel (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) boundary (int) Heat exchanger Pressure Carbon steel Treated water Loss of coating (shell) boundary with internal (int) integrity coating Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) boundary with internal (int) coating Heat exchanger Pressure Carbon steel Treated borated Cracking (tube sheet) boundary clad with water> 140°F stainless steel (ext) Heat exchanger Pressure Carbon steel Treated borated Loss of material (tube sheet) boundary clad with water> 140°F stainless steel (ext) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Water Chemistry Control -Closed Treated Water Systems Coating Integrity Coating Integrity Water Chemistry Control -Primary and Secondar-Y Water* Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 C, 201 V.A.E-28 3.2.1-9 A V.E.E-44 3.2.1-40 A V.A.EP-92 3.2.1-30 A V.A.E-401 3.2.1-72 B V.A.E-414 3.2.1-73 B V.A.E-12 3.2.1-20 C, 201 V.A.EP-41 3.2.1-22 C, 201 Page 3.2-34 Table 3.2.2-1: Containment Spray System Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel Treated water (tube sheet) boundary. clad with (int) stainless steel Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water (int) Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water> 140°F (int) Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water> 140°F (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water> 140°F (int) Heat exchanger Pressure Stainless Treated water (tubes) boundary steel (ext) Heat exchanger Heat transfer Stainless Treated water (tubes) steel (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-93 3.2.1-31 A V.A.EP-41 3.2.1-22 C, 201 V.A.E-20 3.2.1-19 A, 201 V.A.E-12 3.2.1-20 C, 201 V.A.EP-41 3.2.1-22 C, 201 V.A.E-20 3.2.1-19 A, 201 V.A.EP-93 3.2.1-31 A V.A.EP-96 3.2.1-33 A Page 3.2-35 Table 3.2.2-1: Containment Spray System Intended Component Type Function Material Environment Heat exchanger Pressure Carbon steel (water jacket) boundary (ext) Heat exchanger Pressure Carbon steel Air-Indoor (water jacket) boundary (ext) .. Heat exchanger Pressure Carbon steel Lube oil (ext) (water jacket) boundary Heat exchanger Heat transfer Carbon steel Lube oil (ext) (water jacket) Heat exchanger Pressure Carbon steel Treated water . (water jacket) boundary (int) Heat exchanger Heat transfer Carbon steel Treated.water (water jacket) (int) Nozzle Pressure Stainless Air-indoor boundary steel (ext) Flow control* Nozzle Pressure Stainless Air -indoor (int) boundary steel Flow control Orifice Pressure Stainless Air-indoor boundary steel (ext) Flow control 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material External Surfaces Loss of material Oil Analysis
Reduction of heat Oil Analysis transfer* Loss of material Water Chemistry Control -Closed . Treated Water Systems Reduction of heat Water Che'mistry transfer Control -Closed Treated Water Systems None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.E-28 3.2.1-9 A V.E.E-44 3.2.1-40 A V.A.EP-77 3.2.1-49 C, 202 V.A.EP-75 3.2.1-51 A,202 V.A.EP-92 3.2.1-30 A Vll.F1 .AP-204 3.3.1-'50 c V.F.EP-18 3.2.1-63 A V.F.EP-82 3.2.1-63 A V.F.EP-18 3.2.1-63 A Page 3.2-36 Table 3.2$1: Containment Spray System .. *Intended Component Type Function Material Orifice Pressure Stainless boundary steel Flow control Piping
Pressure *Stainless boundary . steel Piping Pressure Stainless boundary steel Piping Pressure . Stainless
boundary *steel Piping Pressure .$tainless boundary steel Piping Pressure Stainless boundary steel* Piping Pressure *Stainless boundary steel Pump casing Pressure Stainless boundary steel *. Pump casing Pressure Stainless boundary steel Separator Pressure Stainless boundary steel 3.0 Aging Management Review. Results i I \ <. Environment
Treated borated water (int) Air-indoor (ext) Air -indoor (int) Treated borated water (int) Treated borated water> 140°F (int)* Treated borated water> 140°F (int) Treated borated water> 140°F (int) Air-indoor (ext) Treated borated
water (int) Air-indoor (ext) Aging Effect Aging i Requiring Management : Management Programs .Loss of Water Chemistry Control -Primary and Secondary None None None None Loss of material. Water Chemistry Control -Primary . and Secondary Cracking Water Chemistry : Control -Primary and Secondary Cracking -fatigue . TLAA ;_metal
fatigue Loe;s of material Water Chemistry Control -Primary and Secondary None None** Loss of material Water Chemistry Control -Primary and Secondary None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 A, 201 .. 3.2.1-63 A V.F.EP-82 3.2.1-63 A
V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A,201 V.F.EP-18 3.2.1-63 A 3.2.1-22 A, 201 V.F .. EP-18 3.2:1-63 A Page 3.2-37 I Table 3.2.2-1: Containment Spray System Aging ,Effect Intended Requiring Component Type Function Material Environment Management Separator Pressure Stainless Treated borated Loss of material boundary steel water (int) Filtration Thermowell Pressure Stainless Air-indoor None boundary steel (ext) Thermowell Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Thermowell Pressure Stainless Treated borated Cracking -fatigue t:>oundary steel water> 140°F (int) Thermowell Pressure* Stainless Treated borated Loss of material boundary steel water> 140°F (int) Tubing Pressure Stainless Air-indoor None boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material boundary steel water (int) Tubing Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated Cracking -fatigue boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary TLAA -metal
fatigue Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c Page 3.2-38 Table 3.2.2-1: Containment Spray System Aging Effect Intended Requiring Component Type Function Material Environment Management Tubing Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) Valve body Pressure Stainless Air-indoor None boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material boundary steel water (int) Valve body Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Cracking -fatigue boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information NU REG-Table 1 1801 Item Item Notes V.A.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.A.EP-41 3.2.1-22 A, 201 V.A.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 c V.A.EP-41 3.2.1-22 A, 201 Page 3.2-39 Table 3.2.2-2 Safety Injection System Summary of Aging Management Evaluation Table 3.2.2-2: Safety Injection System Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Bolting Integrity boundary Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Boric Acid boundary Corrosion Bolting Pressure Carbon steel Air'.'""" indoor (ext) Loss of preload Bolting Integrity boundary Bolting Pressure High strength Air-indoor (ext) Cracking Bolting Integrity boundary steel Bolting Pressure High strength Air -indoor (ext) Loss of material Bolting Integrity boundary steel Bolting Pressure High strength Air-indoor (ext) Loss of j:>reload Bolting Integrity boundary steel Bolting Pressure *Stainless Air-indoor (ext) Loss of preload Bolting Integrity boundary steel Flow element Pressure Stainless Air-indoor (ext) None* None boundary steel Flow control Flow element Pressure Stainless Treated borated Loss of material Water Chemistry boundary steel water (int) Control -Primary Flow control and Secondary 3.0 Aging Management Review Results WatE!rford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.E.EP-70 3.2.1-13 B V.E.E-41 3.2.1-9 A V.E.EP-69 3.2.1-15 B V.E.E-03 3.2.1-12 B V.E.EP-70 3.2.1-13 B V.E.EP-69 3.2.1-15 B V.E.EP-69 3.2.1-15 B V.F.EP-18 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 Page 3.2-40 Table 3.2.2-2: Safety Injection System Intended Component Type Function Material Environment Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Flow element Pressure Stainless Treated borated boundary steel water> 140°F Flow control (int) Heat exchanger Pressure Cc;irbon steel Air-indoor (ext) (shell) boundary Heat exchanger Pressure Carbon steel Air-indoor (ext) (shell) boundary Heat exchanger Pressure Carbon steel Treated water (shell) boundary with internal (int) coating Heat exchanger Pressure Carbon steel Treated water (shell) boundary with internal (int) coating Heat exchanger Pressure Stainless Treated borated (tubes) boundary steel water (int) Heat exchanger Heat transfer Stainless Treated borated (tubes) steel water (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Cracking Cracking -fatigue Loss of material Loss of material Loss of material Loss of coating integrity Loss of material Loss of material Reduction of heat transfer Aging Management Programs Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01 .E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.01.E-28 3.2.1-9 A External Surfaces V.E.E-44 3.2.1-40 A Monitoring Coating Integrity V.0.1.E-401 3.2.1-72 B Coating Integrity V.01.E-414 3.2.1-73 B Water Chemistry V.01.EP-41 3.2.1-22 C, 201 Control -Primary and Secondary Water Chemistry V.01.E-20 3.2.1-19 A, 201 Control -Primary and Secondary Page 3.2-41 Table 3.2.2-2: Safety Injection System Aging Effect Intended Requiring Component Type Function Material Environment Management Heat exchanger Pressure Stainless Treated water Loss of material (tubes) boundary steel (ext) Heat exchanger Heat transfer Stainless Treated water Reduction of heat (tubes) steel (ext) transfer Orifice Pressure Stainless Air -indoor (ext) None boundary steel Flow control Orifice Pressure Stainless Treated borated Loss of material boundary steel water (int) Flow control Orifice Pressure Stainless Treated borated Cracking boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated b9rated Cracking -fatigue boundary steel water> 140°F Flow control (int) Orifice Pressure Stainless Treated borated Loss of material boundary steel water> 140°F Flow control (int) Piping Pressure Stainless Air-indoor (ext) None boundary steel 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01.EP-93 3.2.1-31 A V.01.EP-96 3.2.1-33 A V.F.EP-18 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 V.01 .E-12 3.2.1-20 A, 201 V.01 .E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A Page 3.2-42 Table Safety Injection System Intended Component Type Function Material Erivfronment Piping Pressure Stainless Air -indoor (int) boundary steel Piping Pressure Stainless Gas (int) boundary steel Piping Pressure Stainless Treated borated boundary steel water (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) , Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Pump casing Pressure Stainless Air -indoor (ext) boundary steel Pump casing Pressure Stainless Treated borated boundary steel water (int) Pump *casing Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management .Programs None None None None Loss of material Water Chemistry Control -Primary and Secondary Cracking . Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application . Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-82 3;2.1-63 A VFEP-22 3.2.1-63 A V.01.EP-41 3.2.1-22 A,201 V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A 3.2.1-22 A, 201 V.01.E-12 3.2.1-20 A, 201 Page 3.2-43 Table 3.2.2-2: Safety Injection System Aging Effect Intended Requiring Component Type Function Material Environment Management Pump casing Pressure Stainless Treated borated Loss of material boundary steel water > 140°F (int) Tank Pressure Carbon steel Air -indoor (ext) Loss of material boundary clad with stainless steel Tank Pressure Carbon steel Air -indoor (ext) Loss of material boundary clad with stainless steel Tank Pressure Carbon steel Gas (int) None boundary clad with stainless steel Tank Pressure Carbon steel Treated borated Loss of material boundary clad with water (int) stainless steel Thermowell Pressure Nickel alloy Air -indoor (ext) None boundary Thermowell Pressure Nickel alloy Treated borated Loss of material boundary water (int) Tubing Pressure Stainless Air-indoor (ext) None boundary steel Tubing Pressure Stainless Treated borated Loss of material boundary steel water (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.D1.EP-41 3.2.1-22 A, 201 V.D1.E-28 3.2.1-9 A External Surfaces V.E.E-44 3.2.1-40 A Monitoring None V.F.EP-22 3.2.1-63 c Water Chemistry V.D1 .EP-41 3.2.1-22 A, 201 Control -Primary and Secondary None V.F.EP-17 3.2.1-61 A V.F.EP-115 3.2.1-62 Water Chemistry ----G Control -Primary and Secondary None V.F.EP-18 3.2.1-63 A Water Chemistry V.D1.EP-41 3.2.1-22 A, 201 Control -Primary and Secondary Page 3.2-44 Table 3.2.2-2: Safety Injection System Intended Component Type Function Material Enyironment Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Tubing Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Air-indoor (ext) boundary steel Valve body Pressure Stainless Gas (int) boundary steel Valve body Pressure Stainless Treated borated boundary steel water (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated boundary steel water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 V.F.EP-18 3.2.1-63 A V.F.EP-22 3.2.1-63 A V.01.EP-41 3.2.1-22 A, 201 V.01.E-12 3.2.1-20 A, 201 V.01.E-13 3.2.1-1 A V.01.EP-41 3.2.1-22 A, 201 Page 3.2-45 Table 3.2.2-3 Containment Penetrations Summary of Aging Management Evaluation Table 3.2.2-3: Containment Penetrations Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary steel (ext) Bolting Pressure Stainless Treated borated Loss of material Bolting Integrity boundary steel water (ext) Bolting Pressure Stainless Treated borated Loss of preload Bolting Integrity boundary steel water (ext) Insulated piping Pressure Stainless Condensation Cracking External Surfaces components boundary steel (ext) Monitoring Insulated piping* Pressure Stainless Condensation Loss of material External Surfaces components boundary steel (ext) . Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Piping Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces boundary Monitoring Piping Pressure Stainless Air-indoor None None boundary steel (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.E.EP-70 3.2.1-13 B V.E.EP-69 3.2.1-15 B V.E.EP:..59 3.2.1-15 B ----H V.E.EP-120 3.2.1-15 B V.C.E-406 3.2.1-71 A V.C.E-403 3.2.1-69 A V.E.E-44 3.2.1-40 A V.A.E-29 3.2.1-44 E V.F.EP-18 3.2.1-63 A Page 3.2-46 Table 3.2.2-3: Containment Penetrations Intended Component Type Function Material Environment Piping Pressure Stainless Air -indoor (int) boundary steel Piping Pressure Stainless Treated borated boundary steel water (ext) Piping Pressure Stainless Treated borated boundary steel water (int) Piping Pressure Stainless Treated borated boundary steel water > 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated borated boundary steel water> 140°F (int) Piping Pressure Stainless Treated water boundary steel (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-82 3.2.1-63 A V.A.EP-41 3.2.1-22 C, 201 V.A.EP-41 3.2.1-22 C, 201 V.01.E-12 3.2.1-20 C, 201 V.01.E-13 3.2.1-1 c V.01.EP-41 3.2.1-22 C, 201 V.C.EP-95 3.2.1-31 A V.E.E-44 3.2.1-40 A V.A.E-29 3.2.1-44 E Page 3.2-47 Table 3.2.2-3: Containment Penetrations Aging Effect Intended Requiring Component Type Function Material Environment Management Valve body Pressure Stainless Air-indoor None boundary steel (ext) Valve body Pressure Stainless Air -indoor (int) None boundary steel Valve body Pressure Stainless Treated borated Loss of material boundary steel water (int) Valve body Pressure Stainless Treated borated Cracking boundary steel water> 140°F (int) Valve body Pressure Stainless Treated borated Cracking -fatigue boundary steel water > 140°F (int) Valve body Pressure Stainless Treated borated Loss of material boundary steel water> 140°F (int) Valve body Pressure Stainless Treated water Loss of material boundary steel (int) 3.0 Aging Management Review Results Aging Management Programs None None Water Chemistry 9ontrol -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.F.EP-18 3.2.1-63 A V.F.EP-82 3.2.1-63 A V.A.EP-41 3.2.1-22 C, 201 V.01.E-12 3.2.1-20 C, 201 V.01.E-13 3.2.1-1 c V.01.EP-41 3.2.1-22 C, 201 V.C.EP-95 3.2.1-31 A Page 3.2-48 Table 3.2.2-4-1 Containment Spray System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.2.2-4-1 :Containment Spray System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity V.E.EP-69 3.2.1-15 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity V.E.EP-70 3.2.1-13 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid V.E.E-41 3.2.1-9 A boundary (ext) Corrosion Orifice Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1c63 A boundary steel (ext) Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary . steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary . *steel (int) Miscellaneous Piping and Ducting *' Components 3.0 Aging Management Review Results Page 3.2-49 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.2.2-4-1 :Containment Spray System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Pump casing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.A.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results P?ge 3.2-50 Table 3.2.2-4-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Safety Injection System . Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.2.2-4-2:Safety Injection System, Nonsafety-Related Components Affecting Safety-Related Systems* Aging Effect Aging Intended Requiring Management .NUREG-Table 1 Component Type Function Material Environment Management. .Programs 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity. V.E.EP-69 3.2.1-15 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity V.E.EP-70 3.2.1-13 B" boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid V.E.E-41 3.2.1-9 .A boundary (ext) Corrosion Piping Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material

Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and* Secondary Pump casing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless* Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.2-51 (

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.2.2-4-2:Safety Injection System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Trap Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Tubing Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Tubing Pressure Stainless Treated borated Loss of material Water Chemistry V.D1.EP-.tl1 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None V.F.EP-18 3.2.1-63 A boundary steel (ext) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry V.01.EP-41 3.2.1-22 A, 201 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.2-52 3.3 AUXILIARY SYSTEMS 3.3.1 Introduction Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of the aging management reviews for those components in the auxiliary systems which are subject to aging management review. The following systems are addressed in this section (system descriptions are available in the referenced sections).

Chemical and Volume Control. (Section 2.3.3.1)
Chilled Water (Section 2.3.3.2)
Component Cooling and Auxiliary Component Cooling Water (Section 2.3.3.3)
Compressed Air (Section 2.3.3.4)
Containment Cooling HVAC (Section 2.3.3.5)
Control Room HVAC (Section 2.3.3.6)
Emergency DiesE!I Generator (Section 2.3.3.7)
Fire Protection -Water (Section 2.3.3.8)
Fire Protection RCP Oil Collection (,Section 2.3.3.9)
Fuel Pool Cooling Purification (Section 2.3.3.1 O)
Nitrogen*(Section 2.3.3.11) .
Miscellaneous HVAC (Section 2.3.3.12) * -Auxiliary Diesel Generator (Section 2.3.3.13)
Plant Drains (Section 2.3.3.14)
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) (Section 2.3.3. 15) Table 3.3.1, Summary of Aging Management Programs for Auxiliary* Systems Evaluated in . . Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the auxiliary systems component group. This table uses the format described in the . introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.3.2 Results The*following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for auxiliary systems. * *
Table 3.3.2-1 Chemical and Volume Control System-Summary of Aging Management Evaluation Table 3.3.2-2 _Chilled Water System-Summary of Aging Management Evaluation Table 3.3.2-3 Component Cooling and Auxiliary Component Cooling Water System_:_ Summary of Aging Management Evaluation
Table 3.3.2-4 Compressed Air System-Summary of Aging Management Evaluation *
Table 3.3.2-5 Containment Cooling HVAC System-Summary of Aging' Management Evaluation 3.0 Agi_ng Management Review Results Page 3.3-1 I ...

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information

Table 3.3.2-6 Control Room HVAC System-Summary of Aging Management Evaluation
Table 3.3.2-7 Emergency Diesel Generator System-Summary of Aging Management Evaluation *
Table 3.3.2-8 Fire Protection -Water System-Summary of Aging Management Evaluation
Table 3.3.2-9 Fire Protection RCP Oil Collection System-Summary of Management Evaluation
Table 3.3.2-10 Fuel Pool Cooling and Purification of Aging
Management Evaluation
Table 3.3.2-11 Nitrogen System-Summary of Aging Management Evaluation
Table-3.3.2-12 Miscellaneous HVAC Systems-Summary of Aging Management Evaluation
Table 3.3.2-13Auxiliary Diesel Generator System-Summary of Aging Management Evaluation
Table 3.3.2-14 Plant Drains -Summary of Aging Management Evaluation * * * *
Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) Table 3.3.2-15-1 Air Evacuation System, Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation Table 3.3.2-15-2 Airborne Radioactivity Removal System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-3 Annulus Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation
Table 3.3.2-15-4 Auxiliary Steam System, Nonsafety-Related Components Affecting . Safety-Related System$-Summary of Aging Management Evaluation Table 3.3.2-15-5 Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Management Review Results Page 3.3-2 Waterford Steam Electric' Station, Unit 3 License Renewal Application Technical Information
Table 3.3.2-15-6 Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *-Table 3.3.2-15-7 *Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation * * * * *
Table 3.3.2-15-8 Chemical Feed System, Nonsafety-Related Components Affecting . Safety-Related Systems-Summary of Management Evaluation I Table 3.3.?-15-9 Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-10 Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-12 Compressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-13 Containment Atmosphere Purge System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3*.3:2-15-14 Containment Atmosphere Release System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation
Table 3.3.2-15-15 Containment Building, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *
Table 3.3.2-15-16 Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-17 Emergency Diesel Generator System, Nor:isafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Review Results Page 3.3-3
* * * * * * * * * *
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-18 Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related* Systems-Summary of Aging Management Evaluation Table 3.3.2-15-'19 Fuel Pool Cooling and Purification System, Nonsafety-Related Cornponents Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-20 Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-21 Hot Machine Shop and Decqn Facility Ventilation System, Related Components Affectfng Safety-Related Systems.:..._Summary of Aging Management Evaluation Table 3.3.2-15-22 Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-23 Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-'Summary of Aging Management Evaluation
Table 3.3.2-15-24 Nitrogen System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-25 Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related *Systems-Summary of Aging Management *Evaluation *
Table 3.3.2-15-26 Potable Water System, Nonsafety-Related Com.porients Affecting . Safety-Related Systems-Summary of Aging Management Evaluation. Table 3.3.2,..15-27 Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-28 Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary:of Aging Management Evaluation Table. 3.3.2-15-29 Radiation Monitoring System, Nonsafety-Related Components .. Affecting Safety-Related Systems-Summary of Aging Management Evaluation 3.0 Aging Management Review Results
Page 3.3-4
* * * * *
Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Table 3.3.2-15-30 Reactor Auxiliary Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-31 Reactor Cavity Cooling System, Nonsafety-Related Components Affecting Systems-Summary of Aging Management Evaluation Table 3.3.2-15-32 Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3_.2-15-33 Secondary Sampling System, Nonsafety-Related Components Affecting Systems-:-Sumniary of Aging Management Evaluation Table 3.3.2-15-34 Solid Waste Management System, Nonsafety-Relatep Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-35 Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation Table 3.3.2-15-36 Turbine Building Cooling Water System, Nonsafety-Related Componehts Affecting Safety-Related Systems-Summary of Aging . Management Evaluation 3.3.2.1 Materials, Environments; Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the auxiliary systems. Programs are described in Appendix B.
Further details are provided in the system tables. 3.3.2.1.1 Chemical and Volume Control Materials Chemical c;lnd volume control system components are constructed of the following materials.
Carbon steel
CASS
High strength steel
Stainless steel 3.0 Aging Management Review Results Page 3.3-5
Environments Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Chemical and volume control system components are exposed to the following environments.
Air -indoor
Gas
Lube oil
Treated borated water
Treated borated water> 140°F
Treated water Aging Effects Requiring Management The following aging effects associated with the chemical and volume control system require management. * * * *
Cracking Cracking -fatigue Loss of material Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for chemical and volume control system components. * * * * * * *
Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring lnservice Inspection Oil Analysis One-Time Inspection Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.3.2.1.2 Chilled Water Materials Chilled water system components are constructed of the following materials.
Carbon steel 3.0 Aging Review Results Page 3.3-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information * * * *
Carbon steel with internal coating . Copper alloy Copper alloy > 15% zinc or > 8% aluminum Glass Stainless steel Environments Chilled water system components are exposed to the following environments.
Air-indoor
Condensation
Gas
Lube oil
Treated water Aging Effects Requiring Management The following aging effects associated with the chilled water system require management.
Loss of coating integrity
Loss of material
Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the chilled water system components. * * * *
Bolting Integrity Coating Integrity External Surfaces Monitoring Oil Analysis Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.3 Component Cooling and Auxiliarv Component Cooling Water Materials Component cooling and auxiliary component cooling water system components are constructed of the following materials. 3.0 Aging Management Review Results Page 3.3-7
Aluminum
Carbon steel
Carbon steel with internal coating
Concrete
Copper alloy
Glass
Gray cast iron
High strength steel
Stainless steel Environments Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Component cooling and auxiliary component cooling water system comporients are exposed to the following environments ...
Air-indoor
Air -outdoor
Condensation * . Lube oil
Raw water
Soil
Treated water Aging Effects Requi.ring Management The following aging effects associated with the component cooling and auxiliary component cooling water system require management. * * * * *
Change in material properties Cracking Loss of coating integrity Loss of material Loss of material -erosior:i Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the component cooling and auxiliary component cooling water system components.
Bolting Integrity
Buried and Underground Piping and Tanks Inspection 3.0 Aging Management Review Results Page 3.3-8
*
*
Coating Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Oil Analysis One-Time Inspection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Periodic Surveillance and Preventive Maintenance Selective Leaching
Service Water Integrity
Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.4 Compressed Air Materials Compressed air system components are constructed of the following materials. * * * * *
Aluminum Carbon steel Copper alloy Elastomer Plastic Stainless steel Environments Compressed air system components are exposed to the following environments.
Air -indoor
Air -outdoor
Condensation Aging Effects Requiring Management The following aging effects associated with the compressed air system require management.
Cracking
Loss of material
Loss of material -wear
Loss of preload 3.0 Aging Management Review Results Page 3.3-9 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The.following aging management programs manage the aging effects for the compressed air system components. * *
Bolting Integrity Compressed Air Monitoring External Surfaces Monitoring 3.3.2.1.5 Containment Cooling HVAC Materials Containment cooling HVAC system components are constructed of the following materials.
Carbon steel
Copper alloy
Elastomer
Stainless steel Environments . Containment cooling HVAC system components are exposed to the following environments.
Air -indoor
Condensation
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the containment cooling HVAC system require management. * * * * *
Change in material properties Cracking Loss of material Loss of material -wear Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results Page 3.3-10 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs . The following aging management programs manage the aging effect$ for the containment cooling HVAC system components. * * *
Bolting Integrity External Surfaces Monitoring . Internal Surfaces in Miscellaneous Piping and Ducting Components Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.6 Control Room HVAC Materials Control room HVAC system components are constructed of the following materials. * * *
Carbon steel Copper alloy Elastomer Stainless steel Environments
Control room HVAC system components are exposed to the following envirC?nments.
Air-indoor
Air -outdoor
Condensation
Treated water
Wastewater *Aging Effects Requiring Management The following aging effects associated with the control room HVAC system require management. * * * * *
Change in material properties Cracking Loss of material Loss of material -wear Loss of preload Reduction of heat transfer 3.0 Aging ManagementReview Results Page 3.3-11 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the control room HVAC system components.
Bolting Integrity
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping and Ducting Components
Periodic Surveillance and Preventive Maintenance
Water Chemistry Control -Closed Treated Water Systems 3.3.2.1. 7 Emergency Diesel Generator Materials Emergency diesel generator system components are constructed of the following materials. * * * * * * *
Aluminum Carbon steel Carbon steel with internal coating Copper alloy Copper alloy >
15% zinc (inhibited) Copper alloy > 15% zinc or.> 8% aluminum Glass Stainless steel Environments Emergency diesel generator system components are exposed to the following environments.
Air-indoor
Air -outdoor
Concrete
Condensation *
Exhaust gas
Fuel oil
Lube oil
Soil
Treated water
Treated water> 140°F 3.0 Aging Man(:lgement Review Results Page 3.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Effects Requiring Management The following aging effects associated with the emergency diesel generator system require management.
Cracking
Cracking -fatigue
Loss of coating integrity
Loss of material
Loss of material -wear
Loss of preload
Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the emergency diesel generator system components. * * * * *
* *
*
Bolting Integrity Buried and Underground Piping and Tanks Inspection Coating Integrity Compressed Air Monitoring Diesel Fuel Monitoring External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Oil Analysis One-Time Inspection Periodic Surveillance and Preventive Maintenance Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.3.2.1.8 Fire Protection -Water Materials Fire protection -water system components are constructed of the following materials. * * * * * *
Carbon steel Carbon steel with internal coating Copper alloy Copper alloy > 15% zinc or > 8% aluminum Gray cast iron Plastic (polyvinyl chloride [PVC]) Stainless steel 3.0 Aging Management Review Results Page 3.3-13 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Environments Fire protection -water system components are exposed to the following environments.
Air-indoor
Air -outdoor
Concrete
Condensation
Exhaust gas
Fuel oil
Raw water
Soil
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the fire protection .:.... water system require management. * * * *
Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Recurring internal corrosion Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the fire protection -water system components. * * * * * * *
Bolting Integrity Buried and Underground Piping and Tanks Inspection Diesel Fuel Monitoring External Surfaces Monitoring Fire Water System Internal Surfaces in Miscellaneous Piping and Ducting Components Selective Leaching Water Chemistry Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-14 3.3.2.1.9 Fire Protection RCP Oil Collection Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire protection RCP oil collection system components are constructed of the following materials.
Carbon steel
Glass
Stainless steel Environments Fire protection RCP oil collection system components are exposed to the following environments.
Air -indoor Lube oil Aging Effects Requiring Management The following aging effects associated with the fire protection RCP oil collection system require management.
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the fire protection RCP oil collection system components. * *
Bolting Integrity External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Periodic Surveillance and Preventive Maintenance 3.3.2.1.10 Fuel Pool Cooling and Purification Materials Fuel pool cooling and purification system components are constructed of the following materials.
Baral 3.0 Aging Management Review Results Page 3.3-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Carbon steel
Stainless steel Environments Fuel pool cooling and purification system components are exposed to the following environments.
Air -indoor
Treated borated water
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the fuel pool cooling arid purification system require management. * * * *
Change in material properties Loss of material Loss of preload Reduction in neutron absorption capacity Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the fuel pool cooling and purification system components. * * * * * * * *
Bolting Integrity Boric Acid Corrosion External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components Neutron-Absorbing Material Monitoring One-Time Inspection Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Primary and Secondary 3.3.2.1.11 Nitrogen Materials Nitrogen system components are constructed of the following materials. 3.0 Aging Management Review Results Page3.3-16
Aluminum
Carbon steel
Stainless steel
Environments Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nitrogen system components are exposed to the following environments.
Air -indoor
Air -outdoor
Gas
Waste water Aging Effects Requiring_Management The following aging effects associated with the nitrogen system requi.re management. * * -. Cracking Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the nitrogen system components.
Bolting Integrity
External Surfaces Monitoring .
Internal Surfaces in Miscellaneous Piping and Ducting Components 3.3.2.1.12 Miscellaneous HVAC Materials Miscellaneous HVAC systems components are constructed bf the following materials;
Carbon steel
Copper alloy
Elastomer
Glass
High strength steel
Stainless steel 3.0 Aging Management Review Results Page 3.3-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Environments Miscellaneous HVAC systems components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Treated water
Waste water Aging Effects Requiring Management The following aging effects associated with the miscellaneous HVAC systems require management.
Change in material properties * *Cracking
Loss of material * *
Loss of material -wear Loss of preload Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for the miscellaneous HVAC systems components.
Bolting Integrity
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping* and Ducting Components
Water Chemistry Control -Closed Treated Water Systems *_ 3.3.2.1.13 Auxiliary Diesel Generator Materials Auxiliary diesel generator system components are constructed of the following materials.
Aluminum
Carbon steel -* Carbon steel with internal coating Aging Management Review Results Page 3.3-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *
Gray cast iron Stainless steel Environments Auxiliary diesel system components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Exhaust gas
Fuel oil Aging Effects Requiring Management The following aging effects associated with the auxiliary diesel generator system
require management. *
*
Cracking Cracking -fatigue Loss of coating integrity Loss of material Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the auxiliary diesel generator system components. * * * *
Bolting Integrity Coating Integrity Diesel Fuel Monitoring External Surfaces Monitoring Internal Surfaces in Miscellaneous Piping and Ducting Components 3.3.2.1.14 Plant Drains Materials Plant drain components are constructed of the following materials.
Carbon steel
Copper alloy 3.0 Aging Management Review Results Page 3.3-19 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Copper alloy > 15% zinc or > 8% aluminum
Gray cast iron
Stainless steel Environments Plant drain components are exposed to the following environments.
Air-indoor
Air -outdoor
Soil
Treated water *
Waste water Aging Effects Requiring Management The following aging effects associated with the plant drains require management.
Cracking
Loss of material
Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the plant drain components.
Bolting Integrity *
Buried and Underground Piping and Tanks Inspection
External Surfaces Monitoring
Internal Surfaces in Miscellaneous Piping and Ducting Components
One-Time Inspection
Periodic Surveillance and Preventive Maintenance
Selective Leaching
Water Chemistry Control -Primary and Secondary 3.3.2.1.15 Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.3.2-15-xx tables. 3.0 Aging Management Review Results Page 3.3-20 Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-related components affecting safety-related systems are constructed of the following materials.
Aluminum
Carbon steel
Copper alloy
Copper alloy > 15% zinc or > 8% aluminum
Glass
Gray cast iron Plastic
Stainless steel Environments Nonsafety-related components affecting safety-related systems are exposed to the following environments.
Air-indqor
Air -outdoor
Concrete
Condensation
Gas
Lube oil
Raw water
Steam
Treated borated water
Treated borated water> 140°F
Treated water
Treated water> 140°F
Waste water Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management. * * * *
Cracking Cracking -fatigue Loss of material Loss of material -FAC Loss of preload 3.0 Aging Management Review Results Page 3.3-21 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs The following aging management programs manage the effects of aging on nonsafety-:related components affecting systems.
Bolting Integrity
Boric Acid Corrosion
Compressed Air Monitoring
External Surfaces Monitoring
Flow-Accelerated Corrosion
Internal Surfaces in Miscellaneous Piping and Ducting Components
Oil Analysis
One-Time Inspection
Periodic Surveillance and Preventive Mainten*ance
Selective Leaching
Water Chemistry Control -Closed Treated Water Systems
Water Chemistry Control -Primary and Secondary 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.3.2.2 of NUREG-1800. The following sections are numbered in accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further evaluation. Programs are d.escribed in Appendix B.
3.3.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management for components, the analysis of fatigue is a TLAA as defined in 10 CFR 54.3. TLAAs are evaluated in accordance with 10 CFR 54.21(c). Evaluations of these TtAAs are addressed in Sections 4.3 and 4.7. 3.3.2.2.2 Cracking due to Stress Corrosion Cracking and Cyclic Loading Cracking due to SCC and cyclic loading in stainless steel PWR non-regenerative heat exchanger components exposed to treated borated water greater than 140°F fn the chemical and volume control system is an aging effect requiring management. The Water Chemistry Control -Primary and Secondary Program manag.es cracking of stainless steel non-regenerative heat exchanger components exposed to treated borated water. The program is augmented by the One-Time lns.pection Program which will verify the absence of cracking through the use of visual and volumetric NOE techniques. Absence of cracking of the tubes and tubesheet is also verified by monitoring RCS leakage and radiation levels in the component cooling water system. Temperature monitoring is a much less sensitive technique and is not used. 3.0 Aging Management Review Results Page 3.3-22 3.3.2.2.3 Cracking due to Stress Corrosion Cracking Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Cracking due to stress corrosion cracking could occur for stainless steel piping, piping components, piping elements and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is
located near other industrial fc:icilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with NUREG-1801, cracking of stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.3.2.2.4 Loss of Material due to Cladding Breach This paragraph in NUREG-1800 pertains to steel charging pump casings with stainless steel cladding. Loss of material could occur for the steel casing material if exposed to treated borated water due to a cladding breach. The WF3 charging pumps have solid stainless steel casings. 3.3.2.2.5 loss of Material due to Pitting and Crevice Corrosion Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping piping elements, and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents'. WF3 .is l_ocated hear other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with NUREG-1801, loss of material for stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External . Surfaces Monitoring Program. 3.3.2.2.6 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.3.2.2. 7 Ongoing Review of Operating Experience See Appendix B Section 8.0.4 for discussion of WF3 operating experience review programs. 3.3.2.2.8 Loss of Material due to Recurring Internal Corrosion A review ,af 10 years of plant_operating experience identified recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in carbon steel piping exposed to raw water due to multiple corrosion mechanisms. The Fire Water System 3.0 Aging Management Review Results Page 3.3-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Program will manage loss of material for these piping components by monitoring degradation and replacing pipe where necessary. The Fire Water System Program will conduct augmented flow tests or flushing, and wall thickness measurements for fire water piping experiencing recurring internal corrosion prior to the period of extended operation and at least once every refueling cycle during the period of extended operation. Wall thickness measurements at selected locations will provide a representative sample of the type of piping and environment where the recurring corrosion is occurring. The selected locations may change based the relevance and usefulness of the wall thickness measurements. 3.3.2.3 Time-Limited Aging Analysis The only time-limited aging analysis identified for auxiliary systems components is metal fatigue. This is evaluated'in Section 4.3. 3.3.3 Conclusion The auxiliary system components that are subject to aging management review have been identified in accordance with the requirements of 10 CFR 54.21. The aging management programs selected to manage the effects of aging on auxiliary system components are identified in Section 3.3.2.1 and in the following tables. A description of these aging management programs is provided in Appendix 8, along with the demonstration that the identified aging effects wHI be managed for the period of extended operation. Therefore, based on the demonstrati.ons provided in Appendix B, the effects of aging associated with the auxiliary system components will _be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results
Page 3.3-24 Table 3.3.1 Waterford Steam Electric Station, Unit 3 License. Renewal Application Technical Information Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-180.1 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Aging Management Further Evaluation Number *Mechanism Programs Rec.ommended Discussion 3.3.1-1
Steel cranes -structural Cumulative fatigue Fatigue is a time-limited aging Yes, TLAA Fatigue is a TLAA. Steel cranes girders exposed to air-damage due to
analysis (TLAA) to be are evaluated as structural indoor uncontrolled fatigue* evaluated for t)le period of components in Section 3.5. (external) extended operation for structural girders of cranes See Section 3.3.2.2.1. that fall within the scope of 10 CFR 54 (Standard Review *Plan, Section.4.7, "Other' -Plant-Specific Time-Limited Aging for generic guidance for meeting the requirements' of 10 CFR -54.21 (c)(1)) 3.3.1-2 .Stainless steel, steel Cumulative fatigue .*. Fatigue is atir:ne-limited aging Yes, TLAA* Fatigue:is a TLAA. heat exchanger damage due to analysis (TLAA) to be components and tubes, fatigue evaluated for the period of See Section 3.3.2.2.1. piping, piping extended operation. See-the components, and SRP, Section 4.3 "Metal piping elements
Fatigue," for acceptable . exposed t<;> treated methods for meeting the borated water, air -requirements of 10 CFR indoor, uncontrolled, 54.21 (c)(1 ) .. ' treated water 3.0 Aging Management Review Results Page 3.3-25 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-3 Stainless steel heat Cracking due to Chapter Xl.M2, "Water exchanger stress corrosion Chem!stry" The AMP is to be componentS, non-cracking; cyclic augmented by verifying the regenerative exposed loading absence of cracking due to to treated borated water stress corrosion cracking and >60°C (>140°F) cyclic loading. An acceptable verification program is to include temperature and radioactivity monitoring of the shell side'water, and eddy current testing of tubes. 3.3.1-4 Stainless steel piping, Cracking due to Chapter Xl.M36, "External piping components, stress corrosion Surfaces Monitoring of and piping elements; cracking Mechanical Components" tanks exposed to air -outdoor 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant-specific The Water Chemistry Control -Primary and Secondary Program manages cracking of stainless steel non-regenerative heat exchanger components exposed to treated borated water. The program is augmented by the One-Time Inspection Program which will verify the absence of cracking. Absence of cracking of the tubes and tubesheet is also verified by additional monitoring. See Section 3.3.2.2.2. Yes, environmental Consistent-with NUREG-1801 .. conditions need to be Cracking in stainless steel evaluated components exposed to outdoor air is managed by the External Surfaces Monitoring Program. See Section 3.3.2.2.3. Page 3.3-26 Table 3.3.1: Auxiliary Systems. Item Aging Effect/ Number Component Mechanism 3.3.1-5 Steel (with stainless Loss of material due steel or nickel-alloy to cladding breach cladding) pump casings exposed to treated borated water 3.3.1-6 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements; corrosion tanks exposed to air -outdoor 3.3.1-7 Stainless steel high-Cracking due to pressure pump, casing cyclic loading exposed to treated borated water 3.3.1-8 Stainless steel heat Cracking due to exchanger components cyclic loading and tubes exposed to
treated borated water >60°C (>140°F) 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated. Reference NRG Information Notice 94-63, "Boric Acid Corrosion of Charging Pump Casings Caused by Cladding Cracks." Chapter Xl.M36, "External Surfaces Monitoring of l\llechanical Components" Chapter Xl.M1, "ASME Section XI lnservice Inspection, Subsections IWB, IWC, and IWD" Ghapter Xl.M1, "ASME Section XI lnservice lns.pection, Subsections IWB, IWC, and IWD" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, verify that plant-The WF3 charging pump specific program casings are solid stainless steel. addresses clad cracking See Section 3.3.2:2.4. Yes, environmental Consistent with NUREG-1801. conditions need to be Loss of material in stainless evaluated steel components exposed to outdoor air is managed by the External Surfaces Monitoring Program.
See Section 3.3.2.2.5. No Consistent with NUREG-1801. Cracking of the stainless steel charging pump casings* due to cyclic loading is managed by the lnservice Inspection Program. No Consistent with NUREG-1801. Cracking of stainless steel heat exchanger components exposed to treated borated water >60°C (>140°F) is managed by the lnservice Inspection Program. Page 3.3-27 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-9 Steel, aluminum, Loss of material due copper alloy (>15% Zn to boric acid or >8% Al) external corrosion surfaces, piping, piping components, and piping elements, bolting exposed to air with borated water leakage 3.3.1-10 Steel, high-strength Cracking due to steel closure bolting stress corrosion exposed to air with cracking; cyclic steam or water loading leakage. 3.3.1-11 Steel, high-strength Cracking due to high-pressure pump, stress corrosion closure bolting exposed cracking; cyclic to air with steam or loading water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M10, "Boric Acid Corrosion" Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to boric acid corrosion of steel external surfaces is managed by the Boric Acid Corrosion Program. There are no aluminum or copper alloy (>15% Zn or >8% Al) auxiliary system components exposed to air with borated water leakage within the scope of license renewal. No Consistent with NUREG-1801. Cracking of high strength steel closure bolting is managed by the Bolting Integrity Program. No Consistent with NUREG-1801. Cracking of high strength steel, pump closure bolting is managed by the Bolting Integrity Program. Page 3.3-28 Table 3*.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-12 Steel; stainless steel Loss of material due closure bolting, bolting to general (steel exposed to only), pitting, and condensation, air -crevice corrosion indoor, uncontrolled (external), air-outdoor * (external) 3.3.1-13 Steel closure bolting Loss of material due exposed to air with to general corrosion steam or water leakage 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" .. ' Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel and stainless steel bolting is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, the Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. No As stated in Item 3.3.1-12, loss of material of steel bolting exposed to air in the auxiliary systems is managed by the Bolting Integrity Program. However, steam or water leakage is not considered as a *separate aspect of the indoor air environment. Page 3.3-29 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-14 Steel, stainless steel Loss of preload bolting exposed to soil 3.3.1-15 Steel; stainless steel, Loss of preload due copper alloy, nickel to thermal effects, alloy, stainless steel gasket creep, and closure bolting, bolting self-loosening exposed to air-indoor, uncontrolled (external), any environment, air -outdoor (external), raw water, treated borated water, fuel oil, treated water 3.3.1-16 BWR only 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M18, "Bolting Integrity" Chapter Xl.M18, "Bolting Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of preload for steel bolting exposed to soil is managed by the Bolting Integrity Program. There is no stainless steel bolting exposed to soil in the auxiliary systems in scope for license renewal. No Consistent with NUREG-1801. Loss of preload for steel and stainless steel bolting exposed to relevant (indoor and outdoor air) environments is managed by the Bolting Integrity Program. There is no copper alloy or nickel alloy bolting in the auxiliary systems in scope for license renewal. Page 3.3-30 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-17 Stainless steel heat Reduction of heat exchanger tubes transfer due to exposed to treated fouling water, treated water (borated) 3.3.1-18 Stainless steel high-Cracking due to pressure pump, casing, stress corrosion piping, piping cracking components, and piping elements exposed to treated borated water >60°C (>140°F), sodium pentaborate solution >60°C (>140°F) 3.3.1-19 Stainless steel Cracking due to regenerative heat stress corrosion exchanger components cracking exposed to treated water >60°C (>140°F) 3.0 Aging Management Review Results ( Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to treated borated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. No The operating temperature of the centrifugal charging pumps of the chemical and volume control system is below the 140°F threshold for cracking in stainless steel. No steel regenerative heat exchanger components are exposed to treated borated water >60°C (>140°F), and are addressed in Item 3.3.1-20. Page 3.3-31 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-20 Stainless steel, steel Cracking due to with stainless steel stress corrosion cladding heat cracking exchanger components exposed to treated borated water >60°C (>140°f), treated w:ater >60°C (>140°F) ' 3.3.1-21 BWRonly 3.3.1-22 BWRonly 3.3.1-23 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to treated water .3.3.1-24 BWR o'nly 3.3.1-25 BWRonly 3.3.1-26 Steel with stainless .Loss of material .due .steel cladding'piping; to pitting and crevice piping components, corrosion (only after and piping elements . cladding . exposed to treated degradation)
water 3.3.1-27 BWRonly 3.0 Aging Management Review Results Aging Management Programs
Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" / Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. . Cracking of stainless steel components exposed to treated borated water >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. No There are no aluminum auxiliary systems components exposed to treated water within the scope of license renewal. No There are no steel piping components in the WF3 fuel pool cooling system exposed to tre_ated water within the scope of license renewal. Page 3.3-32 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number . Component Mechanism 3.3.1-28 Stainless steel pipir:ig, Cracking due to piping components, stress corrosion and piping elements; cracking : tanks, exposed to treated borated water (pri.mary oxygen lev_els controlled) >60°C (>140°F) .. .. Steel (with stainless Loss of material due steel cladding); to pitting and crevice stainless steel piping, corrosion piping components, and piping elements exposed to treated borated water (primary oxygen levels controlled) .. " 3.0 Aging Management Re!view Results Aging Management Programs Chapter Xl.M2, "Water Chemistry" Chapter Xl.M2, "Water Chemistry". ' -Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No *Consistent with NUREG-1801 for stainless steel. components exposed to treated borated . water >60°C (>140°F). Cracking for these components is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify .the effectiveness of the water chemistry control program to manage cracking. No Consistent with NUREG-1801. Loss of material for stainless : steel components exposed to treated borated water is managed by the Water Chemistry Control -Primary and Se.condarY Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. Page 3.3-33 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-30 Concrete; cementitious Changes to material material piping, piping properties due to components, and aggressive chemical piping elements attack exposed to raw water -3.3.1-30.5 Fiberglass, HOPE Cracking, blistering, piping, piping change in color due components, and to water absorption piping elements exposed to raw water (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with l9w permeability. The pipe is exposed to raw water (river water) that is not aggressive. Consequently, changes in material properties is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no fiberglass or HOPE components exposed to raw water in the auxiliary systems in the scope of license renewal. Page 3.3-34

. Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-31 Concrete; cementitious Cracking due to Chapter Xl.M20, "Open-Cycle material piping, piping settling Cooling Water System" components, and piping elements exposed to raw water .. ,. 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping is included in scope for a rare tornado event. Bedding under this piping conforms to Class A .. or Class C as specified by the . American Concrete Pipe

Association which provides a densely compacted backfill limiting the potential for settlement leading to cracking of the concrete piping. Consequently, cracking of the piping due to settling is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. Page 3.3-35 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Co_mponent Mechanism '3.3.1-32 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, .and Changes in material piping elements properties due to exppsed to raw water aggressive chemical attack 3.3.1-32.5 Elastomer seals and Hardening and loss components exposed of strength due to to raw water elastomer degradation; loss of material due to erosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" .. Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with low permeability. The pipe is exposed to raw water (river water) that is r:iot aggressive. Consequently, cracking and changes in material properties are not significant aging effects for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no elastomer components exposed to raw water in the auxiliary systems in the scope of license renewal. Page 3.3-36 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-33 Concrete; cementitious Loss of material due material piping, piping to abrasion, components, and cavitation, piping elements aggressive chemical exposed to raw water attack, and leaching 3.3.1-34 Nickel alloy, copper Loss of material due . alloy piping, piping to general, pitting, components, and and crevice corrosion piping elements exposed to raw water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No The nonsafety-related concrete circulating water intake piping (included in scope for a rare tornado event) is designed and constructed to AWWA C-300, -301, -302 requirements resulting in dense, well-cured high strength concrete with low permeability. The pipe is exposed to raw water (river water) that is not aggressive. Consequently, loss of material is not a significant aging effect for the piping. Nevertheless, the One-Time Inspection Program will confirm that unacceptable degradation is not occurring. No There are no nickel alloy or copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other than the copper alloy heat exchanger components compared to Item 3.3.1-38 below. Page 3.3-37 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-35 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements crevice, and exposed to raw water microbiologically influenced corrosion 3.3.1-36 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements crevice, and exposed to raw water microbiologically influenced corrosion; fouling that leads to corrosion 3.3.1-37 Steel piping, piping Loss of material due components, and to general, pitting, piping elements crevice, and exposed to raw water microbiologically influenced corrosion; fouling that leads to corrosion 3.3.1-38 Copper alloy, steel heat Loss of material due exchanger components to general, pitting, exposed to raw water crevice,* galvanic, and microbiologic*ally influenced corrosion; fouling tha_t leads to corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle . Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open'-Cycle Cooling Water System" . Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other than the heat exchanger components compared to Item 3.3.1-38 below. No There are no copper alloy auxiliary system components exposed to raw water in the scope of license renewal, other the heat exchanger components compared to Item 3.3.1-38 below. No Consistent with NUREG-1801. Loss of material for steel components exposed to raw water is managed by the Service
Water Integrity Program. No Consistent with NUREG-1801 . Loss of material for copper alloy and steel heat exchanger exposed to raw water is managed by the Service Water Integrity Program. Page 3.3-38 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-39 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to raw water 3.3.1-40 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion; fouling exposed to raw water that leads to corrosion 3.3.1-41 Stainless steel piping, Loss of material due piping components, to pitting, crevice, and piping elements and microbiologically exposed to raw water influenced corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Stainless steel piping components exposed to raw water are addressed in Item 3.3.1-40. No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to raw water is managed by the Service Water Integrity Program. No Stainless steel piping components exposed to raw water are addressed in Item 3.3.1-40. Page 3.3-39 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.3.1-42 Copper alloy, titanium, Reduction of heat Chapter Xl.M20, "Open-Cycle stainless steel heat transfer due to Cooling Water System" exchanger tubes fouling exposed to raw water 3.3.1-43 Stainless steel piping, Cracking due to Chapter Xl.M21A, "Closed piping components, stress corrosion Treated Water Systems" and piping elements cracking exposed to closed-cycle cooling water >60°C (>140°F) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to raw water is managed by the Service Water Integrity Program. For the fire pump diesel cooler, reduction of heat transfer for the copper alloy heat exchanger tubes exposed to raw water is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. There are no titanium heat exchanger tubes exposed to raw water with a heat transfer intended function in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Cracking of stainless steel components exposed to closed-cycle cooling water >60°C (>140°F) is managed by the Water Chemistry Control -Closed Treated Water Systems Program. Page 3.3-40 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-44 Stainless steel; steel Cracking due to with stainless steel stress corrosion cladding heat cracking exchanger components exposed to closed-cycle cooling water >60°C {>140°F) 3.3.1-45 Steel piping, piping Loss of material due components, and to general, pitting, piping elements; tanks and crevice corrosion exposed to closed-cycle cooling water 3.3.1-46 Steel, copper alloy heat Loss of material due exchanger to general, pitting, components, piping, and crevice, and piping components, galvanic corrosion and piping elements exposed to closed-cycle cooling water 3.3.1-47 BWRonly 3.3.1-48 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to closed-cycle cooling water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking of stainless steel heat exchanger components exposed to closed-cycle cooling water >60°C {>140°F) is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material for steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Consistent with NUREG-1801. Loss of material for steel and copper alloy components exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No There are no aluminum components exposed to closed-cycle cooling water in the auxiliary systems in the scope of license renewal. Page 3.3-41 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-49 Stainless steel piping, Loss of material due piping components,. to pitting and crevice and piping elements corrosion exposed to closed-cycle cooling water .. 3.3.1-50 Stainless steel, copper Reduction of heat alloy, steel heat transfer due to exchanger tubes fouling exposed to closed-cycle cooling water 3.3.1-51 Boraflex spent fuel Reduction of storage racks: neutron-neutron-absorbing absorbing sheets capacity due to (PWR), spent fuel boraflex degradation storage racks: neutron-absorbing sheets (BWR) exposed to treated borated water, treated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M22, "Boraflex Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to closed-cycle cooling water is managed by the Water Chemistry Control :.... Closed Treated Water Systems Program. No Consistent with NUREG-1801. Reduction of heat transfer for steel, stainless steel and copper alloy heat exchanger tubes exposed to closed-cycle cooling water is managed by the Water Chemistry Control -Closed Treated Water Systems Program. No Boraflex is n.ot used in the WF3 spent fuel storage racks. Page 3.3-42 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-52 Steel cranes: rails and Loss of material due structural girders to general corrosion exposed to air-indoor, uncontrolled (external) 3.3.1-53 Steel cranes -rails Loss of material due exposed to air-indoor, to wear uncontrolled (external) 3.3.1-54 Copper alloy piping, Loss of material due piping components, to general, pitting, and piping elements and crevice corrosion exposed to condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems" Chapter Xl.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems" ' Chapter Xl.M24, "Compressed Air Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel crane rails and structural girders exposed to indoor air is managed by the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems {Inspection of OVHLL) Program. This item applies to aging management review results presented in Tables 3.5.2-X. No Visual inspections under the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program manage loss of material. No Consistent with* NUREG-1801. Loss of material for copper alloy components exposed to condensation is managed by the Compressed Air Monitoring Program. Page 3.3-43 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-55 Steel piping, piping Loss of material due components, and to general and pitting piping elements: corrosion compressed air system exposed to condensation (internal) 3.3.1-56 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to condensation (internal) 3.3.1-57 Elastomers fire barrier Increased hardness; penetration seals shrinkage; loss of exposed to air -indoor, strength due to uncontrolled, air -weathering outdoor 3.3.1-58 Steel Halon/carbon Loss of material due dioxide fire suppression to general, pitting, system piping, piping and crevice corrosion components, and piping elements exposed to air -indoor, uncontrolled (external) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M24, "Compressed Air Monitoring" Chapter Xl.M24, "*Comp*ressed Air Monitoring" Chapter Xl.M26, "Fire Protection" Chapter Xl.M26, "Fire Protection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation -Recommended Discussion No Consistent with Loss of material for steel components exposed to condensation is managed by the Compressed Air Monitoring Program.
No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to condensation is managed by the Compressed Air Monitoring Program. No Consistent with NUREG-1801. Increased hardness, shrinkage and loss of strength of elastomer fire barrier seals exposed to indoor air are managed by the Fire Protection Program. This item applies to aging review results presented in Table 3.5.2-4. No Consistent with NUREG-1801.
Loss of material for steel fire protection components exposed '. to indoor air is managed by the Fire Protection Program. This item applies to aging management review results presented in Table 3.5.2-3. Page 3.3-44 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-59 Steel fire rated doors Loss of material due exposed to air -indoor, to wear uncontrolled, air-outdoor 3.3.1-60 Reinforced concrete Concrete cracking structural fire barriers: and spalling due to walls, ceilings and aggressive chemical floors exposed to air -attack, and reaction indoor, uncontrolled with aggregates 3.3.1-61 Reinforced concrete Cracking, loss of strliCtural fire barriers: material due to walls, ceilings and freeze-thaw, floors exposed to air -aggressive chemical outdoor attack, and reaction with aggregates 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M26, "Fire Protection" Chapter Xl.M26, "Fire Protection," and Chapter Xl.S6, "Structures Monitoring" Chapter Xl.M26, "Fire Protection," and Chapter Xl.S6, "Structures Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of steel fire doors is managed by the Fire Protection Program. This item applies to aging management review results presented in Table 3.5.2-X. No Consistent with NUREG-1801. Cracking of concrete fire barriers exposed to indoor air is managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. No Consistent with NUREG-1801. Cracking and loss of material of concrete fire barriers exposed to outdoor air are managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. Page 3.3-45 Table 3.3: 1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-62 Reinforced concrete Loss of material due structural fire barriers: to corrosion of walls, ceilings and embedded steel floors exposed to air -indoor, uncontrolled, air -outdoor 3.3.1-63 Steel fire hydrants Loss of material due exposed to air -to general, pitting, outdoor and crevice corrosion 3.3.1-64 Steel, copper alloy Loss of material due piping, piping to general, pitting, components, and crevice, and piping elements microbiologically exposed to raw water influenced corrosion; fouling that leads to corrosion; flow blockage due to fouling 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M26, "Fire Protection," and Chapter XI.SS, "Structures Monitoring" Chapter Xl.M27, "Fire Water System" Chapter Xl.M27, "Fire Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material of concrete fire barriers exposed to indoor or outdoor air is managed by the Fire Protection and Structures Monitoring Programs. This item applies to aging management review results presented in Tables 3.5.2-X. No Consistent with NUREG-1801. Loss of material for steel fire hydrants exposed to outdoor air is managed by the Fire Water System Program. No Consistent with NUREG-1801. Loss of material for steel and copper alloy fire protection system components exposed to raw water is managed by the Fire Water System Program. Page 3.3-46 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-65 Aluminum piping, piping Loss of.material due components, and to pitting and crevice piping elements corrosion, fouling exposed to raw water
that leads to corrosion; flow blockage due to fouling 3.3.1-66 Stainless steel piping, Loss of material due piping components, to pitting and crevice and piping elements . corrosion; fouling exposed to raw water that leads to corrosion; flow blockage due to fouling 3.3.1-67 Steel tanks exposed to Loss of material due air -outdoor to general, pitting, and crevice corrosion I 3.3.1-68 Steel piping, piping Loss of material due components, and to general, pitting, piping elements and crevice corrosion exposed to fuel oil 3.0. Aging Management Review Results Aging Management Programs Chapter Xl.M27, "Fire Water System" ) Chapter Xl.M27, "Fire Water System" Chapter Xl.M29, "Ahqveground MetalliG Tanks" Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32 *. "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical *Further Evaluation Recommended Discussion No There are no aluminum auxiliary system components exposed to raw water in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for stainless steel fire protection system components exposed to raw water is managed by the Fire Water System Program. No The only steel tank exposed to outdoor air in the scope of license renewal is the fire water
storage tank. Loss of material for the fire water storage tank is addressed in Item 3.3.1-136. No Consistent with NUREG-1801. Loss of material for steel components exposed *to fuel oil is managed by the Diesel Fuel Monitoring Program. The One-Time Inspection Program will verify the effediveness of the Diesef Fuel Monitoring Program to manage loss of material. Page 3.3-47 Table 3.3.1 : Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-69 Copper piping, Loss of material _due piping compon.ents, to general, pitting, and piping elements crevice, and exposed to fuel oil microbiologically influenced corrosion 3.3.1-70 Steel piping, piping Loss of material due components, ar:id to general, pitting, piping. elements; tanks crevice, and exposed to fuel oil microbiologically influenced corrosion; fouling that leads to corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to fuel oil is managed by the Diesel Fuel Monitoring Program. The One-Time Inspection Program will, verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for steel components exposed to fuel oil is managed by the Diesel Fuel Monitoring The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. Page 3.3-48 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number* Component Mechanism 3.3.1-71 Stainless steel, Loss of material due aluminum piping, piping to pitting, crevice, components, and and microbiologically piping elements influenced corrosion exposed to fuel oil 3.3.1-72
Gray cast iron, copper Loss of material due alloy (>15% Zn or >8% to selective leaching Al) piping, piping components, and piping elements, heat exchanger components exposed to.treated water, closed-cycle cooling water, soil, raw water, waste water 3.3.1-73 Concrete; cementitious Changes in material material piping, piping properties due to components, and aggressive chemical piping elements attack exposed to air -outdoor 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M30, "Fuel Oil Chemistry", and Chapter Xl.M32, "One-Time Inspection" . Chapter Xl.M33; "Selective Leaching" Chapter Xl.M36, "External Surfaces Monitoring of
Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to fuel oil is managed by the Diesel Fuel M.onitoring Program. The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program to manage loss of material. There are no aluminum components exposed to fuel oil in the scope of license renewal. No Consistent with. NUREG-1801. Loss of material due to selective leaching for gray cast iron and copper alloy (>15% Zn or >8% Al) components is managed by the Selective Leaching Program. -No There are no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. Page 3.3-49 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-74 Concrete; cementitious Cracking due to material piping, piping settling components, and piping elements exposed 'to air -outdoor 3.3.1-75 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, and Changes in material piping elements properties due to exposed to air -aggressive chemical outdoor attack 3.3.1-76 Elastomers elastomer: Hardening and loss seals and components of strength due to exposed to air-indoor, elastomer uncontrolled (internal/ degradation external) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No There are no reinforced concrete or asbestos cement components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801 for most components. Cracking and change in material properties of elastomer components exposed to indoor air are managed by the External Surfaces Monitoring Program. The Periodic Surveillance and Preventive Maintenance Program manages these aging effects for the portable flexible duct that can be used with the portable smoke exhaust fan in the control room HVAC system. Page 3.3-50 Table 3.3.1: Auxiliary Systems Item Number Component 3.3.1-77 Concrete; cemerititious material piping, piping components, and , piping elements exposed to air -outdoor 3.3.1-78 Steel piping and components (external surfaces), ducting and components (external surfaces), ducting; closure bolting exposed to air -indoor, uncontrolled (external), air -indoor, uncontrolled (external), air-outdoor (external), condensation (external) 3.3.1-79 Copper alloy piping, piping components, and piping elements exposed to condensation (external) 3.0 Aging Management Review Results Aging Effect/ Aging Management Mechanism Programs Loss of material due Chapter Xl.M36, "External to abrasion, Surfaces Monitoring of cavitation, Mechanical Components" aggressjve chemical attack, and leaching Loss of material due Chapter Xl.M36, "External to general corrosion Surfaces Monitoring of Mechanical Components" Loss of material due . Chapter XLM36, "External to general, pitting, Surfaces Monitoring of and crevice corrosion Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Eva I uation Recommended Discussion No There are .no concrete piping components exposed to outdoor air in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801 for most components. *Loss of material for most steel components exposed to indoor air, outdoor air or condensation is managed by the External Surfaces Monitoring Program. The Periodic Surveillance and Preventive Maintenance Program manages loss of material for the portable steel smoke exhaust fan. No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to condensation is managed by the External Surfaces Monitoring Program. Page 3.3-51 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component *Mechanism 3.3.1-80 Steel heat exchanger Loss of material due components, piping, to general, pitting, piping components, and crevice corrosion and piping elements exposed to air -indoor, uncontrolled (external), air-outdoor (external) 3.3.1-81 Copper alloy, aluminum Loss of material due piping, piping to pitting and crevice components, and corrosion piping elements exposed to air -outdoor (external), air-outdoor 3.3.1-82 Elastomers elastomer: Loss of material due seals and components to wear exposed to air -indoor, uncontrolled (external) 3.3.1-83 Stainless steel diesel Cracking due to engine exhaust piping, stress corrosion piping components, cracking and piping elements exposed to diesel exhaust 3.3.1-84 [There is no 3.3.1-84 in NUREG-1800] 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel components exposed to indoor or outdoor air is managed by the External Surfaces Monitoring Program. No Consistent with NUREG-1801. Loss of material for copper alloy and aluminum components exposed to outdoor air is managed by the External Surfaces Monitoring Program. No Consistent with NUREG-1801. Wear of external surfaces of elastomer components exposed to indoor air is managed by the External Surfaces Monitoring Program. No Cracking of stainless steel diesel engine exhaust components is managed by the Periodic Surveillance and Preventive Maintenance Program. Page 3.3-52 Table 3.3.1: Auxiliary Systems Item .. Aging Effect/ Number Component Mechanism 3.3.1-85 Elastomers elastomer Hardening and loss . seals and components of strength due to exposed to Closed-elastomer cycle cooling water degradation 3.3.1-86 Elastomers elastomers, Hardening and loss linings, elastomer: of strength due to seals and components elastomer exposed to treated degradation borated water, treated water, raw water 3.3.1-87 [There is no 3.3.1-87 in NUREG-1800.] 3.3.1-88 Steel; stainless steel Loss of material due piping, piping to general (steel components, only), pitting, and piping elements, piping, crevice corrosion piping components, and piping elements, diesel engine exhaust exposed to raw water i (potable), diesel exhaust 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in . Miscellaneous Piping arid Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no elastomer components exposed to closed-cycle cooling water in the auxiliary systems in the scope of license renewal. No There are no elastomer components exposed to treated
borated water, treated water or raw water in the auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for steel and stainless steel components exposed to diesel exhaust or raw water (potable) is managed by
the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-53 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-89 Steel, copper alloy Loss of material due piping, piping to general, pitting, components, and and crevice corrosion piping elements exposed to moist air or condensation (internal) 3.3.1-90 Steel ducting and Loss of material due components (internal to general, pitting, surfaces) exposed to crevice, and (for drip condensation (internal) pans and drain lines) microbiologically influenced corrosion 3.0 Aging Management Review Results Aging Management Programs For fire water system components: Chapter Xl.M27, "Fire Water System," or for other components: Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" -Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel and copper alloy components exposed to condensation is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Steel and copper alloy fire water system piping components exposed to condensation are addressed in Item 3.3.1-131. No There are no steel duct components internally exposed to condensation in the auxiliary systems in the scope of license renewal. Page 3.3-54 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-91 Steel piping, piping Loss of material due components, and to general, pitting, piping elements; tanks crevice, and exposed to waste water microbiologically influenced corrosion 3.3.1-92 Aluminum piping, piping Loss of material due components, and to pitting and crevice piping elements corrosion exposed to condensation (internal) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl'.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most steel components exposed to waste water. For these components, loss of material is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. The Periodic Surveillance and Preventive Maintenance Program uses periodic visual inspections or other NOE techniquesto manage loss of material for steel components abandoned in place. No Aluminum components within scope of license renewal that are -exposed to internal condensation, are associated with compressed air systems. Loss* of material for these aluminum components is by the Compressed Air Monitoring Program. Page 3.3-55 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-93 Copper alloy piping, Loss of material due piping components, to pitting and crevice and piping elements corrosion exposed to raw water (potable) 3.3.1-94 Stainless steel ducting Loss of material due and components to pitting and crevice exposed to corrosion condensation 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for copper alloy components exposed to raw water (potable) is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. No Consistent with NUREG-1801. Loss of material for stainless steel components internally exposed to condensation is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-56 i Table 3.3.1: Auxiliary Systems Item Aging Effect/ ; Number Component Mechanism 3.3.1-95 Copper alloy, stainless Loss of material due steel, nickel alloy, steel to pitting, crevice, piping, piping and microbiologically components, and
influenced corrosion piping elements, heat ' exchanger i components, piping, piping components, and piping elements; tanks exposed to waste. water, condensation (internal) " .. 3.0 Aging Management Review Results Aging Management Programs Chapter XLM38, "Inspection of Internal Surfaces in Miscellaneous Piping and pucting Components" ' Waterford Steam .Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation *Discussion No Consistent with NUREG-1801 for most copper alloy and stainless components exposed to waste water or condensation. For these components, 1.oss of material is managed by the Internal Surfaces. in Miscellaneous Piping and Ducting Components Program. The Periodic Surveillance and Preventive Maintenance Program uses periodic visual inspections or other NDE techniques to manage ioss of material for components abandoned in place. There. are no nickel alloy. components exposed to waste water in the auxiliary systems in the scope of license renewal. Steel .. components internally exposed to condensation are addressed in Items 3.3.1-55, 3.3.1-89, 3.3.1-131*and 3.3.1-136 . Page 3:3-!?7 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-96 Elastomers elastomer: Loss of material due seals and components to wear exposed to air-indoor, uncontrolled (internal) 3.3.1-97 Steel piping, piping Loss of material due components, and to general, pitting, piping elements, and crevice corrosion reactor coolant pump oil collection system: tanks, reactor coolant pump oil collection system: piping, tubing, valve bodies exposed to lubricating oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most components. Wear of internal surfaces of elastomer components exposed to indoor air is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Wear of the portable duct used with the portable smoke exhaust fan is managed by the Periodic Surveillance and Preventive Maintenance Program. No Consistent with NUREG-1801
for most components. Loss of material for most steel components exposed to lube oil is managed bY the Oil Analysis Program. The One-Time 1.nspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. The Periodic Surveillance and Preventive Maintenance Programs uses periodic visual inspections to. manage loss of material for steel reactor co.olant pump oil collection system components exposed to lube oil. Page 3.3-58 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-98 Steel heat exchanger Loss of material due* components exposed to general, pitting .. to lubricating oil* crevice, and microbiologically influenced corrosion;
fouling that leads to corrosion 3.3.1-99 Copper alloy, aluminum Loss of material due piping, piping to pitting and crevice components, and corrosion piping elements exposed to lubricating oil 3.0 Aging .Management Review Results ( \. Aging Management Programs Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel heat exchanger components exposed
to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will
verify the effectiveness of the Oil Analysis Program to manage loss of material. No Consistent with NUREG-1801. Loss of material for copper alloy and aluminum components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. Page 3.3-59 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-100 Stainless steel piping, Loss of material due piping components,
to pitting, crevice, and piping elements and microbiologically exposed to lubricating influenced corrosion oil -3.3.1-101 Aluminum heat Reduction of heat exchanger tubes transfer due to exposed to lubricating fouling oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for most components. Loss of material for stainless steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis to manage loss of material. For stainless steel components in the RCP oil collection subsystem of the fire protection equipment, the Periodic Surveillance and Preventive Maintenance and External Surfaces Monitoring Programs manage loss of material. No There are no aluminum heat exchanger tubes exposed to lube oil with an intended function of heat transfer in systems in the scope of license renewal. Page 3.3-60 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-102 Boral; boron steel, Reduction of and other materials neutron-absorbing (excluding Boraflex) capacity; change in spent fuel storage dimensions and loss racks: neutron-of material due to absorbing sheets effects of SFP (PWR), spent fuel environment storage racks: neutron-absorbing sheets (BWR) exposed to treated borated water, treated water 3.3.1-103 Reinforced concrete, Cracking due to asbestos cement aggressive chemical piping, piping attack and leaching; components, and Cl]anges in material piping elements properties due to exposed to soil or aggressive chemical concrete attack 3.3.1-104 HOPE, fiberglass Cracking, blistering, piping, piping change in color due components, and to water absorption piping elements exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M40, "Monitoring of Neutron-Absorbing Materials other than Boraflex" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Reduction in neutron absorption capacity, change in material properties and loss of material for Baral is managed by the Neutron-Absorbing Material Monitoring Program. The Water Chemistry Control -Primary and Secondary Program supplements management of loss of material. No The nonsafety-related concrete circulating water intake piping is addressed in Item 3.3.1-105. -No There are no fiberglass or HOPE components exposed to soil or concrete in the systems in the scope of license renewal. Page 3.3-61 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-105 Concrete cylinder Cracking, spalling, piping, asbestos corrosion of rebar cement pipe piping, due to exposure of piping components, rebar and piping elements exposed to soil or concrete 3.3.1-106 Steel (with coating or Loss of material due wrapping) piping, piping to general, pitting,
components, and crevice, and piping elements microbiologically exposed to soil or influenced corrosion concrete 3.3.1-107 Stainless steel, nickel Loss of material due alloy piping, piping to pitting and crevice components, and corrosion piping elements exposed to soil or concrete 3.3.1-108 Titanium, sµper Loss of material due austenitic, aluminum, to pitting and crevice copper alloy, stainless corrosion steel, nickel alloy piping, piping components, and piping elements, bolting exposed to soil or concrete 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Burieq and Underground Piping and Tanks" Chapter Xl.M4t, "Buried and Underground Piping and Tanks" Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter XLM41, "Buried and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking and loss of material for concrete piping exposed to soil .is managed by the Buried and Underground Piping and Tanks Inspection Program. No Consistent with NUREG-1801. Loss of materiar for steel components exposed to soil is managed by the Buried and Underground Piping and Tanks Inspection Program. No There are no stainless steel or nickel alloy components exposed to soil or concrete in the auxiliary systems in the scope of license renewal. No None of the component type, material and environment combinations represented by . this item apply to components in . systems included in the scope of license renewal. Page 3.3-62 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-1.09 Steel bolting exposed . Loss of material due to soil or concrete to general, pitting and crevice corrosion 3.3.1-109.5 Underground . Loss of material due aluminum; copper alloy, to general (steel stainless steel, nickel only), pitting and alloy, steel piping, crevice corrosion
piping components, and piping elements 3.3.1-110 BWRonly 3.3.1-111 Steel structural steel Loss of material due exposed to air-indoor, to general, pitting, uncontrolled (external) and crevice corrosion 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Buried and Underground Piping and Tanks" *. .. Chapter XI. M41, "Buried and Underground Piping and Tanks" Chapter Xl.S_6, "Structures Monitoring" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation
Recommended Discussion No Consistent with NUREG-1801. Loss of material for steel bolting exposed to soil is managed.by* the Buried and Underground Piping and Tanks Inspection Program. There is no steel bolting embedded in concrete in systems in the.scope of license renewal. No There are no underground components in auxiliary systems in the of license renewal. No Aging management review results for structural steel components are presented in and compared to NUREG-1801 items in Section 3.5. Page 3.3-63 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-112 Steel piping, piping None components, and piping elements exposed to concrete 3.3.1-113 Aluminum piping, piping None components, and piping exposed to air -dry (internal/external), air -indoor, uncontrolled (internal/eXternal), air -indoor, controlled (external), gas 3.3.1'-114 Copper alloy piping, . None piping components, and piping elements exposed to air -indoor, uncontrolled (internal/ external), air-dry, gas 3.0 Aging Management Review Results Aging Management Programs None, provided 1) attributes of the concrete are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and
adequate air entrainment) as cited in NUREG-1557, and 2) plant OE indicates no degradation of the concrete None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No, if conditions are Consistent with NUREG-1801. met. Embedded steel components are in concrete that meets the guidelines of ACI 318 for safety-related concrete structures. Operating experience indicates n6 aging-related degradation of this concrete. NA-NoAEM or* Consistent with NUREG-1801 AMP for relevant (indoor air and gas) environments. NA-NoAEM or Consistent with NUREG-1801 AMP . for relevant (indoor air and gas) environments. Page 3.3-64 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-115 . Copper alloy (S15% Zn None and S8% Al) piping, piping components, and piping elements *. exposed to air with . borated water leakage 3.3.1-116
Galvanized steel piping,. None piping components, and piping elements exposed to air -indoor, uncontrolled 3.3.1-117 Glass piping elements None exposed to air -indoor, uncontrolled (external), lubricating oil, closed-cycle cooling water, air -outdoor, fuel oil, raw water, treated water, treated borated water, air with borated water leakage, condensation (internal/external) gas 3.3.1-118 Nickel alloy piping, None 'piping components, and piping elements exposed to air-indoor, .** uncontrolled (external) ' 3.0 Aging Management Review Results Aging Management Programs None None
None None .,. .. Waterford Steam Electric Station, Unit 3 License Renewal Application Tech 11 ical .. 1 nformation Further.Evaluation Recommended Discussion NA -No AEM or AMP There are no cepper alloy (S15% Zn or S8% Al) components exposed to air with borated water leakage in the auxiliary systems in the scope of license renewal. NA-NoAEM or Galvanized (zinc) coating AMP applied to some steel components is not credited for corrosion protection for license. renewal. or Consistent with NUREG-1801 'AMP
for relevant (indoor air, air with borated water leakage, closed-cycle* cooling water,.
condensatioil, lube oil, raw water, treated borated water.and treated water) environments. NA-NoAEM or There are no nickel alloy AMP components in the auxiliary systems in the scope of license * renewal. Page 3.3-65 Table 3.3.1: Auxil_iary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-119 Nickel alloy, PVC, glass None piping, piping components, and piping elements exposed to air with borated water leakage, air -indoor, uncontrolled, condensation (internal), wastewater 3.3.1-120 Stainless steel piping, None piping components, and piping elements .' exposed to air-indoor, uncontrolled (internal/ external), air -indoor, uncontrolled (external), air with borated water leakage, concrete, air-dry, gas 3.3.1-121 Steel piping, piping None
components, and
piping elements exposed to air -indoor, controlled (external), air -dry, g.as 3.0 Aging Management Review Results Aging Management Programs None .. None ' None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion NA-NoAEM or Consistent with NUREG-1801 AMP for glass components exposed to waste water. Other material environment combinations represented by this item are not applicable to auxiliary system components in the scope of license. renewal. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (indoor air, air with borated water leakage, and gas) environments. NA-NoAEM or Consistent with NUREG-1801 AMP for relevant (gas) environment. .. Page 3.3-66 Table 3.;t 1: Auxiliary Systems Item Number Component 3.3.1-122 Titanium !:teat exchanger components, piping, piping components, and piping elements exposed to air-indoor, uncontrolled or air -* outdoor 3.3.1-123 Titanium (ASTM Grades 1,2, 7, 11, or 12 that contains > 5% aluminum or mo.re than 0.20% oxygen or any amount of tin) heat exchanger components other than tubes, piping, piping .. comporents, and piping *elements exposed to raw water 3.0 Aging Management Review Results Aging Effect/ Aging Management Mechanism *Programs* .. None None . None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation
Recommended * .Discussion NA-NoAEM or There are no titanium AMP , components included in systems in the scope of license renewal. NA.:...NoAEM or There are no titanium AMP components included in systems in the scope of license renewal. Page 3.3-67 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-124 Stainless steel, steel Cracking due to (with stainless steel.or stress corrosion nickel-alloy cladding) cracking spent fuel storage racks (BWR), spent fuel storage racks (PWR), piping, piping components, and piping elements; exposed to treated water >60°C (>140°F), treated borated water >60°C (>140°F) 3.3.1-125 Steel (with stainless Loss of material due steel cladding); to pitting and crevice stainless steel spent corrosion fuel storage racks (BWR), spent fuel storage racks (PWR), piping, piping components, and piping elements exposed to treated water, treated borated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M2, "Water Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Wate( Chemistry," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Cracking for stainless steel components exposed to treated borated water (primary) >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. The spent fuel pool is normally maintained at a temperature below 140°F, consequently, cracking is not a significant aging effect for the stainless steel spent fuel pool components. No Consistent with NUREG-1801. Loss of material for stainless steel components exposed to treated borated water is managed by the Water Chemistry* Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry program. Page 3.3-68 Table 3.3.1: Auxiliary Systems Item Aging Effect/ ,
Number Component Mechanism 3.3.1-126 Any material, piping, Wall thinning due to piping components, erosion and piping elements exposed to treated water, treated water . (borated), raw water 3.3.1-127 Metallic piping, piping Loss of material.due components, and .tanks to recurring internal exposed to raw water or Corrosion waste water 3.3.1-128 Steel, stainless steel, or Loss of material due aluminumtanks (within to general (steel the scope. of Chapter only), pitting, or Xl.M29, "Aboveground crevice corrosion; Metallic Tanks") cracking due to exposed to soil or stress corrosion concrete, orthe cracking (stainless following external steel and aluminum environments only) outdoor, air-indoor uncontrolled, moist air, condensation 3.0 Aging Management Review Results Aging Management . Programs Chapter Xl.M17, "Flow-Accelerated Corrosion" A aging management program is to be evaluated to address recurring internal corrosion *Chapter Xl.M29, "Aboveground Metallic Tanks" .. Waterford Steam Electric Station, Unit 3 Renewal Application Technical Information Further Evaluation Recommended Discussion No Consist,ent with NUREG-1801. Loss of material due to erosion for steel components exposed to raw water is managed by the Flow.,Accelerated Corrosion Program . Yes, For carbon steel piping of: the fire plant-specific protection system, loss of material due to recurring internal corrosion is managed by the Fire Water System Program. See Se".tion 3 .. 3.2.2.8. No At WF3, there are no tanks within the scope of Chapter XLM29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capaCity greater than 100,000 gallons. Page 3.3-69 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-129 Steel tanks exposed to Loss of material due soil or concrete; air-to general, pitting, indoor uncontrolled, and crevice corrosion raw water, treated water, waste water, condensation 3.3.1-130 Metallic sprinklers Loss of material due exposed to air-indoor to general (where controlled, air-indoor applicable}, pitting, uncontrolled, air-crevice, and outdoor, moist air, microbiologically-condensation, raw influenced corrosion, water, treated water fouling that leads to corrosion; flow blockage due to fouling 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, "Aboveground Metallic Tanks" Chapter Xl.M27, ."Fire Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Loss of material for the steel fire water storage tank constructed on soil and concrete is managed by the Fire Water System Program. No Consistent with NUREG-1801. Loss of material for sprinklers exposed to condensation or raw water is managed by the Fire Water System Program. Page 3.3-70 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-131 Steel, stainless steel, Loss of material due
copper alloy, or to general (steel, and aluminum fire water copper alloy only), system piping, piping pitting, crevice, and components and piping microbiologically-elements exposed to influenced corrosion, air-indoor uncontrolled fouling that leads to (internal), air-outdoor corrosion; flow (internal), or blockage due to condensation (internal) fouling 3.3.1-132 Insulated steel, Loss of material due stainless steel, copper to general (steel, and alloy, aluminum, or copper alloy only), copper alloy(> 15% Zn) pitting, and crevice piping, piping corrosion; cracking components, and tanks due to stress exposed to corrosion cracking condensation, air-(aluminum, stainless outdoor steel and copper alloy (>15% Zn) only) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M27, "Fire Water System" Chapter Xl.M36, "External Surfaces Monitoring of Mechanical Components" or Chapter Xl.M29, .Aboveground Metallic Tanks" (for tanks only) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801 for* most components. Loss of material for steel, copper alloy and stainless steel fire water system components internally exposed to condensation is managed by the Fire Water System Program. For the fire water system piping and flame arrestor exposed internally to outdoor air, the Internal Surfaces in Miscellaneous Piping and Ducting Components Program manages loss of material. No with NUREG-1801 for insulated carbon steel, copper alloy and stainless steel components exposed to condensation or outdoor air. Loss of material and cracking (stainless steel only) is managed by the External Surfaces Monitoring Program. There are no insulated a.luminum or copper alloy > 15% Zn or > 8% Al piping components in auxiliary systems in the scope of license renewal. Page 3.3-71 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-133 Underground HOPE Cracking, blistering, piping, piping change in color due components, and piping to water absorption elements in an air-indoor uncontrolled or condensation (external) environment 3.3.1-134 Steel, stainless steel, or Loss of material due copper alloy piping, to general (steel and piping components, and copper alloy only), piping elements, and pitting, crevice, and heat exchanger microbiologically components exposed to influenced corrosion, a raw water fouling that leads to environment (for corrosion nonsafety-related components not covered by NRC GL 89-13) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M41, "Buried and Underground Piping and Tanks" Chapter Xl.Ml.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No There are no underground components in auxiliary systems in the scope of license renewal. No Consistent with NUREG-1801. Loss of material for nonsafety-related steel, stainless steel and copper alloy components exposed to raw water (not covered by NRC GL 89-13) is. managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Page 3.3-72 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-135 Steel or stainless steel Loss of material due pump casings to general (steel submerged in a waste only), pitting, crevice, water (internal and and microbiologically external) environment influenced corrosion 3.3.1-136 Steel, stainless steel or Loss of. material due aluminum fire water to general (steel storage tanks exposed only), pitting, crevice, to air-indoor and uncontrolled, air* microbiologically-outdoor, condensation, influenced corrosion,
moist air, raw water, fouling that leads fo treated water corrosion; cracking due to stress corrosion cracking (stainless steel and aluminum only) 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.Ml.M36, "External Surfaces Monitoring of Mechan'ical Components" Chapter Xl.M27, "Fire Water System" .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with for some components. Loss of material for external steel surfaces exposed to waste water is managed by the External Surfaces Monitoring Program. Loss of material for internal steel surfaces exposed to waste water is managed by the Periodic
Surveillance and Preventive Maintenance Program using periodic visual inspections. No Consistent with NUREG-1801. Loss of material for steel and stainless steel components exposed to outdoor air, condensation or raw water is managed by the Fire Water System Program. Page 3.3-73 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Component Mechanism 3.3.1-137 Steel, stainless steel or Loss of material due aluminum tanks (within to general (steel the scope of Chapter only) pitting and Xl.M29, "Aboveground crevice corrosion Metallic Tanks") exposed to treated water, treated borated water 3.3.1-138 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-delamination, ** cycle cooling water, raw. rusting, or physical water, treated water, damage, and spalling treated borated water, for cementitious waste water, lubricating coatings/linings oil, or fuel oil 3.3.1-139 Metallic piping, piping Loss of material due: components, heat to general, pitting, exchangers, tanks with crevice, and internal*coatings/linings microbiologically exposed to closed-influenced corrosion; cycle cooling water, raw fouling that leads to . water, treated water, corrosion treated borated water, or lubricating oil 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M29, "Aboveground Metallic Tanks" Chapter Xl.M42, "Internal Coatings/Linings for h-Scope Piping, Piping Components, Heat Exchangers, and Tanks" Chapter Xl.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks" ' Waterford Steam Electric Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater,than 100,000 gallons. No Consistent with NUREG-1801. Loss of coating or lining integrity for metallic components with internal coating or linings is managed by the Coating Integrity Program. No Consistent with NUREG-1801. Loss of material for metallic components with internal coating or linings is managed by the Coating Integrity Program. '.* Page 3.3-74 Table 3.3.1: Auxiliary Systems Item Aging Effect/ Number Mechanism 3.3.1-140 Gray cast iron piping Loss of material due *components with to selective leaching internal coatings/linings exposed to closed-cycle cooling water, raw water,_ or treated water 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.M42, "Internal Coatings/Linings for In-Scope* Piping, Piping Components, Heat Exchangers, and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion No Consistent with NUREG-1801. Loss of material due to selective leaching for gray cast iron components with internal coating or linings.is managed by the Coating Integrity Program. Page 3.3-75 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Notes for Tables 3.3.2-1 through 3.3.2-15-36 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consistent with component, material, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neitherthe component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 301. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 302. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program. 303. The One-Time Inspection Program will verify the effectiveness of the Diesel Fuel Monitoring Program. 304. This tank is located indoors and is seated on (not embedded in) concrete. 305. These components have openings that expose the internal surfaces to outdoor air. Because the internal and external surfaces are exposed to the same environments, aging effects of the internal surfaces can be inferred from external surface conditions. 3.0 Aging Management Review Results Page 3.3-76 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 306. The (int) and (ext) environment designations refer to the nominal internal and external surfaces of the component and may not be consistent with the internal and external environment designations used in NUREG:-1801. Consequently, an air or condensation (ext) environment for a component contained within a duct or other enclosure can correspond directly to a NUREG-1801 air or condensation (internal) environment. 307. This treated water is equivalent to the NUREG-1801 closed-cycle cooling water environment. 308. The aging mechanism for loss of material in this line is selective leaching. 3.0 Aging Management Review Results Page 3.3-77 Table 3.3.2-1 Chemical and Volume Control System Summary of Aging Management Evaluation Table 3.3.2-1: Chemical and Volume Control System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Programs Accumulator Pressure Stainless ste*e1 Air-indoor None None boundary (ext). Accumulator Pressure* Stainless steel Treated borated Loss of material Chemistry boundary water (int) Control -Primary and Secondary Bolting Press we Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of preload Bolting .integrity boundary steel (ext) Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity boundary (ext) Demineralizer Pressure Stainless steel Air-indoor None None boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-Table 1 1801 Item Notes Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.l.AP-125 3.3.1-12 B Vll.l.A-102 3.3.1-9 A Vll.l.AP-124 3.3.1-15 B Vll.E1.AP-122 3.3.1-11 B Vll.1.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15. B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-18 3.3.1-120 A Page 3.3-78 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Demineralizer Pressure Stainless steel Treated borated Loss of material boundary water (int) Filter housing Pressure Stainless steel Air-indoor None boundary (ext) Filter housing Pressure Stainless steel Treated borated Loss of material boundary water (int) Flow element Pressure Stainless steel Air-indoor None boundary (ext) Flow element Pressure Stainless steel Treated borated Loss of material boundary water (int) Gear box Pressure Carbon steel Air-indoor Loss of material housing boundary (ext) Gear box Pressure Carbon steel Air-indoor Loss of material housing boundary (ext) Gear box Pressure Carbon steel Lube oil (int) Loss .of material housing boundary Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated borated Cracking (channel head) boundary water> 140°F (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Oil Analysis None lnservice Inspection Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-127 3.3.1-97 A, 302 Vll.J.AP-123 3.3.1-120 c Vll.E1.AP-119 3.3.1-8 A Vll.E1.AP-118 3.3.1-20 A, 301 Page 3.3-79 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Stainless steel Treated borated Cracking -fatigue (channel head) boundary water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated Loss of material (channel head) boundary water > 140°F (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) letdown boundary (ext) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) letdown boundary (ext) Heat exchanger Pressure Carbon steel Treated water Loss of material (shell) letdown boundary (int) Heat exchanger Pressure Stainless steel Air-indoor None (shell) boundary (ext) regenerative Heat exchanger Pressure Stainless steel Treated borated Cracking (shell) boundary water> 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated Cracking -fatigue (shell) boundary water> 140°F regenerative (int) 3.0 Aging Management Review Results Aging Management Programs TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Water Chemistry Control -Closed Treated Water Systems None lnservice Inspection Water Chemistry Control -Closed Treated Water Systems TLAA-metal fatigue Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-189 3.3.1-46 A Vll.J.AP-123 3.3.1-120 c Vll.E1.AP-119 3.3.1-8 A Vll.E1.AP-118 3.3.1-20 A, 301 Vll.E1 .A-100 3.3.1-2 A Page 3.3-80 Table 3.3.2-1: Chemical and Volume Control System ' Component* Intended Type Function Material Environment
Heat exchanger Pressure Stainless steel Treated borated (shell) boundary water > 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F * (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F .letdown (ext) Heat exchanger Pressure Stainless steel Treated water (tube sheet) boundary (int) letdown Heat exchanger *Pressure Stainless steel Treated borated (tube sheet) boundary water> 140°F regenerative ' (ext) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative* (int) . 3.0 Aging Management Review Results Aging Effect Aging 'Requiring Management Management Programs Loss of material Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Chemistry Control -Primary and Secondc;iry Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Cracking Water Chemistry Gontrol -Primary and SecondatY Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .A-88 3.3.1-29 A Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-69 3.3.1-3 E Vll.C2.A-52 3.3.1-49 c Vll.E1 .AP-118 3.3.1-20 A, 301 Vll.E1 .AP-118 3.3.1-20 A, 301 Page 3.3-81 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Environment Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative (int) Heat exchanger Pressure Stainless steel Treated borated (tube sheet) boundary water > 140°F regenerative (int) Heat exchanger Heat transfer Stainless steel. Treated borated (tubes) water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated (tubes) boundary water> 140°F (int) Heat exchanger Pressure Stainless steel Treated borated (tubes) boundary water> 140°F (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) letdowri (ext) Heat exchanger Pressure Stainless steel Treated borated (tubes) letdown boundary vyater > 140°F. (int) Heat exchanger Pressure Stainless steel Treated water (tubes) letdown boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Cracking Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1so1* Item Item Notes Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1.A-101 3.3.1-17 A, 301 Vll.E1.A-100 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.C2.AP-188 3.3.1-50 c Vll.E1.A-69 3.3.1-3 E Vll.C2.A-52 3.3.1-49 c Page 3.3-82 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Heat exchanger Heat transfer Stainless steel (tubes) regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Heat exchanger Pressure Stainless steel (tubes) boundary regenerative Orifice Pressure Stainless steel boundary Flow control Orifice Pressure Stainless steel boundary Flow control Piping Pressure Stainless steel boundary Piping Pressure Stainless steel boundary 3.0 Aging Management Review Results ( I \.,_ Environment Treated borated water> 140°F (ext) Treated borated water> 140°F (ext) Treated borated water > 140°F (ext) Treated borated water> 140°F (ext) Treated borated water> 140°F (int) Air-indoor (ext) Treated borated water (int) Air-indoor (ext) Gas (int) Aging Effect Aging Requiring Management Management Programs Reduction of heat Water Chemistry transfer Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-101 3.3.1-17 A, 301 Vll.E1.AP-118 3.3.1-20 A, 301 Vll.E1.A-100 3.3.1-2 A Vll.E1 .A-88' 3.3.1-29 . A Vll.E1.AP-118 3.3.1-20 A, 301 Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Page 3.3-83 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Lube oil (int) Loss of material boundary Piping Pressure Stainless steel Treated borated Loss of material boundary water (int) Piping Pressure Stainless steel Treated borated Cracking boundary water> 140°F (int) Piping Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Piping Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Piping Pressure Stainless steel Treated water Loss of material boundary (int) Pump casing Pressure CASS Air-indoor None boundary (ext) Pump casing Pressure CASS Treated borated Loss of material boundary water (int) Pump casing Pressure Stainless steel Air-indoor None boundary (ext) 3.0 Aging Management Review Results Aging Management Programs Oil Analysis Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-138 3.3.1-100 A, 302 Vll.E1 .A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1 .AP-82 3.3.1-28 A Vll.E1 .A-103 3.3.1-124 A, 301 Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 VI I. C2 .A-52 3.3.1-49 c Vll.J.AP-18 3.3.1-120 A Vll.E1 .A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Page 3.3-84 Table 3.3.2-1: Chemical and Volume Control System Component Intended Type Function Material Environment Pump casing Pressure Stainless steel Treated borated boundary water (int) Pump casing Pressure Stainless steel Treated borated boundary water (int) Strainer Filtration Stainless steel Treated borated water (ext) Strainer housing Pressure Stainless steel Air-indoor boundary (ext) Strainer housing Pressure Stainless steel Treated borated boundary water (int) Tank Pressure Stainless steel Air-indoor boundary (ext) Tank Pressure Stainless steel Treated borated boundary water (int) Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated borated boundary water (int) Thermowell Pressure Stainless steel Treated borated boundary water> 140°F (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking lnservice Inspection Loss of material Water Chemistry Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-115 3.3.1-7 A Vll.E1.A-88 3.3.1-29 A Vll.E1.AP-79 3.3.1-125 A, 301 Vll.E1.A-88 3.3.1-29 A Vll.J.AP-18 3.3.1-120 A Vll.E1.A-88 ' 3.3.1-29 A Vll.J.AP-18 3.3.1-120 c Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.J.AP-18 3.3.1-120 A VI I .E 1.A-88 3.3.1-29 A Vll.E1.AP-79 3.3.1-125 A, 301 VII. E 1.AP-82 3.3.1-28 A Vll.E1.A-103 3.3.1-124 A, 301 Page 3.3-85 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Thermowell Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Treated borated Loss of material boundary water (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Gas (int) None boundary Valve body Pressure Stainless steel Treated borated Loss of material boundary -. water (int) 3.0 Aging Management Review Results Aging Management Programs TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Oil Analysis Water Chemistry Control -Primary and Secondary Boric Acid Corrosion External Surfaces Monitoring Oil Analysis None None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.J.AP-18 3.3.1-120 A Vll.E1.AP-138 3.3.1-100 A, 302 Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.E1.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.E1.AP-127 3.3.1-97 A, 302 Vll.J.AP-18 . 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Vll.E1.A-88 3.3.1-29 A. Vll.E1.AP-79 3.3.1-125 A, 301 Page 3.3-86 Table 3.3.2-1: Chemical and Volume Control System Aging Effect Component Intended Requiring Type Function Material* Environment Management Valve body Pressure Stainless steel Treated borated Cracking boundary water> 140°F (int) Valve body Pressure Stainless steel Treated borated Cracking -fatigue boundary water> 140°F (int) Valve body Pressure Stainless steel Treated borated Loss of material boundary water> 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.E1 .AP-82 3.3.1-28 A Vll.E1.A-103 3.3.1-124 A, 301 Vll.E1.A-57 3.3.1-2 A Vll.E1.A-88 3.3.1-29 A Vll.E1 .AP-79 3.3.1-125 A, 301 Vll.C2.A-52 3.3.1-49 c Page 3.3-87 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Blower housing Pressure Carbon steel boundary Blower housing Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Flow element Pressure Stainless steel boundary 3.0 Aging Management Review Results Table 3.3.2-2 Chilled Water System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Environment Management Programs Air-indoor Loss of material External Surfaces (ext) Monitoring Gas (int) None None Air-Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Condensation Loss of material Bolting Integrity (ext) Condensation Loss of preload Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Condensation Loss of material Bolting Integrity (ext) Con9ensation Loss of preload Bolting Integrity (ext) Condensation Loss of material External Surfaces (ext) Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.D.AP-121 3.3.1-12 D ----H Vll.l.AP-124 3.3.1-15 B Vll.D.AP-121 3.3.1-12 D ----H ----G Page 3.3-88 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Flow element Pressure Stainless steel Treated water boundary (int) Heat exchanger Pressure Carbon steel Air-indoor (channel head) boundary (ext) Heat exchanger Pressure Carbon steel Treated water (channel head) boundary (int) ' Heat exchanger Pressure Stainless steel Air-indoor (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water (channel head) poundary (int) Heat exchanger Pressure Carbon steel Air-indoor (shell) boundary (ext) Heat exchanger Pressure Carbon steeL Gas (int) (shell) boundary Heat exchanger Pressure Stainless steel Air-indoor (shell) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (int) .; (shell) boundary Heat exchanger Pressure Carbon steel Gas (int) (tube sheet) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Water Chemistry Control -Closed
Treated Water Systems Los.s of material External Surfaces
Monitoring Loss of material Water Chemistry Control -Closed ... Treated Water Systems None None Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring None None None None Loss of material Oil Analysis None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information '* NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 3.3.1-78 A . . ' Vll.C2.AP-189 3.3.1-46 A Vll.J.AP-1.23 3.3.1-*120 c Vll.C2.A-52 3.3.1-49 c Vll.l.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 c Vll.J.AP-123 3.3.1-120 c Vll.C2.AP-138 3.3.1-100 C,302 Vll.J.AP-6 3.3.1-121 c Page 3.3-89 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Carbon steel Treated water Loss of material (tube sheet) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (int) Loss of material (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water Loss of material (tube sheet) boundary (ext) Heat exchanger Pressure Copper alloy Gas (ext) None (tubes) boundary Heat exchanger Heat transfer Copper alloy Treated water Reduction of heat (tubes) (int) transfer Heat exchanger Pressure Copper alloy Treated water Loss of material (tubes) boundary (int) Heat exchanger Heat transfer Stainless steel Lube oil (ext) Reduction of heat (tubes) transfer Heat exchanger Pressure Stainless steel Lube oil (ext) Loss of material (tubes) boundary 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Oil Analysis Water Chemistry Control -Closed Treated Water Systems None Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Oil Analysis Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-189 3.3.1-46 A Vll.C2.AP-138 3.3.1-100 C,302 Vll.C2.A-52 3.3.1-49 c Vll.J.AP-9 3.3.1-114 c Vll.C2.AP-205 3.3.1-50 A Vll.C2.AP-199 3.3.1-46 c V.01.EP-79 3.2.1-51 C, 302 Vll.C2.AP-138 3.3.1-100 C,302 Page 3.3-90 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Heat exchanger Pressure steel Treated water (tubes) boundary (int) Insulated piping Pressure Carbon steel Condensation components boundary (ext) Insulated piping Pressure Copper .alloy' Condensation components boundary (ext) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Gas (int) boundary Flow control Piping Pressure Carbon steel Air-indoor boundary . (ext) Piping Pressure Carbon steel Condensation boundary (ext) Piping Pressure Carbon steel Treated water boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of he"'t transfer Los.s of material Loss of material Loss of material None None Loss of material Loss of material Loss of material Aging Management .*Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item .Item Notes Water Chemistry . Vll.C2.AP-188 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems External Surfaces Vll.C2.A-405 3.3.1-132 A Monitoring External Surfaces Vll.C2.A-405 3.3.1-132 A Monitoring None Vll.J.AP-123 3.3.1-120 A None
Vll.J.AP-22 '3.3.1-120 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-81 .3.3.1-78 A Mon'itoring Water Chemistry Vll.C2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems Page 3.3-91 Table 3.3.2-2: Chilled Water System Component Intended Type Function Material Environment Piping Pressure Copper alloy Air-indoor boundary (ext) Piping Pressure Copper alloy Condensation boundary (ext) Piping Pressure Copper alloy
Gas (int) boundary Piping Pressure Copper alloy Treated water boundary (int) Pump casing Pressure Carbon steel Air-indoor boundary (ext) Pump casing Pressure Carbon steel Gas (int) boundary Pump casing Pressure Carbon steel Lube oil (int) boundary Pump casing Pressure Stainless steel Condensation boundary Pump casing Pressure Stainless steel Treated water boundary (int) Sight glass Pressure Copper alloy > Condensation boundary 15% Zn or> 8% (ext) Al 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material External Surfaces Monitoring None None Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring None None Loss of material Oil Analysis Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-144 3.3.1-114 A Vll.F1 .AP-109 3.3.1-79 c Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-199 3.3.1-46 A Vll.1.A-77 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.G2.AP-127 3.3.1-97 A, 302 ----G Vll.C2.A-52 3.3.1-49 A Vll.F1.AP-109 3.3.1-79 c Page 3.3-92 Table 3.3.2-2: Chilled Water System Compom;mt Intended Type Function Material Environment Sight glass Pressure Copper alloy > Condensation boundary 15% Zn or> 8% (ext) Al Sight glass Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Sight glass Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Sight glass Pressure Glass Condensation boundary (ext) Sight glass Pressure Glass Treated water boundary (int) Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Condensation boundary (ext) Tank Pressure Carbon steel Gas (int) boundary Tank Pressure Carbon steel with Treated water boundary internal coating (int) Tank Pressure Carbon steel with Treated water boundary internal coating (int) Thermowell Pressure Stainless steel Condensation boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material None None Loss of material Loss of material None Loss of coating integrity Loss of material Loss of material Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Selective Leaching ----H Selective Leaching Vll.C2.AP-43 3.3.1-72 A Water Chemistry Vll.C2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-97 3.3.1-117 A None Vll.J.AP-166 3.3.1-117 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.1.A-77 3.3.1-78 A Monitoring None Vll.J.AP-6 3.3.1-121 c Coating Integrity Vll.C2.A-416 3.3.1-138 B, 307 Coating Integrity Vll.C2.A-414 3.3.1-139 B, 307 External Surfaces ----G Monitoring Page 3.3-93 Table 3.3.2-2: Chilled Water System Aging Effect *Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel _ Treated water Loss of material boundary (int) Tubing_ Pressure Copper. alloy Air-indoor None boundary (ext) Tubing Pressure Copper alloy Condensation Loss of material boundary (ext) Tubing Pressure Copper alloy Gas (int) -None boundary Tubing Pressure Copper alloy Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Co.ndensation Loss of material boundary (ext) Tubing Pressure Stainless steel Gas:(int) *
None bouridary Tubing Pressure Stainless steel Lube oil (int) Loss *of material boundary 3.0 Aging Management Review Results Aging Management Programs Water Chemistry Control -Closed Treated Water Systems None External Surfaces Monitoring None _Oil Analysis Water Chemistry Control -Closed Treated Water Systems* None External Surfaces Monitoring None Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.J.AP-144 A Vll.F1.AP-109 3.3.1-79 c Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-133 3.3.1-99 A, 302 Vll.C2.AP-199 3.3.1-46 A V!l.J.AP-123 3.3.1-120 A ----G Vll.J.AP-22 3.3.1.-120 A Vll.C2.AP-138 3.3.1-100 A, 302 Page 3.3-94 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel
Treated water Loss of material boundary (int) Valve body Pressure Carbon.steel. Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Condensation Loss of material boundary (ext) Valve body Pressure Carbon steel Gas (int) None boundary Valve body Pressure Carbon steel Lube oil (int) ' Loss of material boundary Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Copper alloy > Air-indoor None boundary 15% Zn or> 8% (ext) Al Valve body Pressure . Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (ext) Al Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (ext) Al 3.0 Aging Management Review Results ( '* Aging Management Programs Water Chemistry Control -Closed Treated Water Systems Exterr:ial Surfaces Monitoring External Surfaces Monitoring None Oil Analysis Water Chemistry Control -Closed Treated Water Systems None External Surfaces Monitoring . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information '* *NUREG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 . 3.3.1-78 A Vll.l.A-81 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.C2.AP-127 3.3.1-97 A, 302 Vll.C2.AP-202 3.3.1-45 A . Vll.J.AP-144 3.3.1-114 A Vll.F1.AP-109 3.3.1-79 c Selective Leaching ----H Page 3.3-95 Table 3.3.2-2: Chilled Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Copper alloy > Gas (int) None boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Lube oil (int)
Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Treated water Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Treated water Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Condensation Loss of material boundary (ext) Valve body Pressure Stainless steel Gas (int) None boundary Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs None Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-9 3.3.1-114 A Vll.C2.AP-133 3.3.1-99 A, 302 Selective Leaching Vll.C2.AP-43 3.3.1-72 A Water Chemistry Vll.C2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-123 3.3.1-120 A External Surfaces ----G Monitoring None Vll.J.AP-22 3.3.1-120 A Water Chemistry Vll.C2.A-52 3.3.1-49 A Control -Closed Treated Water Systems Page 3.3-96 Table 3.3.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling and Auxiliary Component Cooling Water System Summary of Aging Management Evaluation Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Blower housing* Pressure . Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Mo11itoring . Blower housing . Carbon steel Air -outdoor Loss of material External S-urfaces ----G, 305 boundary (int) Monitoring Bolting Pressure Carbon.steel Air -indoor . Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel
Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity 3.3.1-12 B boundary (ext)* Bolting Pressure steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP7263 3.3.1-15 B boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity Vll:l.A-04 3.3.1-10 B boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 .B . boundary steel (ext) Bolting Pressure High strength Air-* indoor . Loss of preload Bolting Integrity VILl.AP.:124 3.3.1-15 B boundary steel (ext) .. Bolting Pressure High strength Air -outdoor Cracking Bolting ,Integrity Vll.l.A-04 3.3.1-10 B boundary steel (ext) Bolting Pressure High strength Air -outdoor Loss ofmaterial Bolting 'Integrity Vll.1.AP-126 3.3.1-12 B boundary steel (ext) 3.0 Aging Management Review Results Page Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Bolting Pressure High strength Air -outdoor Loss of preload Bolting Integrity boundary steel (ext) Coil Pressure Copper alloy Lube oil (int) Loss of material Oil Analysis boundary Coil Pressure Copper alloy Raw water (ext) Loss of material Service Water boundary Integrity Expansion joint Pressure Stainless steel Air-indoor None None boundary (ext) Expansion joint Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Fan housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Fan housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (int) Monitoring Flow element Pressure Stainless steel Air-indoor None None boundary (ext) Flow element Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (channel head) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (channel head) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.AP-263 3.3.1-15 B Vll.C1.AP-133 3.3.1-99 C,302 Vll.C1.AP-179 3.3.1-38 A Vll.J.AP-123 3.3.1-120 A Vll.C2.A-52 3.3.1-49 A Vll.l.A-78 3.3.1-78 A ----G, 305 Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.l.A-77 3.3.1-78 A Vll.C2.AP-189 3.3.1-46 A Page 3.3-98 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Heat exchanger Pressure Stainless steel Air-indoor None None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (channel head) boundary (int) Control -Closed Treated Water Systems Heat exchanger Heat transfer Aluminum Condensation . Cracking External Surfaces (fins) (ext) Monitoring Heat exchanger Heat transfer Aluminum Condensation Loss of material External Surfaces (fins) (ext) Monitoring Heat exchanger Heat transfer Aluminum Condensation Reduction of heat Periodic (fins) (ext) transfer Surveillance and Preventive Maintenance Heat exchanger Pressure Carbon steel Air-indoor Loss of material. External Surfaces (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel . Raw water (int) Loss of material Service Water (shell) boundary Integrity Heat exchanger Pressure Stainless steel Air-indoor None None (shell) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (shell) boundary (int) Control -Closed Treated Water Systems Heat exchanger Pressure Carbon steel Raw water (int) Loss of material Service Water (tube sheet) boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-123 3.3.1-120 c Vll.C2.A-52 3.3.1-49 c ----G ----G ----G Vll.l.A-77 3.3.1-78 A Vll.C1.AP-183 3.3.1-38 A Vll.J.AP-123 3.3.1-120 c Vll.C2.A-52 3.3. 1-49 c Vll.C1 .AP-183 3.3. 1-38 A Page 3.3-99 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (tube sheet) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (tube sheet) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Pressure Stainless steel Treated water Loss of material Water Chemistry (tube sheet) boundary (int) Control -Closed Treated Water Systems Heat exchanger Heat transfer Carbon steel Condensation Reduction of heat Periodic (tubes) (ext) transfer Surveillance and Preventive Maintenance Heat exchanger Pressure Carbon steel Condensation Loss of material External Surfaces (tubes) boundary (ext) Monitoring Heat exchanger Heat transfer Carbon steel Treated water Reduction of heat Water Chemistry (tubes) (int) transfer Control -Closed Treated Water Systems Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (tubes) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-189 3.3.1-46 A Vll.C2.A-52 3.3.1-49 c Vll.C2.A-52 3.3.1-49 c ----G Vll.l.A-81 3.3.1-78 A Vll.F1 .AP-204 3.3.1-50 c Vll.C2.AP-189 3.3.1-46 A Page 3.3-100 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect
Aging Component Intended Requiring Management Type Function
Material Environment Management Programs Heat exchanger Pressure Copper alloy Condensation Loss of material External Surfaces (tubes) boundary (ext) Mo_nitoring Heat exchanger Pressure Copper.alloy Treated water Loss of material Water Chemistry (tubes) boundary (int) Control -Closed Treated Water .. Systems Heat exchanger Heat transfer Stainless steel Raw water (ext) Reduction of heat Service Water (tubes) transfer Integrity Heat exchanger Pressure Stainless steel Raw water (ext) Loss of material
Service Water (tubes) boundary Integrity Heat exchanger Pressure Stainless steel Treated water Loss' of material Water Chemistry (tubes) boundary (ext) Control -Closed Treated Water Systems Heat exchanger Heat transfer Stainless steel. Treated water Reduction of heat Water Chemistry (tubes) (int) transfer Control -Closed Treated Water . Systems Heat exchanger . Pressure Stainless steel Treated water Loss of material Water Chemistry (tubes). boundary (int) Control -Closed ; Treated Water Systems Insulated piping Pressure Carbon steel Air -outdoor Loss of material* External Surfaces components boundary (ext) Monitoring Insulated piping. Pressure Carbon steel Condensation Loss of material External Surfaces components boundary .. (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.F1.AP-109 3.3.1-79 c Vll.C2.AP-199 3.3.1-46 c Vll.C1.AP-187 3.3.1-42 A Vll.C1.A-54 3.3.1-40 c Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-188 3.3.1-50 A 3.3.1-49 c VILC1 .A-405 3.3.1-132 A Vll.C1 .A-405 3.3.1-132 A Page 3.3-101 Waterford Steam Electric Station, Unit 3 License Renewal Technical Information Table 3.3.2-3: Component Cooling and Auxiliary Compo,nent CooHng Water System
Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Nozzle Pressure Stainless steel . Air -outdoor Cracking External Surfaces Vll.C1 .AP-209 3.3.1-4 A boundary (ext) Monitoring Nozzle Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vll.C1 .AP-221 3.3.1-6 A bOundary (ext) Monitoring Nozzle Pressure . Stainless steel Raw water (int) Loss of material *
Service Water VILC1.A-54 3.3.1-40 A bounda.ry Integrity Orifice Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary *(ext) Orifice Pressure Stainless steel Raw water (int) Loss of material Service Water Vll.C1.A-54 3.3.1-40 A boundary Integrity Flow control Orifice Pressure Stainless stee! *Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Flow control Treated Water Systems Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary * (ext) Monitoring Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A *boundary (ext) Monitoring Piping Pressure Carbon steel Raw water.(int) Loss of Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Piping Pressure Carbon steel Soil (ext) Loss of material Buried and VILC1.AP-198 3.3.1-106 A boundary Underground* Piping and Tanks . Inspection 3.0 Aging Management Review Results Page 3.3-102 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Piping Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel with Raw water (int) Loss of coating Coating Integrity boundary internal coating integrity Piping Pressure Carbon steel with Raw water (int) Loss of material Coating Integrity boundary internal coating Piping Pressure Concrete Raw water (int) Change in material One-Time boundary properties Inspection Piping Pressure Concrete Raw water (int) Cracking One-Time boundary Inspection Piping Pressure Concrete Raw water (int) Loss of material One-Time boundary Inspection Piping Pressure Concrete Soil (ext) Cracking Buried and boundary Underground Piping and Tanks Inspection Piping Pressure Concrete Soil (ext) Loss of material Buried and boundary Underground Piping and Tanks Inspection Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-202 3.3.1-45 A Vll.C1 .A-416 3.3.1-138 B Vll.C1 .A-414 3.3.1-139 B Vll.C1 .AP-250 3.3.1-30 E 3.3.1-32 Vll.C1 .AP-155 Vll.C1 .AP-248 3.3.1-31 E 3.3.1-32 Vll.C1.AP-155 Vll.C1 .AP-249 3.3.1-33 E Vll.C1.AP-178 3.3.1-105 A Vll.C1.AP-178 3.3.1-105 A Vll.l.A-77 3.3.1-78 A Page 3.3-103 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Pump casing Pressure Carbon steel Air -indoor (int) Loss of material Periodic boundary Surveillance and Preventive Maintenance Pump casing Pressure Stainless steel Air-indoor None None boundary (ext) Pump casing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None boundary (ext) Sight glass Pressure Glass Treated water None None boundary (int) Strainer housing Pressure Stainless steel Air-indoor None None boundary (ext) Strainer housing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes V.A.E-29 3.2.1-44 E Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.C2.A-52 3.3.1-49 A Vll.l.A-77 3.3.1-78 A Vll.C2.AP-202 3.3.1-45 A Vll.J.AP-14 3.3.1-117 A Vll.J.AP-166 3.3.1-117 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Page 3.3-104 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Programs Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Tank Pressure Carbon steel with Treated water Loss of coating Coating Integrity boundary internal coating (int) integrity Tank Pressure Carbon steel with Treated water Loss of material Coating Integrity boundary internal coating (int) Thermowell Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Thermowell Pressure Carbon steel Raw water (int) Loss of material Service Water boundary Integrity Thermowell Pressure Carbon steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Thermowell Pressure Stainless steel Air-indoor None None boundary (ext) Thermowell Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity Thermowell Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems Tubing Pressure Stainless steel Air-indoor None None boundary (ext) Tubing Pressure Stainless steel Raw water (int) Loss of material Service Water boundary Integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.C2.A-414 3.3.1-138 B,307 Vll.C2.A-414 3.3.1-139 B,307 Vll.l.A-77 3.3.1-78 A Vll.C1.AP-194 3.3.1-37 A Vll.C2.AP-202 3.3.1-45 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Vll.C2.A-52 3.3.1-49 A Vll.J.AP-123 3.3.1-120 A Vll.C1.A-54 3.3.1-40 A Page 3.3-105 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging Component Intended Requiring Management NUREG-Table 1 Type Function Material Environment Management Programs 1801 Item Item Notes Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure, Carbon steel Air'-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Raw water (int) Loss of material Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Valve body Pressure Carbon steel Raw water (int) Loss of material -Flow-Accelerated Vll.C1 .A-409 3.3.1-126 A boundary erosion Corrosion Valve body Pressure Carbon steel Treated water
Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Gray cast iron Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring 0 Valve body Pressure Gray cast iron Raw water (int) Loss of material Selective Leaching Vll.C1.A-51 3.3.1-72 A boundary Valve body Pressure G.ray cast iron. Raw water (int) Loss of material Service Water Vll.C1.AP-194 3.3.1-37 A boundary Integrity Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary * (ext) Valve body Pressure Stainless steel Raw water (int) Loss of material Service Water Vll.C1.A-54 3.3.1-40 A boundary Integrity 3.0 Aging Management Review Results Page 3.3-106 Table 3.3.2-3: Component Cooling and Auxiliary Component Cooling Water System Aging Effect Aging* Component Intended Requiring Management Type Function Material Environment Management Programs Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results *
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 A Page 3.3-107
Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Accumulator Pressure Carbon steel boundary Accumulator Pressure Carbon steel boundary Accumulator Pressure Carbon steel boundary* Accumulator Pressure Stainless steel boundary Accumulator Pressure Stainless steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure
Carbon steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure* Plastic boundary 3.0 Aging Management Review Results Table 3.3.2-4 Compressed Air System Summary of Aging Management Evaluation Aging Effect Aging ' Requiring Management Environment MC1nagement Programs Air-indoor Loss of material External Surfaces (ext) Monitoring Air -outdoor Loss of material External Surfaces (ext) Monitoring Condensation Loss of material Compressed Air (int) Monitoring Air-indoor None None (ext) Condensation Loss of material Compressed Air (int) Monitoring Air-indoor Loss of material Bolting Integrity (ext) Air -indoor* Loss of preload Bolting Integrity (ext) Air -outdoor loss of material External Surfaces (ext) Monitoring Condensation Loss of material Compressed Air (int) Monitoring Air-indoor None None (ext) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A ----F Page 3.3-108 Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Environment Filter housing Pressure Plastic Condensation boundary (int) Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Condensation boundary (int) Flex hose Pressure Elastomer Air-indoor boundary (ext) Flex hose Pressure Elastomer Condensation boundary (int) Flex hose Pressure Stainless steel Air-indoor boundary (ext) Flex hose Pressure Stainless steel Condensation boundary (int) Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Condensation boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Air -outdoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None None None Loss of material Compressed Air Monitoring Loss of material -External Surfaces wear Monitoring None None None None Loss of material Compressed Air Monitoring Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Cracking External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----F Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.F1 .AP-113 3.3.1-82 c ----G Vll.J.AP-123 3.3.1-120 A Vll.D.AP-81 3.3.1-56 A Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A Page 3.3-109 Table 3.3.2-4: Compressed Air System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure* Stainless steel Air -outdoor Loss of material .. boundary (ext) Piping Pressure Stainless steel Condensation
Loss of material boundary (int) Regulator body Pressure Aluminum Air-indoor None boundary (ext) Regulator body Pressure Aluminum Condensation Loss of material boundary (int) Regulator body Pressure Copper alloy
Air -indoor None boundary (ext) .Regulator body Pressure Copper alloy Condensation Loss of material bdundar-Y (int) Regulator body Pressure Plastic Air-indoor None boundary (ext) Regulator body Pressure Plastic Condensation None ' boundary (int) Tubing Pressure Copper alloy Air-indoor None boundary (ext) Tubing* Pressure Copper alloy Condensation Loss of material boundary {int) Tubing Pressure Stainles.s steel Air=-indoor None bounda_ry (ext) Tubing Pressure Stainless steel
Air -outdoor Cracking boundary (ext) 3.0 Aging Management Review Results Aging Management Programs. External Surfaces Monitoring Compressed Air Monitoring None Compressed Air Monitoring None Compressed Air Monitoring None None None Compressed Air fl.llonitoring. *None External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-221 3.3.1-6 A Vll.D.AP-81 3.3.1-56 0 A VILJ.AP-135 3.3.1.-113 A Vll.F2.AP-142 3.3.1-92 E ' Vll.J.AP-144 3.3.1-114 A
Vll.D.AP-240 3.3.1-54 A ----F ----F Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A .. *P.age 3.3-110 Table 3.3.2-4: Compressed Air System Component Intended Type Function Material Environment Tubing Pressure Stainless steel Air -outdoor boundary (ext) Tubing Pressure Stainless steel Condensation boundary (int) Valve body Pressure Aluminum Air-indoor boundary (ext) Valve body Pressure Aluminum Condensation boundary (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Condensation boundary (int) Valve body Pressure Copper alloy Air-indoor boundary (ext) Valve body Pressure Copper alloy Condensation boundary (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) Valve body Pressure Stainless steel Air -outdoor boundary (ext) Valve body Pressure Stainless steel Air -outdoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Loss of material Compressed Air Monitoring Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring Loss of material Compressed Air Monitoring None None Loss of material Compressed Air Monitoring None None Cracking External Surfaces Monitoring Loss of material External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-221 3.3.1-6 A Vll.D.AP-81 3.3.1-56 A Vll.J.AP-135 3.3.1-113 A Vll.F2.AP-142 3.3.1-92 E Vll.D.A-80 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 A Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 A Vll.J.AP-123 3.3.1-120 A Vll.D.AP-209 3.3.1-4 A Vll.D.AP-221 3.3.1-6 A Page 3.3-111 Table 3.3.2-4: Compressed Air System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Programs Compressed Air Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-Table 1 1801 Item Item Notes Vll.D.AP-81 3.3.1-56 A Page 3.3-112 Table 3.3.2-5 . Containment Cooling HVAC System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-5: Containment Cooling 'HVAC System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor
Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.AP-41 3.3.1-80 A boundary (ext) Monitoring Cooler housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E bo_undary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of r:naterial External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E: boundary Monitoring Fan housing . Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-113 Table 3.3.2-5: Containment Cooling HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Flex connection Pressure Elastomer Air-indoor Change in material boundary (ext) properties Flex connection Pressure Elastomer Air-indoor Cracking boundary (ext) Flex connection Pressure Elastomer Air-indoor Loss of material -boundary (ext) wear Flex connection Pressure Elastomer Air -indoor (int) Change in material boundary properties Flex connection Pressure Elastomer Air -indoor (int) Cracking boundary Flex connection Pressure Elastomer Air -indoor (int) Loss of material -boundary wear Heat exchanger Heat transfer Copper alloy Condensation Loss of material (fins) (ext) Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (fins) (ext) transfer 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring *External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F3.AP-113 3.3.1-82 A Monitoring External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F3.AP-102 3.3.1-76 A Monitoring Internal Surfaces in Vll.F3.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Page 3.3-114 Table 3.3.2-5: Containment Cooling HVAC System Component Intended Type Function Material Environment Heat exchanger Pressure Carbon steel Air-indoor (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) (housing) boundary Heat exchanger Heat transfer Copper alloy Condensation (tubes) (ext) Heat exchanger Pressure Copper alloy Condensation (tubes) boundary (ext) Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Reduction of heat transfer Loss of material. Reduction of heat transfer Loss of material None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.F3.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Water Chemistry Vll.F3.AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F3.AP-203 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-123 3.3.1-120 A Page 3.3-115 Table 3.3.2-5: Containment Cooling HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Waste water Loss of material boundary (int) Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary 3.0 Aging Management Review Results Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Internal Surfaces in Vll.ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Page 3.3-116 Table Control Room HVAC System Component Intended Type Function Material Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Stainless steel boundary Damper Pressure Carbon steel boundary Damper housing Pressure Carbon steel boundary Damper housing Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary Ducting Pressure Carbon steel boundary 3.0 Aging Management Review Results ( Table 3.3.2-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Control Room HVAC System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NU REG-Table 1 Environment Management Programs. 1801 Item Item Notes Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B (ext) Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B (ext) Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B (ext) Air-indoor Loss of material External Surfaces Vll.F1.A-10 3.3.1-78 A (ext) Monitoring Air-indoor.(i.nt) Loss of material External Surfaces V.A.E-29 3.2.1-44 E Monitoring Air -outdoor Loss of material Internal Surfaces in Vlll.B1 .SP-59 3.4.1-36 c (int) Miscellaneous Piping and Ducting Components Air-indoor Loss of material External Surfaces Vll.F1.A-10 3.3.1-78 A (ext) Monitoring Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E Monitoring Air -outdoor Loss of material Internal Surfaces in Vlll.B1 .SP-59 3.4.1-36 c (int) Miscellaneous Piping and Ducting Components Page \ )

Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Ducting Pressure Elastomer Air-indoor Change in material boundary (ext) properties Ducting Pressure Elastomer Air-indoor Cracking boundary (ext) Ducting Pressure Elastomer Air -indoor (int) Loss of material -boundary wear Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary 3.0 Aging Management Review Results Aging Management Programs Periodic Surveillance and Preventive Maintenance Periodic Surveillance and Preventive Maintenance Periodic Surveillance and Preventive Maintenance External Surfaces Monitoring Periodic Surveillance and Preventive Maintenance External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.F1.AP-102 3.3.1-76 E Vll.F1.AP-102 3.3.1-76 E Vll.F1 .AP-103 3.3.1-96 E Vll.F1.A-10 3.3.1-78 A Vll.F1 .A-10 3.3.1-78 E V.A.E-29 3.2.1-44 E Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Page 3.3-118 Table 3.3.2-6: Control Room HVAC System Component Intended Type Function Material Environment Fan housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Carbon steel Air-indoor boundary (ext) Filter housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Air -indoor (int) boundary Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air -indoor (int) boundary 3.0 Aging Management Review Results ( \ Aging Effect Requiring Management Loss of material Loss of material Loss of material None None Change in material properties Cracking Loss of material -wear Loss of material -wear Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Periodic V.A.E-29 3.2.1-44 E Surveillance and Preventive Maintenance External Surfaces Vll.F1.A-10 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.F1.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F1.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F1.AP-113 3.3.1-82 A Monitoring Internal Surfaces in Vll.F1.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components Page 3.3-119 Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Heat transfer Copper alloy Condensation Loss of material (fins) (ext) ' Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (fins) (ext) transfer Heat exchanger Pressure Carbon steel Air-indoor Loss of material (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material (housing) boundary Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material (housing) boundary Heat exchanger Heat transfer Copper alloy Condensation Reduction of heat (tubes) (ext) transfer Heat exchanger Pressure Copper alloy Condensation Loss of material (tubes) boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information .Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Internal Surfaces in Vll.G.AP-143 3.3.1-89 C, 306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components External Surfaces Vll.F1.AP-41 3.3.1-80 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in ----H Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Page 3.3-120 Table 3.3.2-6: Control Room HVAC System Component Intended Type Function Material Environment Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Heater housing Pressure Carbon steel Air-indoor boundary (ext) Heater housing Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Waste water boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of heat transfer Loss of material Loss of material Loss of material Loss of material Loss of material None Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Water Chemistry Vll.F1 .AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F1 .AP-203 3.3.1-46 A Control -Closed Treated Water Systems External Surfaces Vll.F1.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F1.A-10 3.3.1-78 c Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-121 Table 3.3.2-6: Control Room HVAC System Aging Effect Component Intended Requiring Type Function Material Environment Management Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) Loss of material boundary Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Stainless steel Waste water Loss of material boundary (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.F1 .A-10 3.3.1-78 c Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-122 Table 3.3.2-7 Emergency Diesel Generator System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program* 1801 Item Item Notes Blower Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Blower Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components Blower Pressure Carbon steel Exhaust gas Loss of material Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A boundary (int) Miscellaneous Piping and Ducting Components Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.1.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Expansion joint Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results

Page 3.3-123 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Expansion joint Pressure Stainless steel Air -indoor (int) Cracking -fatigue boundary Expansion joint Pressure Stainless steel Exhaust gas Cracking boundary (int) Expansion joint Pressure Stainless steel gas Cracking -fatigue boundary (int) Expansion joint Pressure Stainless steel Exhaust gas Loss of material boundary (int) Expansion joint Pressure Stainless steel Lube oil (int) Loss of material boundary Expansion joint Pressure Stainless steel Treated water Loss of material boundary (int) Expansion joint Pressure Stainless steel Treated water Cracking boundary > 1.40°F (int) Expansion joint Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program TLAA-metal fatigue Periodic Surveillance and Preventive Maintenance TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----H Vll.H2.AP-128 3.3.1-83 E ----H Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Oil Analysis Vll.H2.AP-138 3.3.1-100 A, 302 Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Water Chemistry VI I. C2.AP-186 3.3.1-43 c Control -Closed Treated Water Systems Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Page 3.3-124 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environ.ment Management Filter housing Pressure Aluminum Air-indoor None boundary (ext) Filter housing Pressure Aluminum Condensation Loss of material boundary (int) Filter housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Filter housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Filter housing Pressure Carbon steel Fuel oil (int) Loss of material boundary Filter housing Pressure Carbon steel Lube oil (int) Loss of material boundary Flame arrestor Pressure Carbon steel . Air -outdoor
Loss of material
boundary (ext) Flame arrestor Pressure Carbon steel Air -outdoor Loss of material boundary (int) Flow element Pressure Stainless steel Air-indoor None boundary (ext) Flow element Pressure Stainless steel Fuel oil (int) Loss of material boundary Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) 3.0 Aging Management Review Results Aging Management *Program None Compressed Air Monitoring External Surfaces
Monitoring Waterford Steam Electric Station, *unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.J.AP-135 3.3.1-113 A Vll.F2.AP-142 3.3.1-92 E Vll.l.A-77 3.3.1-78 A Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Diesel Fuel
Vll.H1.AP-105 3.3.1-70 A,303 Monitoring " Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring External Surfaces ----G, 305 Monitoring None Vll.J.AP-17 3.3.1-120 A Diesel Fuel Vll.H1 .AP-136 3.3.1-71 A, 303 Monitoring None Vll.J.AP-123 3.3.1-120 c Page 3.3-125 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Stainless steel Treated water Loss of material (channel head) boundary (int) Heat exchanger Heat transfer Aluminum Air-indoor Reduction of heat (fins) * (ext) transfer Heat exchanger Pressure Carbon steel Air-indoor Loss of material (housing) boundary (ext) Heat exchanger Pressure Carbon steel Air -indoor (int) Loss of material. (housing) boundary Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) HeC!t exchanger Pressure Carbon steel with Fuel oil (int) Loss of coating (shell) boundary internal coating integrity Heat exchanger Pressure Carbon steel with Fuel oil (int) Loss of material (shell) ' boundary
internal coating Heat exchanger Pressure Carbon steel with Lube oil (int) Loss of coating (shell boundary internal coating integrity Heat exchanger Pressure Carbon steel with Lube oil (int) Loss of material (shell) boundary internal coating Heat exchanger Pressure Carbon steel with Treated water Loss of coating (shell) boundary internal coating (int) integrity 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Water Chemistry Vll.C2.A-52 3.3.1-49 c Control -Closed Treated Water Systems Internal Surfaces in ----G Miscellaneous Piping and Ducting Components External Surfaces Vll.H2.AP-41 3.3.1-80 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.H2.AP-41 3.3.1-80 A Monitoring Coating Integrity Vll.H2.A-416 3.3.1-138 B Coating Integrity --G Coating Integrity Vll.H1 .A-416 3.3.1-138 B Coating Integrity Vll.H1 .A-414 3.3.1-139 B Coating Integrity Vll.H1 .A-416 3.3.1-138 B Page 3.3-126 Table 3.3.2-7: Diesel Generator System " Component Intended Type Function
Material Environment Heat exchanger Pressure Carbon steelwith Treated water (shell) boundary internal coating (int) Heat exchanger Pressure Stainless steel Fuel oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Lul;>e oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water *(tube sheet) boundary : (ext) Heat exchanger Pressure steel Treated water (tube sheet) boundary > 140°F (int) Heat exchanger . .Pressure Stainless steel Treated water (tube sheet) boundary > 140°F (int) ** Heat exchanger Heat transfer Copper alloy > Air""" indoor (tubes) 15% zinc-(ext) (inhibited) Heat exchanger Pressure Copper alloy > Air-indoor (tubes) boundary 15%iinc . (ext) (inhibited) 3.0 Aging. Management Review Results Aging Effect Requiring M;magement Loss qf material .Loss of material Loss of material Loss of material Cracking Loss of material Reduction of heat transfer .. None Aging Management Program Coating Integrity Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item* Notes Vll.H1 .A-414 3.3.1-139 B Vll.H2.AP-136 3.3.1-71 C,303 Vll.H2.AP-138 3.3.1-100 C,302 Vll.C2.A-52 3.3.1-49 c i Vll.E3.AP-192 3.3.1-44 c Vll.C2.A-52 3.3.1-49 c Internal Surfaces in --*--G Miscellaneous Piping al')d Ducting Components -None Vll.J.AP-144 3.3.1-114 A Page 3.3-127 r Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management < Heat exchanger Heat transfer Copper alloy > Treated water Reduction of heat (tubes) 15% zinc (int) transfer (inhibited) Heat exchanger Pressure Copper alloy > Treated water Loss of material (tubes) boundary 15% zinc : (int) (inhibited) Heat exchanger Heat transfer Stainless steel Fuel oil (ext) Reduction of heat (tubes) transfer Heat exchanger Pressure Stainless steel Fuel oil (ext) Loss of material (tubes) boundary Heat exchanger Pressure Stainless steel Fuel oil (ext)* Loss of material -(tubes) boundary wear Heat exchanger Heat transfer Stainless steel Lube oil (ext) Reduction of heat (tubes) . transfer Heat exchanger Pressure Stainless steel Lube oil (ext) Loss of material (tubes) boundary Heat exchanger Flressure Stainless steel Lube oil (ext) Loss of material -(tubes) boundary wear 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Diesel Fuel . Monitoring Diesel Fuel Monitoring Periodic Surveillance and Preventive Maintenance Oil Analysis Oil Analysis Periodic Surveillance and Preventive Maintenance Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-205 3.3.1-50 c Vll.E1 .AP-203 3.3.1-46 c ----G Vll.H2.AP-136 3.3.1-71 C,303 ----G V.D1.EP-79 3.2.1-51 C, 302 Vll.H2.AP-138 3.3.1-100 C, 302 --. --H Page 3.3-128 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Heat exchanger Heat transfer Stainless steel Treated water (tubes) (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (int) Heater housing Pressure Stainless steel Air-indoor boundary (ext) Heater housing Pressure Stainless steel Lube oil (int) boundary 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Closed Treated Water Systems Loss of material -Periodic wear Surveillance and Preventive Maintenance Reduction of heat Water Chemistry transfer Control -Closed Treated Water Systems Loss of material Water Chemistry Control -Closed Treated Water Systems None None Loss of material Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c ----H Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c Vll.J.AP-123 3.3.1-120 c Vll.H2.AP-138 3.3.1-100 C, 302 Page 3.3-129 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Heater housing Pressure Stainless steel Treated water boundary > 140°F (int} Heater housing Pressure Stainless steel Treated water boundary > 140°F (int) Level indicator Pressure Copper alloy > Air-indoor boundary 15% Zn or> 8% (ext) Al Level indicator Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Level indicator Pressure Copper alloy > Treated water boundary 15% Zn or> 8% (int) Al Level indicator Pressure Glass Air-indoor boundary (ext) Level indicator Press lire Glass Treated water boundary (int) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control 3.0 Aging Management Review Results Aging Effect Requiring Management Cracking Loss of material None Loss of material Loss of material None None None Aging Management Program Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.AP-186 3.3.1-43 c Vll.C2.A-52 3.3.1-49 c Vll.J.AP-144 3.3.1-114 A Selective Leaching Vll.H2.AP-43 3.3.1-72 A Water Chemistry VI I. H2.AP-199 3.3.1-46 A Control -Closed Treated Water Systems None Vll.J.AP-166 3.3.1-117 A None Vll.J.AP-166 3.3.1-117 A None Vll.J.AP-17 3.3.1-120 A Page 3.3-130 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function
Material. Environment Management Orifice
Pressure Stainless steel Condensation Loss of material boundary (int) Flow control Piping Pressure Carbon steel
Air-indoor Loss of material . boundary (ext) Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary Piping Pressure Carbon steel Air -outdoor . Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure Carbon steel Condensation
Loss of material ,. boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue boundary (int) Piping Pressure Carbon steel Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (ext) Loss of material boundary 3.0 Aging Management Review Results ( \ Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Compressed Air . Vll.D.AP-81 3.3.1-56 c Monitoring External Surfaces VILl.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Piping and Ducting Components External.Surfaces 3.3.1-78 A Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous 'Piping and Ducting Components Compressed Air Vll.D.A-26 3.3.1-55 c Monitoring TLAA-metal ----H fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Page 3.3-131 \

Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Jlllanagement Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Piping Pressure Carbon steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Soil (ext) Loss of material .. boundary Piping Pressure Carbon steel Treated water . Loss of material boundary (int) Pump casing Pressure . Carbon steel Air-indoor Loss of material boundary (ext) Pump casing Pressure Carbon steel Fuel oil (int) Loss of material boundary Pump casing Pressure Carbon steel Lube qil (int) Loss of material boundary Pump casing Pressure Carbon steel Treated water Loss of material boundary (int) Silencer Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Aging Management Program Diesel Fuel Monitoring Oil Analysis Buried ;:ind Underground . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.H1.AP-105 3.3.1-70 A, 303 Vll.H2.AP-127 3.3.1-97 A, 302

Vll.H1.AP-198 3.3.1-106 A Piping and Tanks' *. Inspection Water Chemistry Vll.H2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303* Monitoring Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 Water Chemistry Vll,H2.AP-202 3.3.1-45 A Control -Closed Treated Water Systems External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-132 Table 3.3.2-7: Emergency Diesel Generator System Component Intended Type Function Material Environment Silencer Pressure Carbon steel Air -indoor (int) boundary Silencer Pressure Carbon steel boundary (int) Strainer Filtration Carbon steel Fuel oil (ext) Strainer Filtration Carbon steel Lube oil (ext) Strainer housing Pressure Carbon steel Air-indoor boundary (ext) Strainer housing Pressure Carbon steel Fuel oil (int) boundary Strainer housing Pressure Carbon steel Lube oil (int) boundary Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Concrete (ext) boundary Tank Pressure Carbon steel Condensation boundary (int) Tank Pressure Carbon steel with Fuel oil (int) boundary internal coating 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material None Loss of material Loss of coating integrity Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Oil Analysis Vll.H2.AP-127 3.3.:1-97 A, 302 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring None ----G, 304 Compressed Air Vll.D.A-26 3.3.1-55 c Monitoring Coating Integrity Vll.H2.A-416 3.3.1-138 B Page 3.3-133 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Tank Pressure Carbon steel with Fuel oil (int) Loss of material boundary internal coating Tank Pressure Carbon steel with Treated water Loss of coating boundary internal coating (int) integrity Tank Pressure Carbon steel with Treated water Loss of material boundary internal coating (int) Thermowell Pressure Carbon steel Air-indoor Loss of material boundary (ext) Thermowell Pressure Carbon steel Lube oil (int) Loss of material boundary Thermowell Pressure Carbon steel Treated water Loss of material boundary (int) Thermowell Pressure Stainless steel Air-indoor None boundary (ext) Thermowell Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Air-indoor None boundary (ext) Tubing Pressure Copper alloy Air -indoor (int) None boundary Tubing Pressure Copper alloy Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program Coating Integrity Coating Integrity Coating Integrity External Surfaces Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None Oil Analysis None None Compressed Air Monitoring Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ----G Vll.H1 .A-416 3.3.1-138 B Vll.H1.A-414 *. 3.3.1-139 B Vll.l.A-77 3.3.1-78 A Vll.H2.AP-127 3.3.1-97 A,302 Vll.H2.AP-202 3.3.1-45 A Vll.J.AP-17 3.3.1-120 A Vll.H2.AP-138 3.3.1-100 A, 302 VI l.J .AP-144 3.3.1-114 A . Vll.J.AP-144 3.3.1-114 A Vll.D.AP-240 3.3.1-54 c Page 3.3-134 Table 3.3.2-7: E.mergency Diesel Generator System Aging Effect Component Intended Requiring. Type Function Material Environment Management Tubing Pressure Copper alloy Fuel*oil (int) . Loss of material boundary p Tubing Pressure Copper alloy Lube oil (int) Loss of material boundary Tubing Pressure Copper alloy Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) None boundary Tubing Pressure Stainless steel Condensation Loss of material boundary (int) Tubing Pressure Stainless steel Fuel oil (int) Loss of material boundary Tubing Pressure Stainless steel Lube oil* (int) Loss of material boundary lubing Pressure Stainless steel Treated water Loss of material boundary (int) '. Tubing Pressure
Stainless steel Treated water Cracking boundary > 140°F (int) 3.0 Aging Management Review Res,ults Aging 'Management Program Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None None Compressed Air Monitoring D.iesel Fuel Monitoring Oil Analysis . Water Chemistry Control -Closed . Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information NU REG-Table 1 1801 Item Item Notes Vll.H1 3.3.1-69 A,.303 Vll.H2.AP-133 . 3.3.1-99 A, 302 Vll.H2.AP-199. 3.3.1-46 A VILJ.AP-17 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A . Vll.D.AP-81 3.3.1-56 c VILH1.AP-136 3.3.1-71 A, 303 Vll.H2.AP-138 3.3.1-100 A, 302 Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-186 3.3.1-43 c Page 3.3-135

) Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring . Type Function Material Environment Management Tubing Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -indoor (irit) Loss of material boundary Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (eXt) Valve body Pressure Carbon steel Condensation Loss of material boundary* (int) Valve body Pressure Carbon steel Fuel oil (int) Loss of material boundary Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Copper alloy > Air-indoor None boundary 15% ?:nor> 8% (ext) Al Valve body Pressure Copper alloy > -indoor (int) None boundary 15% Zn or> 8% Al 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Closed Treated Water Systems External Surfaces Mol')itoring External Surfaces Monitoring External Surfaces Monitoring Compressed Air Monitoring Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.C2.A-52 3.3.1-49 c Vll.l.A-77 3.3.1-78 A V.A.E-29 3.2.1-44 E Vll.l.A-78 3.3.1-78 A Vll.D.A-26 3.3.1-55 c Vll.H1.AP-105 3.3.1-70 A, 303 Vll.H2.AP-127 3.3.1-97 A, 302 Vll.H2.AP-202 3.3.1-45 A Vll.J.AP-144 3.3.1-114 A Vll.J.AP-144 3.3.1-114 A Page 3.3-136 Table 3.3.2-7: Emergency Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Fuel oil (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Condensation Loss of material boundary (int) Valve body Pressure Stainless steel Fuel oil (int) Loss of material boundary Valve body Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Treated water Loss of material boundary (int) Valve body Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program Compressed Air Monitoring Diesel Fuel Monitoring None Compressed Air Monitoring Diesel Fuel Monitoring Oil Analysis Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vll.D.AP-240 3.3.1-54 c Vll.H1 .AP-132 3.3.1-69 A, 303 Vll.J.AP-17 3.3.1-120 A Vll.D.AP-81 3.3.1-56 c Vll.H1 .AP-136 3.3.1-71 A, 303 Vll.H2.AP-138 3.3.1-100 A, 302 Vll.C2.A-52 3.3.1-49 c Vll.C2.AP-186 3.3.1-43 c Vll.C2.A-52 3.3.1-49 c Page 3.3-137 Table 3.3.2-8 Fire Protection -Water System Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-8: Fire Protection -Water System Aging Effect Aging Component Intended Requiring Management NU REG-Table 1 Type Function Material Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor (ext) Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary Bolting Pressure Carbon steel Air-indoor (ext) Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Soil (ext) Loss of material Buried and Vll.l.AP-241 3.3.1-109 A boundary Underground Piping and Tanks Inspection Bolting Pressure Carbon steel Soil (ext) Loss of preload Bolting Integrity Vll.l.AP-242 3.3.1-14 B boundary Expansion joint Pressure Carbon steel Air-indoor (ext) Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary Monitoring Expansion joint Pressure Carbon steel Exhaust gas Loss of material Internal Surfaces in Vll.H2.AP-104 3.3.1-88 c boundary (int) Miscellaneous Piping and Ducting Components Flame arrestor Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-138 3.3.2-8: Fire Protection -Watel'.' System I Component Intended* Type* Function Material* Environment Flame arrestor Pressure

Carbon steel Air --outdoor boundary (int) Flex hose Pressure Copper alloy > Air-indoor (ext) boundary 15% Zn or> 8% Al flex hose Pressure Copper alloy > Fuel oil (int) boundary 15% Zn or> 8% Al Heat exchanger Pressure. Carbon steel Air-indoor (ext) (housing) boundary Heat exchanger Pre.ssure Carbon steel Treated water (housing) boundary (int) .. Heat exchanger Heat transfer
Copper alloy
Raw water (irit) (tubes) .. Heat exchanger Pressure Copper alloy
Raw water (int) (tubes) boundary Heat exchanger Heat transfer Copper alloy neated water (tubes) (ext) 3.0 Aging Management Review Results .* Aging Effect Requiring Management Loss of material None Loss of material Loss of material Loss of material Reduction of heat transfer Loss of material Reduction ofheat transfer Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information .,, Aging Management NU REG-Table 1 'Program
1801 Item Item. Notes
Internal Surfaces in Vll.G.A-404 3.3.1-131 E Miscellaneous
Piping anti Due.ting Components None , Vll.J.AP-144 3.3.1-114 A Diesel Fuel Vll.G.AP-132 3.3.1-69 I A, 303 Monitoring External Surfaces Vll.G.AP-41 3.3.1-:80 A Monjtoring . Water Chemistry Vll.C2.AP-189 3.3.1-46 c Control -Closed Treated Water $ystems Internal Surfaces in Vll.C1.A-72 3.3.1-42 E 'Miscellaneous Piping and Ducting Components Fire Water System Vll.G.AP-197 3.3.1-64 D Water Chemistry 3.3.1-50 c Control -Closed Treated Water Systems Page 3.3-139 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Heat exchanger Pressure Copper alloy Treated water Loss of material (tubes) boundary (ext) Hydrant Pressure Gray cast iron Air -outdoor Loss of material boundary (ext) Hydrant Pressure Gray cast iron Raw water (int) Loss of coating boundary with internal integrity coating Hydrant Pressure Gray cast iron Raw water (int) Loss of material boundary with internal coating Hydrant Pressure Gray cast iron Raw water (int) Loss of material boundary with internal coating Hydrant Pressure Gray cast iron Soil (ext) Loss of material boundary Hydrant Pressure Gray cast iron Soil (ext) Loss of material boundary Insulated piping Pressure Carbon steel Air -outdoor Loss of material components boundary (ext) Piping Pressure Carbon steel Air-indoor (ext) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Water Chemistry Vll.E1 .AP-203 3.3.1-46 c Control -Closed Treated Water Systems Fire Water System Vll.G.AP-149 3.3.1-63 B Coating Integrity Vll.G.A-416 3.3.1-138 B Coating Integrity Vll.G.A-414 3.3.1-139 B Coating Integrity Vll.G.A-415 3.3.1-140 B,308 Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Selective Leaching Vll.G.A-02 3.3.1-72 A External Surfaces
Vll.G.A-405 3.3.1-132 A Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-140 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure Carbon steel Condensation Loss of material boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue -boundary (int) Piping Pressure Carbon steel Exhaust gas Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Piping Pressure Carbon steel Raw water (int) Loss of material boundary Piping Pressure Carbon steel Raw water (int) Recurring internal boundary corrosion Piping Pressure Carbon steel Soil (ext) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vll.G.A-404 3.3.1-131 E Miscellaneous Piping and Ducting Components Fire Water System Vll.G.A-404 3.3.1-131 B TLAA-metal ----G fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 c Miscellaneous Piping and Ducting Components Diesel Fuel Vll.G.AP-234 3.3.1-68 A, 303 Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B Fire Water System Vll.G.A-400 3.3.1-127 E Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Page 3.3-141 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Waste water Loss of material boundary (int) Piping Pressure Gray cast iron Raw water (int) Loss of material boundary Piping Pressure Gray cast iron Raw water (int) Loss of material boundary Piping Pressure Gray cast iron Soil (ext) Loss of material boundary Piping Pressure Gray cast iron Soil (ext) Loss of material boundary Piping Pressure Plastic (PVC) Raw water (int) None boundary Piping Pressure Plastic (PVC) Soil (ext) None boundary Pump casing Pressure Carbon steel Air -indoor (ext) Loss of material boundary Pump casing Pressure Carbon steel Raw water (int) Loss of material boundary Silencer Pressure Carbon steel Air -outdoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components Fire Water System Vll.G.A-33 3.3.1-64 B Selective Leaching Vll.G.A-51 3.3.1-72 A Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection Selective Leaching Vll.G.A-02 3.3.1-72 A None ----G None ----G External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Page 3.3-142 Table 3.3.2-8: Fire Protection -Water System Component Intended Type. Function Material Silencer Pressure Carbon steel boundary Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow contror Al Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al ' Sprinkler Pressure Copper alloy > boundary 15% Zn or> 8% Flow control Al Strainer Filtration Stainless steel Strainer Filtration Stainless steel Strainer housing Pressure Carbon steel boundary Strainer housing Pressure Carbon steel boundary 3.0 Aging Management Review Results Aging Effect Requiring Environment Management Exhaust gas . Loss of material (int) Air-indoor (ext) None Condensation Loss of material (int) Raw water (int) Loss of material Raw water (int) Loss of material Condensation Loss of material (ext) Raw water (ext) Loss of material Air-indoor (ext) Loss of material Raw water (int) Loss of material Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in 3.3.1-88 c Miscellaneous Piping and Ducting Components None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.A-403 3.3.1-130 8 Fire Water System Vll.G.A-403 3.3.1-130 8 Selective Leaching Vll.G.A-47 3.3.1-72 A Fire Water System Vll.G.A-412 3.3.1-136 D Fire Water System Vll.G.A-55 3.3.1-66 8 External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-33 3.3.1-64 8 Page 3.3-143 Table 3.3.2*8: Fire Protection -Water System i Component Intended* Function Material Environment Strainer housing Pressure Copper alloy > Air-indoor (ext) boundary or> 8% .. Al Strainer housing Pressure Copper alloy > Raw water (int) boundary 15%Zn or> 8% Al Strainer housing Pressure Copper alloy > Raw water (int)
I boundary 15% Zn or> 8% Al Tank Pressure Carbon steel Air-indoor (ext) boundary Tank Pressure Carbon steel Air -outdoor boundary (ext) Tank Pressure Carbon steel Concrete (ext) boundary Tank Pressure Carbon steel Condensation boundary (int) Tank Pressure Carbon steel Fuel oil (int) boundary Tank . Pressure Carbon steel Raw water (int) boundary with*internal . . coating Tank Pressure Carbon steel Raw water (int) boundary with internal 3.0 Aging Management Review Results Aging Effect Requiring MaF!agement None Loss of material Loss of material Loss of material Loss of material Loss of material Loss o_f material Loss of material Loss of coating Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.AP-197 3.3.1-64 B .Selective Leaching. Vll.G.A-47 3.3.1-72 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-412 3.3.1-136 B Fire Water System Vll.G.A-402 3.3.1-129 E Fire Water System Vll.G.A-412 3.3.1-136 B Diesel Fuel Vll.H1.AP-105 3.3.1-70 C,303 Monitoring Fire Water System ----H Fire Water System Vll.G.A-412 3.3.1-136 B Page 3.3-144 Table 3.3.2-8: Fire Protection -Water System Component Intended Type Function Material Environment Tank Pressure Carbon steel Soil (ext) boundary Trap Pressure Gray cast iron Air-indoor (ext) boundary Trap Pressure Gray cast iron Condensation boundary (int) Tubing Pressure Copper alloy Air-indoor (ext) boundary Tubing Pressure Copper alloy Condensation boundary (int) Tubing Pressure Copper alloy Fuel oil (int) boundary Tubing Pressure Copper alloy Raw water (int) boundary Tubing Pressure Stainless steel Air -indoor (ext) boundary Tubing Pressure Stainless steel Raw water (int) boundary Valve body Pressure Carbon steel Air-indoor (ext) boundary Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Condensation boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material None Loss of material Loss of material Loss of material None Loss of material Loss of material Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Fire Water System Vll.G.A-402 3.3.1-129 E External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B None Vll.J.AP-144 3.3.1-114 A Fire Water System Vll.G.A-404 3.3.1-131 B Diesel Fuel Vll.G.AP-132 3.3.1-69 A,303 Monitoring Fire Water System Vll.G.AP-197 3.3.1-64 B None Vll.J.AP-123 3.3.1-120 A Fire Water System Vll.G.A-55 3.3.1-66 B External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Page 3.3-145 Table 3.3.2-8: Fire Protection -Water System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Carbon steel Fuel oil (int) Loss of material boundary Valve body Pressure Carbon steel Raw water (int) Loss of material boundary Valve body Pressure Carbon steel Soil (ext) Loss of material boundary Valve body Pressure Copper alloy > Air -indoor (ext) None boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Air -outdoor Loss of material boundary 15% Zn or> 8% (ext) Al Valve body Pressure Copper alloy > Condensation Loss of material boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Fuel oil (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Raw water (int) Loss of material boundary 15% Zn or> 8% Al Valve body Pressure Copper alloy > Raw water (int) Loss of material boundary 15% Zn or> 8% Al 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Diesel Fuel Vll.G.AP-234 3.3.1-68 A, 303 Monitoring Fire Water System Vll.G.A-33 3.3.1-64 B Buried and Vll.G.AP-198 3.3.1-106 A Underground Piping and Tanks Inspection None Vll.J.AP-144 3.3.1-114 A External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Diesel Fuel Vll.G.AP-132 3.3.1-69 A, 303 Monitoring Fire Water System Vll.G.AP-197 3.3.1-64 B Selective Leaching Vll.G.A-47 3.3.1-72 A Page 3.3-146 Table 3.3.2-8: Fire Protection -Water System Component lntende.d Type Function Material Environment Valve body Pressure Gray cast iron Air-indoor (ext) boundary Valve body Pressure Gray cast iron Condensation boundary (int) Valve body Pressure Gray cast iron Raw water (int) boundary Valve body Pressure Gray cast iron Raw water (int) boundary Valve body Pressure Stainless steel Air-indoor (ext) boundary Valve body Pressure Stainless steel Condensation boundary (int) Valve body Pressure Stainless steel Raw water (int) boundary
Vortex breaker Flow control Carbon steel Raw water (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss qf material Loss of material Loss of material Loss of material None Loss of material Los!S of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Fire Water System Vll.G.A-404 3.3.1-131 B Fire Water System Vll.G.A-33 3.3.1-64 B Selective Leaching Vll.G.A-51 3.3.1-72 A None Vll.J.AP-123 3.3.1-120 A Fire Water System Vll.G.A-404 3.3.1-131 B Fire Water System Vll.G.A-55 3.3.1-66 B Fire Water System Vll.G.A-412 3.3.1-136 D Page 3.3-147 Table 3.3.2-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fire Protection RCP Oil Collection System Summary of Aging Management Evaluation Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Aging Component . Intended Requiring_ Management NU REG-Table 1 Type Function Material
Environment Management Program 1801 Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material .Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Drip pan-Pressure Carbon steel Air-'-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Drip pan Pressure Carbon steel Lube oil (int) Loss of material Periodic Vll.G.AP-117 3.3.1-97 E boundary Surveillance and .. Preventive Maintenance *Drip pan Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A *boundary (ext) Drip pan Pressure Stainless steel Lube oil (int) Loss of material Periodic Vll.G.AP-138 3.3.1-100 E boundary . Surveillance and Preventive .. Maintenance Enclosure Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-148 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Enclosure Pressure Carbon steel Lube oil (int) Loss of material boundary Enclosure Pressure Stainless steel Air-indoor None boundary (ext) Enclosure Pressure Stainless steel Lube oil (int) Loss of material boundary Flame arrestor Pressure Carbon steel Air-indoor Loss of material boundary (ext) Flame arrestor Pressure Carbon steel Air -indoor (int) Loss of material boundary Flex hose Pressure Stainless steel indoor None boundary (ext) Flex hose Pressure Stainless steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program* 1801 Item Item Notes Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Page 3.3-149 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary -Piping Pressure Carbon steel oil (int) Loss of material boundary Piping Pressure Stainless steel Air-indoor None boundary (ext) Piping Pressure Stainless steel Lube oil (int) Loss of material boundary . Sight glass Pressure Carbon steel Air-indoor Loss of material boundary (ext) Sight glass Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Lube oil (int) None boundary Strainer Filtration Stainless steel Lube oil (ext) Loss of material 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Program 1801 Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-14 3.3;1-117 A None Vll.J.AP-15 3.3.1-117 A External Surfaces Vll.G.AP-138 3.3.1-100 E Monitoring Page 3.3-150 Table 3.3.2-9: Fire Protection RCP Oil Collection System Aging Effect Component Intended Requiring Type Function Material Environment Management Strainer Filtration Stainless steel Lube oil (int) Loss of material Tank Pressure Carbon steel Air-indoor Loss of material boundary (ext) Tank Pressure Carbon steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary 3.0 Aging Management Review Results Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes External Surfaces Vll.G.AP-138 3.3.1-100 E Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance None Vll.J.AP-123 3.3.1-120 A Periodic Vll.G.AP-138 3.3.1-100 E Surveillance and Preventive Maintenance External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Periodic Vll.G.AP-117 3.3.1-97 E Surveillance and Preventive Maintenance Page 3.3-151

\ Table 3.3.2-1 O Fuel Pool Cooling and Purification System Summary of Aging Management Evaluation Table 3.3.2-10: Fuel Pool Cooling and Purification System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Heat exchanger Pressure Stainless steel Air-indoor None None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated borated Loss of material Water Chemistry (channel head) boundary water (int) Control -Primary and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material Boric Acid (shell) boundary (ext) Corrosion Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry (shell) boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.AP-125 3.3.1-12 B Vll.l.A-102 3.3.1-9 A Vll.l.AP-124 3.3.1-15 B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-123 3.3.1-120 c , Vll.A3.AP-79 3.3.1-125 C, 301 Vll.A3.A-79 3.3.1-9 A Vll.l.A-77 3.3.1-78 A Vll.A3.AP-189 3.3.1-46 A Page 3.3-152 Table 3.3.2-10: Fuel Pool Cooling and Purification System Component Intended Type . Function Material Environment . Heat exchanger Pressure Stainless steel Treated borated (tube sheet)* boundary water (ext) Heat exchanger. Pressure Stainless steel . Treated water (tube sheet) *boundary (int) Heat exchanger Heat transfer Stainless steel Treated borated (tubes) water (int) Heat exchanger Pressure

Stainless steel Treated borated (tubes) boundary water (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (ext) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (ext) Neutron Neutron Bora I Treated borated Absorber absorption water (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Reduction of heat transfer Loss of material Reduction of heat transfer
Loss of material Change in material properties Aging Management Program Water Chemistry Control -Primary and Secondary Water Chemistry Control.-Closed Treated Water Systems Water. Chemistry Control -Primary and Secondary Water Chemistry Control -Primary Secondary Water Chemistry Control -Closed Treated Water Systems Water Chemistry Control -Closed Treated Water Systems Neutron-Absorbing Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.A3.AP-79 3.3.1-125 C, 301 Vll.C2.A-52 3.3.1-49 c Vll.A3.A-10.1 3.3.1-17 A, 301 Vll.A3.AP-79 3.3.1-125 C, 301 Vll.C2.AP-188 3.3.1-50 c Vll.C2.A-52 3.3.1-49 c Vll.A2.AP-235 3.3.1-102 A Material Monitoring Page 3.3-153 Table 3.3.2-10: Fuel Pool Cooling and Purification System I Component Intended Type Function Material Environment Neutron Neutron Bora I Treated borated Absorber absorption water (ext) Neutron Neutron Bora I Treated borated Absorber absorption water (ext) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Treated borated boundary water (ext) Piping Pressure Stainless steel Treated borated boundary water (int) Piping Pressure Stainless steel Waste water boundary (int) Pump casing Pressure Stainless steel Air-indoor boundary (ext) Pump casing Pressure Stainless steel Treated borated boundary water (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Reduction in neutron absorption capacity None Loss of material Loss of material Loss of material None Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Neutron-Absorbing Vll.A2.AP-235 3.3.1-102 A Material Monitoring Water Chemistry Control -Primary and Secondary Neutron-Absorbing VI I .A2.AP-235 3.3.1-102 A Material Monitoring None Vll.J.AP-17 3.3.1-120 A Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None Vll.J.AP-17 3.3.1-120 A Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 Control -Primary and Secondary Page 3.3-154 Table 3.3.2-10: Fuel Pool Cooling and Purification System Component Intended Type Function Material Environment Rack Support for Stainless steel Treated borated criterion (a)(1) water (ext) equipment Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated borated boundary water (int) Tubing Pressure Stainless steel Air-indoor boundary (ext) Tubing Pressure Stainless steel Treated borated boundary water (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) Valve body Pressure Stainless steel Treated borated boundary water (int) Valve body Pressure Stainless steel Waste water boundary (int) 3.0 Aging Management Review Results ( Aging Effect Requiring Management Loss of material None Loss of material None Loss of material None Loss of material Loss of material Aging Management Program Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.A3.AP-79 3.3.1-125 C, 301 Vll.J.AP-17 3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Vll.J.AP-17 3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Vll.J.AP-17-3.3.1-120 A Vll.A3.AP-79 3.3.1-125 A, 301 Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-155 Table 3.3.2-11 Nitrogen System Summary of Aging Management Evaluation Table 3.3.2-11: Nitrogen System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Accumulator Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Accumulator Pressure Carbon steel Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Accumulator Pressure Carbon steel Gas (int) None None boundary Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity boundary (ext) Flex hose Pressure Stainless steel Air-indoor None None boundary (ext) Flex hose Pressure Stainless steel Gas (int) None None boundary Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces components boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.A-77 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.AP-126 3.3.1-12 B Vll.l.AP-263 3.3.1-15 B Vll.J.AP-17 3.3.1-120 A Vll.J.AP-22 3.3.1-120 A Vll.l.A-405 3.3.1-132 A Page 3.3-156 Table 3.3.2-11: Nitrogen System Component Intended Type Function Material Environment Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Gas (int) boundary Flow control Piping Pressure Carbon steel Air-indoor boundary (ext) Piping Pressure Carbon steel Air -indoor. (int) boundary Piping Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Gas (int) boundary Piping Pressure Carbon steel Waste water boundary (int) Regulator body Pressure Aluminum Air-indoor boundary (ext) Regulator body Pressure Aluminum Gas (int) boundary Tubing Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging _Management Review Results Aging Effect Requiring Management None None Loss of material Loss of material Loss of material None Loss of material None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes None Vll.J.AP-17 3.3.1-120 A None Vll.J.AP-22 3.3.1-120 A External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 c Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring None Vll.J.AP-6 3.3.1-121 A Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-135 3.3.1-113 A None Vll.J.AP-37 3.3.1-113 A None Vll.J.AP-17 3.3.1-120 A Page 3.3-157 Table 3.3.2-11: Nitrogen System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss*ofmaterial boundary (ext)
Tubing Pressure Stainless steel Gas (int) -None boundary Valve body Pressure Carbon steel Air..., indoor Loss of material boundary (ext)* Valve body Pressure Carbon steel Air..:. outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Gas (int) None boundary Valve body Pressure Carbon steel Wastewater Loss of material boundary (int) Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Gas (int) None. boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring External Surfaces Monitoring None External Surfaces Monitoring External Surfaces Monitoring None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.D.AP-209 3.3.1-4 ' c Vll.D.AP-221 3.3.1-6 c Vll.J.AP-22 3.3.1-120 A Vll.l.A-77 3.3.1-78 A Vll.l.A-78 3.3.1-78 A Vll.J.AP-6 3.3.1-121 A Internal Surfaces in V11.E5.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-1.7 3.3.1-120 A INone Vll.J.AP-22 3.3.1-120 A Page 3.3-158 Table 3.3.2-12 Miscellaneous HVAC Systems Summary of Aging Management Evaluation Table 3.3.2-12: Miscellaneous HVAC Systems ., Aging Effect Aging Component Intended Requiring Management . Type Function Material Environment Management Program aolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Halting Integrity boundary (ext) Bolting Pressure High strength. Air-*indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-*indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss .of preload Bolting Integrity ,. boundary steel (ext) Bolting Pressure Stainless steel Air :-indoor " Loss of preload Bolting 'Integrity boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces boundary Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item *.Notes Vll.l.AP-125 3.3.1-12 B 3.3.1-15 B
Vll.l.AP-126 3.3 .. 1-12 B Vll.l.AP.,.263 3.3.1-15 B Vll.l.A-04 3.3.1-10 D ViLl.AP-125 3.3.1-12 B Vll.l.AP-1.24 3.3.1-15 B Vll.l.AP-124 B Vll.F2.A-10 3.3.1-78 A V.A.E-29 3.2.1-44 E ' Page 3.3-159 Table 3.3.2-12: Miscellaneous HVAC Systems Aging Effect Component Intended Requiring Type Function Material Environment Management Damper housing Pressure Carbon steel Air -outdoor Loss of material boundary (int) Ducting Pressure Carbon steel Air-indoor Loss of material boundary (ext) Ducting Pressure Carbon steel Air -indoor (int) Loss of material boundary Ducting Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Ducting Pressure Carbon steel Air -outdoor Loss of material boundary (int) Fan housing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Fan housing Pressure Carbon steel, Air -indoor (int) Loss of material boundary Fan housing Pressure Carbon steel Air -indoor (int) Loss of material boundary Filter housing Pressure Carbon steel Air-indoor Loss of material boundary (ext), Filter housing Pressure Carbon steel Air -indoor (int) Loss of material boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components External Surfaces Vll.F3.A-10 3.3.1-78 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Page 3.3-160 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Filter housing Pressure Carbon steel Air -indoor (int) boundary Filter housing Pressure Carbon steel Air -outdoor boundary (int) Filter housing Pressure Stainless steel Air-indoor boundary (ext) Filter housing Pressure Stainless steel Air -indoor (int) boundary Filter housing Pressure Stainless steel Condensation boundary (int) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) Flex connection Pressure Elastomer Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material None None Loss of material Change in material properties Cracking Loss of material -wear Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.F2.AP-99 3.3.1-94 A Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F2.AP-102 3.3.1-76 A Monitoring External Surfaces Vll.F2.AP-113 3.3.1-82 A Monitoring Page 3.3-161 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Flex connection Pressure Elastomer Air -indoor (int) boundary Flex hose Pressure Stainless steel Air-indoor boundary (ext) Flex hose . Pressure Stainless steel Air -indoor (int) boundary Heat exchanger Heat transfer Copper alloy Condensation (fins) (ext) Heat exchanger Heat transfer Copper alloy Condensation (fins) (ext) Heat exchanger Pressure Carbon steel Air-indoor (housing) boundary (ext)
Heat exchanger Pressure Carbon steel Air-indoor (int) (housing) boundary Heat exchanger Pressure Carbon Air -indoor (int) (housing) boundary 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material -wear .. None None Loss of material Reduction of heat transfer Loss of materiaJ Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vll.F2.AP-103 3.3.1-96 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A -None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in 3.3.1-89 C, 306 Miscellaneous Piping and Ducting Components Internal Surfaces in ----G Miscellaneous Piping and Ducting Components External Surfaces Vll.F2.AP-41 3.3.1-80 A . Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components Page 3.3-162 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Heat exchanger Heat transfer Copper alloy Condensation (tubes) (ext) Heat exchanger Pressure Copper alloy Condensc;ition (tubes) boundary (ext) Heat exchanger Heat transfer Copper alloy Treated water (tubes) (int) Heat exchanger Pressure Copper alloy Treated water (tubes) boundary (int) Heater housing Pressure Carbon steel Air-indoor boundary (ext) Heater housing Pressure Carbon steel Air -indoor (int) boundary Heater housing Pressure Carbon steel Air -outdoor boundary (int) 3.0 Aging Management Review Results Aging Effect Requiring Management Reduction of heat transfer Loss of material Reduction of heat transfer Loss of material Loss of material Loss of material Loss of material Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in ----G* Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.G.AP-143 3.3.1-89 C,306 Miscellaneous Piping and Ducting Components Water Chemistry Vll.F2.AP-205 3.3.1-50 A Control -Closed Treated Water Systems Water Chemistry Vll.F3.AP-203 3.3.1-46 A Control Closed Treated Water Systems External Surfaces Vll.F2.AP-41 3.3.1-80 A Monitoring External Surfaces V.A.E-29 3.2.1-44 E Monitoring Internal Surfaces in Vlll.81 .SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components Page 3.3-163 Table 3.3.2-12: Miscellaneous HVAC Systems Aging Effect Component Intended Requiring Type Function Material Environment Management Nozzle Pressure Stainless steel Air-indoor None boundary (ext) Flow control Nozzle Pressure Stainless steel Air -indoor (int) None boundary Flow control Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -indoor (int) Loss of material boundary Pump casing Pressure Stainless steel Air-indoor None boundary (ext) Pump casing Pressure Stainless steel Air -indoor (int) None boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Air -indoor (int) None boundary Sight glass Stainless steel Air-indoor None boundary (ext) Sight glass Pressure Stainless steel Air -indoor (int) None boundary 3.0 Aging Management Review Results Aging Management Program None None External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.l.A-77 3.3.1-78 A Internal Surfaces in V.A.E-29 3.2.1-44 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A None Vll.J.AP-14 3.3.1-117 A None Vll.J.AP-48 3.3.1-117 A None VI l.J .AP-123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120 A Page 3.3-164 Table 3.3.2-12: Miscellaneous HVAC Systems Component Intended Type Function Material Environment Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Air -indoor (int) boundary Tubing Pressure Stainless steel Air-indoor boundary (ext) Tubing Pressure Stainless steel Air -indoor (int) boundary Tubing Pressure Stainless steel Air -outdoor boundary (ext) Tubing Pressure Stainless steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Air-indoor . boundary (ext) Valve body Pressure Carbon steel Air -indoor (int) boundary Valve body Pressure Carbon steel Air -indoor (int) boundary Valve body Pressure Carbon steel Waste water boundary (int) Valve body Pressure Stainless steel Air-indoor boundary (ext) 3.0 Aging Management Review Results Aging Effect Requiring Management None None None None Cracking Loss of material Loss of material Loss of material Loss of material Loss of material None Aging Management Program None None None None External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.J.AP-123 3.3.1-120 A Vll.F2.AP-209 3.3.1-4 A Vll.F2.AP-221 3.3.1-6 A Vll.l.A-77 3.3.1-78 A V.A.E-29 3.2.1-44 E Internal Surfaces in V.A.E-29 3.2.1-44 A
Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A Page 3.3-165 Table 3.3.2-12: Miscellaneous HVAC Systems I c Aging Effect Component Intended 'Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Air -indoor (int) None boundary Valve body Pressure Stainless steel Wastewater Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-123 3.3.1-120 A Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-166 Table 3.3.2-13 Auxiliary Diesel Generator System Summary of Aging Management Evaluation Table 3.3.2-13:Auxiliary Diesel Generator System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Expansion joint Pressure Stainless steel Air-indoor None None boundary (ext) Flame arrestor Pressure Aluminum Air -outdoor Cracking External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Aluminum Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Aluminum Air -outdoor Cracking External Surfaces boundary (int) Monitoring Flame arrestor Pressure Gray cast iron Air -outdoor Loss of material External Surfaces boundary (ext) Monitoring Flame arrestor Pressure Gray cast iron Air -outdoor Loss of material External Surfaces boundary (int) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.l.AP-125 3.3.1-12 B Vll.l.AP-124 3.3.1-15 B Vll.l.AP-124 3.3.1-15 B Vll.J.AP-123 3.3.1-120 A ----H Vll.l.AP-256 3.3.1-81 A ----H Vll.H1.A-24 3.3.1-80 A ----G, 305 Vll.l.A-77 3.3.1-78 A Page 3.3-167 Table 3.3.2-13:Auxiliary Diesel Generator System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Air -outdoor Loss of material boundary (int) Piping Pressure* Carbon steel Condensation Loss of material boundary (int) Piping Pressure Carbon steel Exhaust gas Cracking -fatigue boundary (int) Piping Pressure Carbon steel Exhaust gas Loss of material boundary (int) Piping Pressure Carbon steel Fuel oil (int) Loss of material boundary Silencer. Pressure Carbon steel Air-*indoor Loss of material boundary (ext) Silencer Pressure Carbon steel Condensation Loss of material boundary (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes External Surfaces Vll.H1.A-24 3.3.1-80 A Monitoring Internal Surfaces in Vlll.B1.SP-59 3.4.1-36 c Miscellaneous Piping and Ducting Components Internal Surfaces in Vll.H2.A-23 3.3.1-89 A Miscellaneous Piping and Ducting Components TLAA-metal ----H fatigue Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Internal Surfaces in Vll.H2.A-23 3.3.1-89 A Miscellaneous Piping and Ducting Components Page 3.3-168 Table 3.3.2-13:Auxiliary Diesel Generator System Component Intended Type Function Material Environment Silencer Pressure Carbon steel Exhaust gas boundary (int) Tank Pressure Carbon steel Air-indoor boundary (ext) Tank Pressure Carbon steel Fuel oil (int) boundary . Tubing Pressure Carbon steel Air-indoor boundary (ext) Tubing Pressure Carbon steel Fuel oil (int) boundary Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Fuel oil (int) boundary 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Loss of material Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Internal Surfaces in Vll.H2.AP-104 3.3.1-88 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1 .AP-105 3.3.1-70 A, 303 .Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel Vll.H1.AP-105 3.3.1-70 A, 303 Monitoring External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring Diesel Fuel VJl.H1.AP-105 3.3.1-70 A, 303 Monitoring Page 3.3-169 Table 3.3.2-14:Plant Drains Intended Component Type Function Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary. Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary Bolting Pressure boundary Piping Pressure boundary Piping Pressure boundary Piping Pressure boundary 3.0 Aging Management Review Results Table 3.3.2-14 Plant Drains Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NUREG-1801 Table 1 M;;iterial Environment Management Program Item Item Notes Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B (ext) Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B (ext) Carbon steel Waste water Loss of material Bolting Integrity ----G (ext) Carbon steel Waste water Loss of preload Bolting Integrity ----G (eXt) .. Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B steel (ext) Stainless Air-*outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B steel (ext) Stainless Air -outdoor _Loss of preload Bolting Integrity Vl,l.l.AP-263 3.3.1-15 B steel (ext) Carbon steel . Air-indoor .Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A (ext) Monitoring Carbon steel Air -o*utdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A (ext) Monitoring . Carbon steel Air -outdoor Loss of material Internal Surfaces in VllLB1.SP-59 3.4.1-36 c (int) Miscellaneous
Piping and Ducting Components Page 3.3-170 Table 3.3.2-14:Plant Drains Aging Effect Intended -Requiring Component Type Function Material Environment Management Piping Pressure Carbon steel _ Soil (ext)' ' 'Loss of material boundary '* Piping Pressure .Carbon steel Wastewater Loss of material boundary (int) \ \ Piping Pressure Stainless Air -indqor None boundary steel (ext) Piping Pressure Stainless Air-in.door (int) None boundary steel Piping Pre.ssure Stainless Treated water . Loss qf material boundary steel (int) Piping Pressure Stainless Wastewater .of mate.rial boundary steel (int) Pump casing Pressure Carbon steel Wastewater Loss of material boundary (ext) Pi.Imp casing Pressure. Carbon steel W(3ste water Loss of material boundary (int) 3.0 Aging Manageme11t Review Results Aging Management Program Buried and Underground Piping and Tanks Inspection Waterford Steam Electric Station, Unit 3 License Renewal Application , Technical Information NUREG-1801 Table 1 Item Item Notes* VILC1.AP-;198 3.3.1-106 c Internal Surfaces in VI I. E5 .. AP-28.1 3.3.1-91 A Miscellaneous Piping and Ducting
Components Npne* VILJ.AP-123 . 3.3.1-120 A None. Vll.J.AP-123 3.3.1-120 A ' Water Chemistry Vlll.81.SP-87 3.4.1-16 C, 301 Control -Primary and Secondary Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A . Mi.scellaneous Piping and Ducting ' Components Surfaces VILE5.A-410 3.3.1-135 A Monitoring Periodic Vll.E5.A-410 3 .. 3.1-135 E Surveillance and Preventive Maintenance Page 3.3-171 Table 3.3.2-14:Plant Drains* Aging Effect -Intended Requiring Component Type Function Material Environment Management Pump casing Pressure Gray cast iron Air -outdoor Loss of material boundary (ext) Pump casing Pressure Gray cast iron Waste water Loss of material boundary (int) Pump casing Pressure Gray cast iron Waste water Loss of material boundary (int) Strainer Filtration Stainless Waste water Loss of material steel (ext) Strainer housing Pressure Stainless Air-indoor None boundary steel (ext) Strainer housing Pressure Stainless Air -outdoor Cracking boundary steel (ext) Strainer housing Pressure Stainless Air -outdoor Loss of material boundary steel (ext) Strainer housing Pressure Stainless Treated water Loss of material boundary steel (int) Strainer housing Pressure Stainless Waste water Loss of material boundary steel (int) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Periodic Vll.E5.A-410 3.3.1-135 E Surveillance and Preventive Maintenance Selective Leaching Vll.E5.A-407 3.3.1-72 A Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components None Vll.J.AP-123 3.3.1-120 A External Surfaces Vll.C1 .AP-209 3.3.1-4 c Monitoring External Surfaces Vll.C1 .AP-221 3.3.1-6 c Monitoring Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 Control -Primary and Secondary Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Page 3.3-172 Table 3.3.2-14:Plant Drains Aging Effect Intended Requiring Component Type Function Material Environment Management Tubing Pressure Stainless Air-indoor None boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material boundary steel (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Waste water Loss of material boundary (int) Valve body Pressure Copper alloy Air -outdoor Loss of material boundary (ext) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes. None Vll.J.AP-123 3.3.1-120 A Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.A-77 3.3.1-78 A Monitoring External Surfaces Vll.l.A-78 3.3.1-78 A Monitoring Internal Surfaces in Vll.E5.AP-281 3.3.1-91 A Miscellaneous Piping and Ducting Components External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring Page 3.3-173 Table 3.3.2-14: Plant Drains Aging Effect Intended Requiring Component Type Function Material Environment Management Valve body Pressure Copper alloy Waste water Loss of material boundary (int) Valve body Pressure Copper alloy Air -outdoor Loss of material boundary > 15% Zn or (ext) >8%AI Valve body Pressure Copper alloy Wastewater Loss of material boundary > 15% Zn or (int) >8%AI Valve body Pressure Copper alloy Wastewater Loss of material boundary > 15% Zn or (int) -.. >8%AI Valve body Pressure Gray cast iron Wastewater Loss of material boundary (ext) Flow control Valve body Pressure Gray cast iron Wastewater Loss of material boundary (ext) ' Flow control Valve body Pressure Gray cast iron Wastewater . Loss of material boundary (int) Flow control 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NUREG-1801 Table 1 Program Item Item Notes Internal Surfaces in Vll.E5.AP-272 3.3.1-95 A Miscellaneous Piping and Ducting . Components External Surfaces Vll.l.AP-159 3.3.1-81 A Monitoring . Internal Surfaces in VII. E5.AP-272 3.3.1-95 A Miscellaneous Piping and Ducting Components Selective Leaching Vll.E5.A-407 3.3.1-72 A External Surfaces Vll.E5.A-410 3.3.1-135 c Monitoring Selective Leaching Vll.E5.A-407 3.3.1-72 A Internal Surfaces in VI I. E5.AP-281 3.3.1-91 A Miscell*ineous Piping and Ducting Components Page 3.3-174 Table 3.3.2-14:Plant Drains Intended Component Type Function Valve body Pressure boundary Flow control Valve body Pressure boundary Valve body Pressure boundary Valve body Pressure boundary Valve body Pressure boundary Valve body . Pressure boundary Valve body* Pressure boundary 3.0 Aging Man.agement Review Results ( \ Material Environment Gray cast iron Wastewater (int) Stainless f.ir -indoor steel* (ext) Stainless Air -in.door (int) stainless Air -outdoo'r steel (ext) Stainless Air -outdoor . steel (ext) Stainless Treated water steel (int) Stainless Wastewater steel (int) Aging Effect Requiring Management Loss of material None None Cracking Loss of material Loss of material Loss of material Aging Management Program Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes SeleCtive Leaching VI I. E5.A-407 3.3.1-72 A None Vll.J.AP..:123 3.3.1-120 A None Vll.J.AP-123 3.3.1-120' A External Surfaces Vll.C1 .AP-209 3.3.1-4 c Monitoring . External Surfaces VllC1 .AP-221 3.3.1-6 c Monitoring Water Chemistry Vlll.B1.SP-87 '3.4.1-16 C, 301 Control -Primary and.Secondary Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A Miscellaneous Piping and Ducting Components Page 3.3-175 Table 3.3.2-15-1 Air Evacuation System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-1 :Air Evacuation System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous* Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-176 Table 3.3.2-15-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Airborne Radioactivity Removal System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-2:Airborne Radioactivity Removal System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-177 Table 3.3.2-15-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Annulus Negative Pressure System Nonsafety-Related Components. Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-3:Annulus Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect . Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment r Management Program Item Item Notes Blower housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in 3.2.1-44 A boundary Miscellaneous Piping and Ducting Components Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Bolting Pressure steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon.steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 A boundary Miscellaneous Piping and Ducting Components Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-178 Waterford Steam Electric Station, Unit 3 License Renewal Application *Technical Information Table Negative Pressure System, Nonsafety-Related Components Affecting Safety-Related Systems . ' Aging Effect Aging* Component Intended Requiring ' Management NUREG-1801 -Table 1 Type Function Material Environment Management Progral'!" Item Item Notes Ducting Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 A boundary Miscellaneoas Piping and Ducting Components 3.0 Aging Mahagement Review Results Page 3.3-179 ( \

Table 3.3.2-15*4

Auxiliary Steam System Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation _Table 3.3.2-15-4:Auxiliary Steam. System, Nonsafety-Related Components Affecting Safety-Re.lated Systems Aging Effect Aging Component Intended Requiring Management . NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-1,25 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of.preload Bolting Integrity Vll.l.AP-1.24 3.3.1-15 B boundary (ext) Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary Control ._ Primary and Secondary
Flow element Pressure Stainless steel Steam (int) Cracking -fatigue TLAA-metal ----H boundary fatigue Flow element Pressure Stainless steel Steam (int) Loss of material Water Chemistry 3.4.1-16 C, 301 boundary Control -Primary ... and Secondary Flow element Pressure Stainless steel Waste water Loss of material .Periodic VI I. E5.AP-278 3.3.1-95 E (int) Surveillance and .. Preventive Maintenance Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-180 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-4:Auxiliary Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Piping Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAG Corrosion Piping Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Waste water Loss of material Periodic VII. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-181 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary fatigue Trap Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Trap Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Trap Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary fatigue Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 c boundary Control -Primary and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Valve body Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-182 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-1,5-4:Auxiliary Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management .. 'NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve.body Pressure Stainless steel Steam (int) Cracking Water Chemistry . Vlll.A.SP-98 3.4.1-11 C, 301 boundary Control -Primary and Secondary Valve body Pressure Stainless steel steam (int)
Cracking -fatigue TLAA.,..,metal ---H boundary
body Pressure Stainless steel Steam (int) Loss of material .Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundar"Y Control -Primary . and Secondary , 3.0 Aging Management Review Results Page 3.3-183 Table 3.3.2-15-5 Boric Acid Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-5: Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item* Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C,301 boundary water (int) Control -Primary and Secondary Sight glass Pressure Glass Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated borated None None Vll.J.AP-52 3.3.1-117 A boundary water (int) Sight glass Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Sight glass Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-184 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-5: Boric Acid Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended *Requiring Management NUREG-1801 Table 1 Type Function Material E.nvironment Management Program Item Item Notes Strainer housing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Strainer housing Pressure Stainless steel
Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel indoor None None Vll.J.AP.:18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 C,.301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry VI l.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-185 Table 3.3.2-15-6 Boron Management System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-6:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting. Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Condenser Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c (Shell) boundary (ext) Condenser Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 (Shell) boundary water (int) Control -Primary and Secondary Cooler housing Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary (ext) Cooler housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Demineralizer Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Demineralizer Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-186 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-G:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Evaporator Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary (ext) Evaporator Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Filter housing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Filter housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Insulated piping Pressure Stainless steel Condensation Cracking External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Insulated piping Pressure Stainless steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Orifice Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Orifice Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 *boundary water Control -Primary and Secondary Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-187 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems : Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Piping Pressure Stainless ste.el Waste water Loss of material . Internal Surfaces.in Vll.ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting ' Components Piping Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Pump casing Pressure Stainless steel Air-indoor None None 3.3.1-120 A boundary (ext) -Pump casing Pressure Stainless steel Treated borated Loss of material
Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Pump casing Pressure Stainless steel Waste water Lqss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary (int) Surveillance and P'reventive Maintenance Sight glass Pressure Glass Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary * (ext) Sight glass Pressure Glass* Treated !;>orated None* None Vll.J.AP-52 3.3.1-117 A .. water (int) Sight glass P*ressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A bouridar}t* (ext) 3.0 Aging Management Review Results Page 3.3-188 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management
Program Item Item Notes Sight glass Pressure Stainless steel Treated borated Loss of material Water-Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Strainer housing Pressure Stainless steel Air-indoor None None . Vll.J.AP-17 3.3.1-120 A boundary (ext) Strainer housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material . Water Chemistry Vll.E1.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Trap Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Trap Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive* Maintenance Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary 3.0 Aging Management Review Results Page 3.3-189 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Boron Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 *Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-190 Table 3.3.2-15-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Chemical and Volume Control System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.1.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Demineralizer Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Demineralizer Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Flex hose Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Flex hose Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Piping Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1.AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-191 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended .. .Requiring Management NUREG-1801 Table 1 Type Function Material
Environment Management Program Item Item Notes Piping.* Pressure Stainlesl) steel Treatec! water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301. boundary (int) Control -Primary and Secondary Piping Pressure Stainless steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) ' . Pump casing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125. *A, 301 boundary water (int) -Primary and Secondary Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81.SP-87 3.4.1-16 C, 301 boundary (int) Control Primary and Secondary Sight glass Pressure Air-indoor None None Vll.J.AP-96 3.3.1-117 A boundary .. (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A bound?ry (int) " Sight glass Pressure Stainless steel Air -indoor . None None Vll.J.AP-18 3.3.1-120 A boundary .. (ext> Sight glass Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81.SP-87 3.4.1-16 C,301 boundary (int) Control -Primary and Secondary Strainer housing Pressure Stainless steel Air-indoor None Norie Vll.J.AP-18 3.3.1-120 A boundary (ext) 3.0 Aging Management Review Results Page 3.3-192 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 c boundary (ext) Tank Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 C, 301 boundary water (int) Control -Primary and Secondary Tank Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-18 3.3.1-120 A boundary (ext) Tubing Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.B1.SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor No11e None Vll.J.AP-18 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry Vll.E1 .AP-79 3.3.1-125 A, 301 boundary water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-193 Waterford Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-7: Chemical and Volume Control System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-194
Table 3.3.2-15-8 Chemical Feed System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cylinder Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Cylinder Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless steel* Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Piping Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting -Components Piping Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-195 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging .component Intended Requiring Management NUREG-1801 Table 1 Type Function Material
Environment Management Program Item Item Notes Pump casing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Pump casing Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c b<;)undary (int) Miscellaneous I Piping and Ducting Components Sight glass Pressure Carbon steel Air-indoor Loss of material. External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Tank Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary -(ext) Tank Pressure Stainless steel Wastewater Loss of material Internal Surfaces ii'! VI I. E5.AP-278 3.3.1-95 c boundary (int) . Miscellaneous ., Piping and Ducting Component!;l. Tubing Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) '. 3.0 Aging Management Review Results Page 3.3-196 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-S:Chemical Feed System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive ' Maintenance Valve body Pressure Stainless steel Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary (ext) Valve body Pressure Stainless steel Waste water
Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-197 Table 3.3.2-15-9 Chilled Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment
Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H bouhdar}t (ext) Flow element Pressure Stainless steel Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary (ext) Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A \ boundary (int) Control -Closed Treated Water Systems Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A . boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-198 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting* Components Piping Pressure Carbon steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None Vll.J.AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-199 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System; Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated.Water Systems Tank Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous*
Piping and Ducting
Components . Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ex.t). Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 c (int) I Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Waste water
Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int)
Surveillance and Preventive Maintenance Valve body Pressure Copper alloy >
Air -indoor None None Vll.J.AP-144 3.3.1-114 A boundary 15% Zn or>8% (ext)* Al 3.0 Aging Management Review Results Page. 3.3-200 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-9: Chilled Water System, Nonsafety-Related ComponentS Affecting Safety-Related Systems Aging Effect Aging Component Intended Requirjng Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Copper .alloy > Condensation Loss of material External Surfaces Vll.F1.AP-109 3.3.1-79 c boundary 15% Zn or> 8% (ext) Monitoring Al -Valve body Pressure Copper alloy > Treated water Loss of material Selective Leaching Vll.C2.AP-43 3.3.1-72 A boundary 15% Zn or> 8% (int) Al Valve body Pressure Copper alloy > Treated water I,.oss of material Water Chemistry Vll.C2.AP-199 3.3.1-46 A boundary 15% Zn or> 8% (int) Control -Closed Al Treated Water Systems 3.0 Aging Management Review Results Page 3.3-201 Table 3.3.2-15-1 O Circulating Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes -Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H boundary_ (ext) Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Sight glass Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Sight glass Pressure Glass Condensation None None Vlll.l.SP-68 3.4.1-55 c boundary (ext) 3.0 Aging Management Review Results Page 3.3-202 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Sight glass Pressure Glass Raw water (int) None None Vll.J.AP-50 3.3.1-117 A boundary Strainer housing Pressure Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Strainer housing Pressure Stainless steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-409 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.C1 .A-408 3.3.1-134 c boundary Miscellaneous ' Piping and Ducting Components Valve body Pressure Copper alloy > Condensation Loss of material External Surfaces Vll.F1.AP-109 3.3.1-79 c boundary 15% Zn or> 8% (ext) Monitoring Al Valve body Pressure Copper alloy > Raw water (int) Loss of material Internal Surfaces in VI I. C 1.A-408 3.3.1-134 c boundary 15% Zn or> 8% Miscellaneous Al Piping and Ducting Components Valve body Pressure Copper alloy > Raw water (int) Loss of material Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary 15% Zn or > 8.% Al Valve body Pressure Gray cast iron Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-203 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-10:Circulating Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Gray cast iron Raw water (int) Loss of material Internal Surfaces in VI I. C 1.A-408 3.3.1-134 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Gray cast iron Raw water (int) Loss of material Selective Leaching Vll.C1 .A-51 3.3.1-72 c boundary 3.0 Aging Management Review Results Page 3.3-204 Table 3.3.2-15-11
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Component Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management .Evaluation Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Condensation Loss of material Bolting Integrity Vll.D.AP-121 3.3.1-12 D boundary (ext) Bolting Pressure Carbon steel Condensation Loss of preload Bolting Integrity ----H boundary (ext) Filter housing Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Filter housing Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Flow element Pressure . Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring Insulated piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.C2.A-405 3.3.1-132 A components boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-205 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.H1 .A-24 3.3.1-80 c boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Plastic Condensation None None --F boundary (ext) Piping Pressure Plastic Treated water None None --F boundary (int) Sight glass Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-81 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Condensation None None Vll.J.AP-97 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) 3.0 Aging Management Review Results Page 3.3-206 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless steel Condensation Loss of material External Surfaces ---G boundary (ext) Monitoring Strainer housing. Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A-boundary (int) Control -Closed Treated Water Systems Tank Pressure Carbon steel Condensation Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Treated water Loss of material Water Chemistry VI I. C2.AP-202 3.3.1-45 A boundary (int) Control -Closed *Treated Water Systems Tubing Pressure Stainless steel Condensation Loss of material External Surfaces ---G boundary (ext) Monitoring Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Condensation Loss of material External Surfaces Vll.1.A-81 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry VI I ,C2.AP-202 3.3.1-45 A boundary (int) Control -Closed . Treated Water Systems 3.0 Aging Management Review Results Page 3.3-207 )

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-11: Component Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging -. Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in VIL E5.,A.P-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless steel Condensation Loss of material External Surfaces ----G boundary (ext) Monitoring Valve body Pressure. Stainless steel Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-208 Table 3.3.2-15-12 Compressed Air System Waterford Steam Electric Station, Unit 3

License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-12:Compressed Air System, Nonsafety-RelatedComponents Affecting Safety-Related Systems Aging Effect Aging. Intended Requiring' Management *NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity VIU.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity VII .l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure. Stainless Condensation Loss of material Compressed Air 3.3.1-56 A boundary steel (int) Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.D.A-80 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 A boundary (int) MonitQring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 . 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary (ext) Piping Pressure Copper alloy Condensation Loss of material Compressed Air Vll.D.AP-240 3.3.1-54 A boundary (int) Monitoring 3.0 Aging Management Review Results Page (

Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information Table 3.3.2-15-12:Compressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tubing Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A bound.ary. (ext) Tubing Pressure Copper alloy Condensation Loss of material Compressed Air Vll.D.AP-240 3.3.1-54 A boundary (int) Monitoring Tubing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 A boundary steel (int) Monitoring Valve body *Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.D.A-80 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 A boundary (int) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary > 15% Zn or (ext) >8%AI Valve body Pressure Copper alloy Waste water Loss of material Internal Surfaces in VI I. E5.AP-272 3.3.1-95 c boundary > 15% Zn or (int) Miscellaneous >8%AI Piping and Ducting Components Valve body Pressure Copper alloy Waste water Loss of material Selective Leaching Vll.E5.A-407 3.3.1-72 c boundary > 15% Zn or (int) >8%AI 3.0 Aging Management Review Results Page 3.3-210 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-12:Gompressed Air System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect *Aging* Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material EnvironmE;!nt Management Program Item Item Notes Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 1-120 A boundary steel* (eXt) Valve body Pressure Stainless Wastewater Loss of material . Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary

steel (iht) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-211 Table 3.3.2-15-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment Atmosphere Purge System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-13:Containment Atmosphere Purge System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting . Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel . Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Concrete (ext) None None Vll.J.AP-282 3.3.1-112 A boundary Heater housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.AP-41 3.3.1-80 A boundary (ext) Monitoring Heater housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-212 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-13:Containment Atmosphere Purge System *. Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Pi:ogram Item Item Notes Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-213 Table 3.3.2-15-14 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Containment Atmosphere Release System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-14:Containment Atmosphere Release System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F3.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material Internal Surfaces in V.A.E-29 3.2.1-44 c boundary Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-214
Table* 3.3.2-15-15 Containment Building Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-15:Containment Building, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801" Table 1 Component Ty.pe Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext)' Bolting Pressure* Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Tubing Pressure Stainless Air-indoor None . None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 c boundary steel (int) Monitoring Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Condensation Loss of material Compressed Air Vll.D.AP-81 3.3.1-56 c bound9_ry steel (int) Monitoring 3.0 Aging Management Review Results Page 3.3-215 (

Table 3.3.2-15-16 Decontamination Facility Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-16:Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) . Filter housing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-216 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-16:Decontamination Facility, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring NUREG-1601 Table 1 Component Type. Function Material Environment Management Program Item Item Notes Pump casing Pressure. Stainless

Waste water Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure
Stainless . Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel *
Strainer housing Pressure Stainless
Waste water
Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting
ComponE;?nts Tank Pressure Stainless* Air:-indoor None None Vll.J.AP-123 3.3.1-120 c boundary " steel (ext) Tank Pressure Stainless Waste water Loss of material Internal.Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (irit) Miscellaneous Piping and Ducting Components / Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of matE;?rial Internal Surfaces in VI I. ES.AP-278 3.3.1-95 . c boundary steel (int) Miscellaneous . }--, Piping and Ducting .. Components 3.0 Aging Management Review Results Page 3.3-217 Table 3.3.2-15-17 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Emergency Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-17:Emergency Diesel Generator System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Condensation Loss of material Compressed Air Vll.D.A-26 3.3.1-55 c boundary (int) Monitoring Piping Pressure Carbon steel Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-127 3.3.1-97 A, 302 boundary Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-218 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-17:Emergency Diesel Generator System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Lube oil (int) Loss of material Oil Analysis Vll.H2.AP-138 3.3.1-100 A, 302 boundary steel **. Valve body Pressure Stainless Treated water Loss of material . Water Chemistry Vll.C2.A-52 . 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systeml) Valve body Pressure Stainless ** Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous . ' Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-219 Table 3.3.2-15-18 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fuel Handling Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-18:Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-.1801 Table 1 Component Type Function Materi(ll Environment Management Program Item Item Notes Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Blower housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring *-Piping Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-220 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-18:Fuel Handling Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting -Components 3.0 Aging Management Review Results
Page 3.3-221 Table 3.3.2-15-19 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fuel Pool Cooling and Purification System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-19:Fuel Pool Cooling and Purification System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated borated Loss of material Water Chemistry VI l.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-222 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-19:Fuel Pool Cooling and Purification System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 *Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A bc;iundary steel (ext) Pump casing Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Treated borated Loss of material Water Chemistry VI I .A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-223 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-19:Fuel Pool Cooling and Purification System,* Nonsafety*Related Components Affecting Safety-Related Systems . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A3.AP-79 3.3.1-125 A, 301 boundary steel water (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-224 Table 3.3.2-15-20 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Gaseous Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Sumrriary of Aging Management Evaluation Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function *Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Lo_ss of preload Bolting Integrity Vll.1.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Stainless . Air -indoor None None Vll.J.AP-17 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water
Syster:ris Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting : Coriponents Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Gas (int) None None* Vll.J.AP-6 3.3.1-121 A boundary 3.0 Aging Management Review Results Page 3.3-225 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry VI I. C2.AP-202 3.3.1-45 c boundary (int) Control -Closed Treated Water Systems Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Separator Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Separator Pressure Stainless Gas (int) None None Vll.J.AP-22 3.3.1-120 A boundary steel Sight glass Pressure Glass Air-indoor None None Vll.J.AP-48 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Sight glass Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Sight glass Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-226 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-20:Gaseous Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Agir:1g Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Carbon steel Air -indoor. Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Mon'itoring Trap Pressure Carbon steel Waste water of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Trap Pressure Stainless Waste water . Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Gomponents Valve body Pressure Stainless Air-indoor None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Gas (int) . None None 3.3.1-120 A boundary steel Valve body Pressure Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel . (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-227 Table 3.3.2-15-21 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information H.ot Macbine Shop and Decon Facility Vent System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-21:Hot Machine Shop & Decon Vent System, Nonsafety-Related Components Affecting_Safety-Related Systems Aging Effect Aging Intended . Requiring Management
NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting *Pressure Carbon steel Air --indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air --indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Riping Pressure Carbon steel . Air..: indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting pomponents Valve body Pressure Air --indoor None None Vll.J .. AP-123 3.3.1-120 A boundary steel <ext> *Valve body Pressure Stainless Waste water Loss of materii;il Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components* 3.0 Aging Management Review Results Page 3.3-228 Table 3.3.2-15-22 Leak Rate Testing System Waterford Steam*Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-22:Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item* Item Notes Bolting Pressure Carbon Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vll.l.AP-126 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vll.l.AP-263 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces
Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring .. Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary , (int) Miscellaneous Piping* and Ducting Components Piping Pressure Copper alloy Air -indoor (int) None None Vll.J.AP-144 3.3.1-114 A boundary 3.0 Aging Management Review Results Page 3.3-229 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-22:Leak Rate Testing System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Copper alloy Air -outdoor Loss of material External Surfaces Vll.l.AP-159 3.3.1-81 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vll.l.A-78 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-230 Table 3.3.2-15-23 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Liquid Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 . B boundary steel (ext) Condenser (Shell) Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Condenser (Shell) Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance
Cooler housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Demineralizer Pressure Stainless Air -indoor
None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Demineralizer Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-231 Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management Syste*m, Nonsafety-Related Components Affecting Safety-Related Systems -Aging Effect Aging Intended Requiring Management NUREG-1801 Table1 Component Type . Function* Material Environment Management Program Item Item Notes Evaporator Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Evaporator Pressure Stainless, Waste water Loss of material Periodic Vll.E5.AP-275 3.3.1-95 E boundary steel (int) Surveillance and Preventive* .. Maintenance Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary . steel (int) Miscellaneous Piping and Ducting ** Components Orifice Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel. (ext) Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Garbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281. 3.3.1-91 A ** boundi!iry (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None VILJ.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-232 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Systems Aging Effect Aging Intended* Requiring Management NUREG-1801 . Table 1 Component Type Function Material Environment " Management Program Item Item Notes Piping Pressure Stainless VV?Ste water Loss of material Internal Surfaces in 3.3.1-95 A boundary steel (int) Miscellaneo'us Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance .and Preventive Maintenance . Pump casing . *Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in VII. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous .. Piping and Ducting
Components Sight glass Pressure Glass Air -indoor
None None VI l.J .AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Waste water None None Vll.J.AP-277 3.3.1-119 A boundary (int) Sight glass Pressure
Stainless . Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) .. Sight glass Pressure Stainless Waste* water Loss of material Internal Surfaces in VII. 3.3.1-95 A boundary steel (int) .. Miscellaneous Pipi.ng and Ducting Components Strainer housing Pressure Stainless Air. -indoor None. None Vfl.J.AP-123 3.3.1-120 A boundary steel (ext) ' . 3.0 Aging Management Review Results Page 3.3-233 Waterford Steam Electric Station, Unit 3 .License Renewal Application Technical Information Table 3.3.2-15-23:Liquid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components. Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-234 Table 3.3.2-15-24 Nitrogen System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-24:Nitrogen System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Gas (int) None None Vll.J.AP-22 3.3.1-120 A boundary steel Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Carbon steel Air -indoor . Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and. Ducting Components 3.0 Aging Management Review Results Page 3.3-235 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type
Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78. A boundary. (ext) Monitoring Trap Pressure Carbon steel Waste water Loss of material Internal Surfaces in VII.. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of materiar External Surfaces Vll.l.A-77 3,3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary ,, Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c *boundary Miscellaneous Piping and Ducting 3.0 Aging Management Review Results Page 3.3-236 Table 3.3.2-15-25 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Post Accident Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Chiller housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 c boundary (ext) Monitoring Chiller housing Pressure Carbon steel Waste water Loss of material Internal Surfaces in VII. E5.AP-281 3.3.1-91 c boundary . (int) Miscellaneous Piping and Ducting Components Heat exchanger Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c (shell) boundary steel (ext) Heat exchanger Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c (shell) boundary steel (int) Control -Closed Treated Water Systems Orifice Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-237 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Orifice Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.ES.AP-278 \ 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping . Pressure Stainless Air -indoor , None None Vll.J.AP-123 3.3.1..:120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Wastewater Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components s.trainer housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Wastewater Loss of material lnternal*Surfaces in VILE5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainles's Air:_ indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-238 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-25:Post Accident Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Environment Management Program Item Item Notes Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-239 Table 3.3.2-15-26 Potable Water System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems
Summary of Aging Management Evaluation Table 3.3.2-15-26:Potable Water System, Nonsafety-Related Components Affecting Safety-Related Systems ' . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel water (int) Loss of material Internal Surfaces in VI I. c boundary Miscellaneous Piping and Ducting Components Pump casing Pressure Copper alloy Air-indoor None None* VILJ.AP-144 3.3.1-114 A boundary > 15% Zn or (ext) >8%AI '. Pump casing Pressure Copper alloy Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-271 3.3.1-93 c boundary > 15% Zn or Miscellaneous ?' 8% Al Piping and Ducting Components . Pump casing Pressure Copper alloy Raw water (int) Loss Of mc:iterial Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary > 15% Zn or >8%AI 3'.0 Aging Management Review Results Page 3.3-240 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-26:Potable Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Tank Pressure Carbon steel Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-270 3.3.1-88 c boundary Miscellaneous Piping and Ducting Components Valve body Pressure Copper alloy Air-indoor None None Vll.J.AP-144 3.3.1-114 A boundary > 15% Zri or (ext) >8%AI Valve body Pressure Copper alloy Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-271 3.3.1-93 c boundary > 15% Zn or Miscellaneous >8%AI Piping and Ducting Components Valve body Pressure Copper alloy Raw water (int) Loss of material Selective Leaching Vll.C1.A-47 3.3.1-72 c boundary > 15% Zn or >8%AI Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Raw water (int) Loss of material Internal Surfaces in Vll.E5.AP-270 3.3.1-88 c boundary steel Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-241 Table 3.3.2-15-27 Primary Makeup System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-27:Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material
Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) , Insulated piping Pressure Stainless Condensation Cracking External Surfaces Vll.l.A-405 3.3.1-132 A components boundary steel (ext) Monitoring Insulated piping Pressure Stainless Condensation Loss of material External Surfaces Vll.l.A-405 3.3.1-132 A components boundary steel (ext) Monitoring Piping Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel (int) Control -Primary and Secondary Piping Pressure *Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-242 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-27:Primary Makeup System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-243 Table 3.3.2-15-28 Primary Sampling System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation ' ' Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Systems Aging Effect Aging Intended '* Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure *carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-102 3.3.1-9 A boundary (ext) Corrosion Bolting Pressure Carbon steel Air-indoor Loss of preload
Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Flex hose Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Flex hose Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Flex hose Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water> 140°F Control -Primary (int) and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material Boric Acid Vll.l.A-79 3.3.1-9 A (shell) boundary (ext) Corrosion Heat exchanger . Pressure Carbon steel Air-indoor Loss of.material External Surfaces Vll.l.A-77 3.3.1-78 A (shell) boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-244
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-189 3.3.1-46 c (shell} boundary (int) Control -Closed Treated Water Systems Piping. Pressure steel Air .... indoor Loss of material Boric Acid Vll.l.A-79 3.3.1-9 A . boundary (ext) Corrosion Piping Pressure Carbon steel Air*-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) -* Monitoring Piping Pressure Carbon steel Gas (int) None None Vll.J.AP-6 3.3.1-121 A boundary Piping Pressure Stainless Air-indoor None* None VI l.J .AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Treated borated Cracking -fatigue TLAA-metal Vll.E1.A-57 3.3.1-2 c boundary steel water > 140°F fatigue (int) *Piping Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary* steel water > 140°F Control -Primary (int) and Secondary Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-245 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping anq Ducting Components Trap Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Trap Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water (int) Control -Primary and Secondary Trap Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary Trap Pressure Stainless Treated borated Cracking -fatigue TLAA-metal VII. E 1.A-57 3.3.1-2 c boundary steel water > 140°F fatigue (int) Trap Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air -i'ndoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water> 140°F Control -Primary (int) and Secondary 3.0 Aging Management Review Results Page 3.3-246 Waterford Steam Electric Station, License Renewal Application Technical Information Table 3.3.2-15-28:Primary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Stainless Treated borated Cracking -fatigue TLAA-metal Vll.E1.A-57 3.3.1-2 c . boundary steel water > 140°F fatigue (int) Valve body Pressure Stainless Treated borated Loss of material Water Chemistry Vll.A2.AP-79 3.3.1-125 . C, 301
boundary steel water > 140°F Control-Primary (int) and Secondary Valve body Pressure Stainless Waste water Loss of material lpternal Surfaces in Vll.ES.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Vessel Pressure Stainless Air -indoor None None Vll.J.AP-17 * . 3.3.1-120 A boundary steel (ext) Vessel Pressure Stainless Treated borated Cracking Water Chemistry Vll.E1.A-103 3.3.1-124 c boundary steel water > 140°F Control -Primary -(int) and Secondary Vessel Pressure Stainless Treated borated Cracking -fatigue TLAA -metal Vll.E1.A-57 3.3.1-2 c boundary steel water> 140°F fatigue (int) -Vessel Pressure Stainless Treated borated Loss of material Water Chemistry. Vll.A2.AP-79 3.3.1-125 C, 301 boundary steel water> 140°F Control -Primary (int) and Secondary . 3.0 Aging Management Review Results
Page 3.3-247 Table 3.3.2-15-29 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Radiation Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Filter housing Pressure Aluminum Air-indoor None None Vll.J.AP-135 3.3.1-113 A boundary (ext) Filter housing Pressure Aluminum Wastewater Loss of material Internal Surfaces in ----G boundary (int) Miscellaneous Piping and Ducting Components Filter housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Filter housing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c r boundary steel (int) Miscellaneous Piping and Ducting Components Filter housing Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-248 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Heat exchanger Pressure Carbon steel Air -indoor . Loss of material External Surfaces Vll.l.A-77 3.3.1-78 c (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c (shell) bo1,mdary (int) . MisceUaneous Piping and Ducting Components Piping Pressure *Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary* steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and . -Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Trap Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-249 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-29:Radiation Monitoring System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Env.ironment Management Program Item Item Notes Trap Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.:?.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) , Tubing Pressure Stainless Air....:. indoor (int) None None Vll.J.AP-123 3.3.1-120 A boundary steel Valve body Pressure Stainless Air-indoor None None : Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Air -indoor (int) None None VI l.J .AP-123 3.3.1-120 A boundary steel Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure* Stainless Waste water Loss of material Periodic 3.3.1-95 E boundary steel *(int) Surveillance and Preventive .. ' Maintenance 3.0 Aging Management Review Results Page 3.3-250 Table 3.3.2-15-30 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Auxiliary Building HVAC System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table Auxiliary Building HVAC System, Affecting Safety-Related Systems Aging Effect
Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoc;>r Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B *boundary (ext) Damper housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Damper housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Ducting. Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A . boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 c boundary (int) Miscellaneous Piping 1?ucting Components Valve body Pressure Garb.on steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-251 ----

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-30:Reactor Auxiliary Building HVAC System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous* Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-252 Table 3.3.2-15-31 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Cavity Cooling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Ag.ing Management Evaluation Table 3.3.2-15-31 :Reactor Cavity Cooling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Blower housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1-78 A boundary (ext) Monitoring Blower housing Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 B boundary (ext) Ducting Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.F2.A-10 3.3.1'-78 A boundary (ext) Monitoring Ducting Pressure Carbon steel Air -indoor (int) Loss of material External Surfaces V.A.E-29 3.2.1-44 E boundary Monitoring 3.0 Aging Management Review Results Pa*ge 3.3-253 Table 3.3.2-15-32 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Resin Waste Management System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management

Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Stainless Air -indoor
None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Wastewater Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Pump casing Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-254 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Intended Component Type Function Pump casing Pressure boundary Sight glass Pressure . boundary Sight glass Pressure boundary Sight glass Pressure boundary Sight glass Pressure boundary Strainer housing Pressure boundary Strainer housing
Pressure boundary Tank Pressure . boundary Tank Pressure boundary 3.0 Aging Management Review Results *, *. Material Environment Stainless Waste water steel (int) Glass Air-indoor (ext) Glass Waste water *(int) Stainless Air-indoor steel (ext) Stainless Wastewater steel (int) I Stainless Air-indoor steel (ext) .. Stainless Waste water steel (int) Stainless Air-indoor steel (ext) Stainless Waste water steel (int) Aging Effect Aging Requiring Management NUREG-1801 Table 1 Management Program Item Item Notes
Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-48 3.3.1-117 A None None Vll.J.AP-277 3.3.1-119 A None None Vll.J.AP-17 3.3.1-120 A Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-17 3.3.1-120 A Loss of material Internal Surfaces in 3.3.1-95 c Miscellaneous Piping and Ducting Components None None Vll.J.AP-123 3.3.1-120 c Loss of material Internal Surfaces in VI I. ES.AP-278 3.3.1-95 c Miscellaneous Piping and Ducting Components Page 3.3-255 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-32:Resin Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-256 Table 3.3.2-15-33 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Secondary Sampling System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Cooler housing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Cooler housing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Orifice Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Orifice Pressure Stainless Treated water Cracking Water Chemistry Vlll.B1 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Orifice Pressure Stainless Treated water Loss of material Water Chemistry Vlll.B1 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.3-257
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Air -indoor (int) Loss of material Periodic V.A.E-29 3.2.1-44 E boundary Surveillance and Preventive .. Ma,intenance Piping Pressure Carbon steel Waste water Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E qoundary {Int) Surveillance arid Preventive Maintenance .. Piping Pressure Stainless Air-indoor None None VII.J.AP-17 3.3.1-'120 A ' boundary steel (ext) Piping Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary steel Control -Prin:iary and Secondary Piping Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary steel fatigue Piping Pressure Stainless Steam (int) Loss of material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundary steel Control -Primary . and Secondary Piping Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Piping Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 c;301 boundary steel > 140°F (int) Control -.Primary and Secondary 3.0 Aging Management Review Results Page 3.3-258 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Piping Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Pump casing Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Pump casing Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Pump casing Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Strainer housing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Strainer housing Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Strainer housing Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-259 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related . Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Tank Pressure Stainless Treated water Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C,301 boundary steel > 140°F (int) Control -Primary and Secondary Tank Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 .SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Prim*ary and Secondary Tubing Pressure Stainless Air-indoor None None Vll.J.AP-17 3.3.1-120 A boundary steel (ext) Tubing Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C, 301 boundary steel Control -Primary and Secondary Tubing Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary steel fatigue Tubing Pressure Stainless Steam (int) . Loss of material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 *boundary steel Control -Primary and Secondary Valve body Pressure Stainless Air-indoor None None Vll.J .. AP-17 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Steam (int) Cracking Water Chemistry Vlll.A.SP-98 3.4.1-11 C,301 . boundary steel Control -Primary and Secondary Valve body Pressure Stainless Steam (int) Cracking -fatigue TLAA-metal ----H boundary. steel fatigue Valve body Pressure Stainless Steam (int) Loss of. material Water Chemistry Vlll.A.SP-155 3.4.1-16 C, 301 boundary steel Control -Primary .. and Secondary 3.0 Aging Management Review Results Page 3.3-260 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-33:Secondary Sampling System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management . Program Item Item Notes Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 c boundary steel (int) Control -Closed Treated Water Systems Valve body Pressure Stainless Treated water *Cracking Water Chemistry Vlll.81 .SP-88 3.4.1-11 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary Valve body Pressure Stainless Treated water Loss of material Water Chemistry Vlll.81 ,SP-87 3.4.1-16 C, 301 boundary steel > 140°F (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.3-261 Table 3.3.2-15-34 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Solid Waste Management System N9nsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-34: Solid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Accumulator Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Accumulator Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Bolting Pressure Stainless Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary steel (ext) Piping Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillarice and Preventive Maintenance Pump casing Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-262 Waterford Steam Electric Station, Unit 3 -License Renewal Application Technical Information Table 3.3.2-15-34: Solid Waste Management System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Pump casing Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Tank Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 c boundary steel (ext) Tank Pressure Stainless Waste water Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance Valve body Pressure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in Vll.E5.AP-278 3.3.1-95 c boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Stainless Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary steel (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.3-263 Table 3.3.2-15-35 Surrip Pump System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summ.ary of Aging Management Evaluation Table 3.3.2-15-3S:Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect . Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -,indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (eXt) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 A boundary (int) Miscellaneous Piping and Ducting Components Piping Pressure Stainless Air-indoor None None Vll.J.AP-'123 3.3.1-120 A boundary steel (ext) Piping Pressure Stainless
Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure
Stainless Air-indoor None Vll.J.AP-123 3:3.1-120 A boundary steel (ext) 3.0 Aging Management Review Results Page 3.3-264 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-35:Sump Pump System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring* Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Strainer housing Pressure Stainless Waste water . . Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Air-indoor Loss of material . External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Wastewater Loss of material* Internal Surfaces in Vll.E5.AP-281 3.3.1-91 A boundary (int) Miscellaneous Piping and Ducting Components Valve body Pres$ure Stainless Air-indoor None None Vll.J.AP-123 3.3.1-120 A boundary steel (ext) Valve body Pressure Stainless Waste water Loss of material Internal Surfaces in VI I. E5.AP-278 3.3.1-95 A boundary steel (int) Miscellaneous Piping and Ducting Components 3.0 Aging Management Review Results Page 3.3-265 Table 3.3.2-15-36 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Turbine Building Cooling Water System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.3.2-15-36:Turbine Building Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vll.l.AP-125 3.3.1-12 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vll.l.AP-124 3.3.1-15 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.1.A-77 3.3.1-78 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Sight glass Pressure Glass Air-indoor None None Vll.J.AP-14 3.3.1-117 A boundary (ext) Sight glass Pressure Glass Treated water None None Vll.J.AP-166 3.3.1-117 A boundary (int) Sight glass Pressure Stainless Air-indoor None None VI l.J .AP-123 3.3.1-120 A boundary steel (ext) Sight glass Pressure Stainless Treated water Loss of material Water Chemistry Vll.C2.A-52 3.3.1-49 A boundary steel (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-266 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.3.2-15-36:Turbine Building Cooling Water System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Intended Requiring Management NUREG-1801 Table 1 Component Type Function Material Environment Management Program Item Item *Notes Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary . (ext) Monitoring Tank Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vll.l.A-77 3.3.1-78 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vll.C2.AP-202 3.3.1-45 A boundary (int) Control -Closed Treated Water Systems 3.0 Aging Management Review Results Page 3.3-267 3.4 STEAM AND POWER CONVERSION SYSTEMS 3.4.1 Introduction Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of the aging management reviews for components in the steam and power conversion systems that are subject to aging management review. The following systems are addressed in this section (the system descriptions are available in the referenced section).
Condensate Makeup and Storage (Section 2.3.4.1)
Emergency Feedwater (Section 2.3.4.2)
Main Feedwater (Section 2.3.4.3)
Main Steam (Section 2.3.4.4)
Steam and Power Conversion Systems in Scope for 1 O CFR 54.4(a)(2) (Section 2.3.4.5) Table 3.4.1, Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for the steam and power conversion system component group. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program evaluations in Appendix B. 3.4.2 Results The following system tables summarize the results of aging management reviews and the NUREG-1801 comparison for the condensate storage system.
Table 3.4.2-1 Condensate Makeup and Storage System-Summary of Aging Management Evaluation
Table 3.4.2-2 Emergency Feedwater System-Summary of Aging Management Evaluation
Table 3.4.2-3 Main Feedwater System-Summary of Aging Management E'valuation
Table *3.4.2-4 Main Steam System-Summary of Aging Management Evaluation *
Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) Table 3.4.2-5-1 Slowdown System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Management Evaluation Table 3.4.2-5-2 Condensate System, Nonsafety-Related Components Affecting Related Systems__;_Summary of Aging Management Evaluation 3.0 Aging Management Review Results Page 3.4-1 Waterford Steam Electric Station, Unit 3 Licen_se Renewal Application -Technical Information
Table 3.4.2-5-3 Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation *
Table 3.4.2-5-4 Emergency Feedwater System, Nonsafety-Related Components Affecting Safety-Related Systems;_:_Summary of Aging Management Evaluation
Table 3.4.2-5-5 Feedwater System, Nonsafety-Related Components Affecting Related.Systems-Summary of Aging Management Evaluation
Table 3.4.2-5-6 Main steam System, Nonsafety-Related Components Affecting Related Systems-Summary of Aging Managem*ent Evaluation 3.4.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging effects requiring management, and aging management programs for the steam and power conversion systems. Programs are described in Appendix B. Further details are provided in the system tables. 3.4.2.1.1 Condensate Makeup and Storage Materials Condensate makeup and storage system components are constructed of the following materials. *
Carbon steel
stainless steel Environments Condensate makeup and storage system components are exposed to the following environments. *
Air -indoor
Treated water Aging Effects Requiring Management The following aging effects associated with the condensate makeup and storage system require management.
Loss of material 3.0 Aging Management Review Results Page 3.4-2
Loss of preload Aging Management Programs Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the aging effects for the condensate makeup and storage system components. * * *
Bolting Integrity External Surfaces 'Monitoring One-Time Inspection . Water Chemistry Control -Primary and Secondary 3.4.2.1.2 Emergency Feedwater Materials Emergency feedwater system components are constructed of the following materi.als.
Carbon steel * *
Gray cast iron High steel Stainless steel Environments Emergency feedwater system components are exposed to the following environments. *
Air -indoor
Air -outdoor
Lube oil
Treated water Aging Effects Requiring Management The following aging effects associated with the emergency feedwater system require management. * *
Cracking J..oss of material Loss of preload Reduction of heat transfer 3.0 Aging Management Review Results
Page 3.4-3 Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
The following aging management programs man.age aging for the emergency feedwater system components. * * * *
Bolting Integrity External *Surfaces Monitoring Oil Analysis One-Time Inspection Water Chemistry Control -Primary and Secondary 3.4.2.1.3 Main Feedwater Materials Main feedwater system components are constructed of the following materials.
Carbon steel
High strength .steel
Stainless steel Environments Main feedwater system components are exposed to the following environments.
Air -indoor
Air -outdoor
Steam
Treated water
Treated water> 140°F Aging Effects Requiring Management The following aging effects associated with the main feedwater system require management. * * * *
Cracking Cracking -fatigue Loss of material Loss .of material -FAC Loss of preload 3.0 Aging Management Review Results Page 3.4-4

./ Waterford Steam Electric Station, Unit 3 Ucense Renewal Application Technical Information Aging Management Programs The following aging management programs manage the aging effects for the main feedwater system components. * * * *

Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion One-Time Inspection Water Chemistry Control -Primary and Secondary 3.4.2.1.4 Main Steam Materials Main steam system components are constructed of the following materials.
Carbon steel * *CASS
Glass
Gray cast iron
High strength steel
Stainless steel Environments Main steam system components are exposed to the following environments.
Air-indoor
Air -outdoor
Condensation
Lube oil
Steam
Treated water Aging Effects Requiring Management The following aging effects associated with the main steam system require management. * * *
Cracking Cracking -fatigue Loss of material Loss of material -erosion 3.0 Aging Management Review Results Page
Loss of material -FAC
Loss of preload Aging Management Programs Waterford Steam Electric Station, Unit 3 License Renewal Application
Technical Information The following aging management programs manage the aging effects for the main steam system components. .* * * .. * *
Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Oil Analysis . One-Time Inspection Selective Leaching Water Chemistry Control -Primary and Secondary 3.4.2.1.5 Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2) The following lists encompass materials, environments, aging effects requiring management, and aging management programs for the series 3.4.2-5-x tables. *Materials Nonsafety-related components affecting safety-related systems .are constructed of the following materials.
Carbon steel
Glass
Stainless steel Environments Nonsafety-related components affecting safety-:related systems are exposed to the. following environments.
Air-indoor
Air -outdoor
Condensation
Steam
Treated water
Wastewater 3.0 Aging Management Review Results Page 3.4-6 \

Waterford Steam Electric Station, Unit 3 License Renewal Application TechnJcal Information

Aging Effects Requiring Management The following aging effects associated with nonsafety-related components affecting safety-related systems require management.
Cracking
Craqking -fatigue
Loss of material
Loss of material -erosion
Loss of material -*FAG
Loss of preload Aging Programs The following aging management programs manage the effects of aging on nonsafety-related components affecting. safety-related systems. * * * * * *
Bolting Integrity External Surfaces Monitoring Flow-Accelerated Corrosion Internal Surfaces in Miscellaneous Piping and Ducting Components One-Time Inspection . Periodic Surveillance and Preventive Maintenance Water Chemistry Control -Primary and Secondary 3.4.2.2 Further Evaluation of Aging Management as Recommended hy NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.4.2.2 of NUREG-1800. The .following sections are numbered in accordance with the discussions in NUREG 1800 and explain the approach to those areas requiring further evaluation. Programs are described in Appendix B. 3.4.2.2.1 Cumulative Fatigue Damage Where identified as an aging effect requiring management, the analysis of fatigue is a TLAA as defined in 1 O CFR 54.3. TLAAs are evaluated in accordance with 1 O CFR' 54.21 (c). Evaluation of this TLAA is addressed in Section 4.3. 3.4.2.2.2 Cracking due to Stress Corrosion Cracking CSCC) Cracking due to stress corrosion cracking could occur for stainless steel piping, pipfng components, piping elements and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may occur. Consistent with 3.0 Aging Management Review Results Page 3.4-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801, cracking of stainless steel components exposed to outdoor air, including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.4.2.2.3 Loss of Material Due to Pitting and Crevice Corrosion Loss of material due to pitting and crevice corrosion could occur for stainless steel piping, piping components, piping elements, and tanks exposed to outdoor air, including air which has recently been introduced into buildings, such as near intake vents. WF3 is located near other industrial facilities, including chemical manufacturers. Chloride contamination of components exposed to outdoor air may* occur. Consistent with NUREG-1801, loss of material for stainless steel components exposed to outdoor including indoor components accessible to outdoor air, is identified as an aging effect requiring management and is managed by the External Surfaces Monitoring Program. 3.4.2.2.4 Qualitv Assurance for Aging Management of Nonsafety-Related Components See Appendix B Section_B.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.4.2.2.5 Ongoing Review of Operating Experience See Appendix B Section B.0.4 for discussion* of the WF3. operating experience review . . . programs. 3.4.2.2.6 Loss of Material due to Recurring Internal Corrosion
A review of 10 years of plant operating experience identified no conditions* of recurring internal corrosion (RIC) as defined in LR-ISG 2012-02, Section A, in the piping * ,*,components of the steam and *power conversion systems in the scope oflicerise . renewal'. 3.4.2.3 Time-Limited Aging Analysis The only time-limited aging for the steam and power conversion systems components is metal fatigue. This is evaluated in Section 4.3. 3.4.3 Conclusion The steam and power conversion system components that are subject to aging management review have been identified in accordance with the requirements of 1 O CFR 54.21. The aging management programs selected to manage the effects of aging on and power conversion system components are identified in Secti.on 3.4.2.1 and in following tables. A description of these aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects wilr be managed for the period of extended operation. . . 3.0 Aging Management Review Results Page 3.4-8 Waterford Stearn Electric Station, Unit 3 License Renewal Application Technical Information Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the steam and power conversion system components will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.4-9 Table 3.4.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of NUREG-1801 . Table 3.4.1: Steam and Power Conversion Systems Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion 3.4.1-1 Steel piping, piping Cumulative fatigue Fatigue is a time-limited Yes, TLAA Fatigue is a TLAA. components, and piping damage due to aging analysis (TLAA) to be elements exposed to fatigue evaluated for the period of See Section 3.4.2.2.1. steam or treated water extended operation: See the SRP, Section 4.3 "Metal Fatigue," for acceptable methods for meeting the requirements of 10 CFR 54.21(c)(1). 3.4.1-2 Stainless steel piping, Cracking.due to Chapter Xl.M36, "External Yes, Consistent with NUREG-1801. piping components, and stress corrosion Surfaces Monitoring of environmental Cracking of stainless steel piping elements; tanks cracking Mechanical Components" conditions need to components exposed to outdoor air is exposed to air -outdoor be evaluated managed .by the External Surfaces Monitoring Program. See Section 3.4.2.2.2. 3.4.1-3 Stainless steel piping, Loss of material due Chapter Xl.M36, "External Yes, Consistent with NUREG-1801. Loss of piping components, and to pitting and crevice . S.urfaces Monitoring of environmental material for stainless steel piping elements; tanks corrosion Mechanical Components" conditions need to components exposed to outdoor air is exposed to air -outdoor be evaluated managed by the External Surfaces Monitoring Program. See Section 3.4.2.2.3. 3.0 Aging Management Review Results Page 3.4-10 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-4 Steel external surfaces, Loss of material due bolting exposed to air to boric acid with borated water corrosion leakage 3.4.1-5 Steel piping, piping Wall thinning due to components, and piping flow-accelerated elements exposed to corrosion steam, treated water 3.4.1-6 Steel, stainless steel Loss of preload bolting exposed to soil 3.4.1-7 High-strength steel Cracking due to closure bolting exposed cyclic loading, stress to air with steam or corrosion cracking water leakage 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M10, "Boric No Acid Corrosion" Chapter XI.Mt?, "Flow-No Accelerated Corrosion" -Chapter Xl.M18, "Bolting No Integrity" Chapter Xl.M18, "Bolting No Integrity" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no external steel surfaces exposed to borated water in the steam and power conversion systems. Consistent with NUREG-1801. Loss of material due to flow accelerated corrosion in steel components exposed to steam or treated water is managed by the Flow-Accelerated Corrosion Program. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Cracking of high strength steel bolting exposed to air with steam or water leakage is managed by the Bolting Integrity Program. Page 3.4-11 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/_ Aging Management Number Component Mechanism Programs 3.4.1-8 Steel; stainless steel Loss of material due Chapter Xl.M18, "Bolting bolting, closure bolting to general (steel Integrity" exposed to air -outdoor only), pitting, and (external}, air-indoor, crevice corrosion uncontrolled (external) 3.4.1-9 Steel closure bolting Loss of material due Chapter Xl.M18, "Bolting exposed to air with to general corrosion Integrity" steam or water leakage .. 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel and stainless steel closure bolting exposed to indoor and outdoor air is managed by the Bolting Integrity Program. Loss of material is not an aging effect for stainless steel closure bolting in indoor air unless exposed to prolonged leakage (an event driven condition). Nevertheless, t_he Bolting Integrity Program also applies to stainless steel bolting exposed to indoor air. As stated in Item 3.4.1-8, loss of material of steel bolting exposed to air in the steam and power conversion systems is managed by the Bolting
Integrity Program. However, steam or water leakage is not considered as a separate aspect of the indoor air envfronment. Page 3.4-12
Table 3.4.1 : Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-10 Copper alloy, nickel Loss of preload due alloy, steel; stainless to thermal effects, steel, steel; stainless gasket creep, and
steel bolting, closure self-loosening bolting exposed to any environment, air -outdoor (external), air -indoor, uncontrolled (external) 3.4.1-11 Stainless steel piping, Cracking due to piping components, and stress corrosion piping elements, tanks, cracking heat exchanger components exposed to steam, treated water >60°C (>140°F) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M18, "Bolting No . Integrity" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Tinie Inspection" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of preload for steel and stainless steel bolting is managed by the Bolting Integrity Program. Copper alloy and nickel alloy bolting is not included in the scope of license renewal for steam and power conversion systems. Consistent with NUREG-1801. Cracking of stainless steel components exposed to steam or treated water >60°C (>140°F) is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage cracking. Page 3.4-13 Table 3.4.1 : Steam and* Power Conversion Systems Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.4.1-12 Steel; stainless steel Loss of material due Chapter Xl.M2, "Water tanks exposed to treated to general (steel Chemistry," and Chapter water only), pitting, and Xl.M32, "One-Time crevice corrosion Inspection" " .. 3.4.1-13 Steel piping, piping Loss of material due Chapter Xl.M2, "Water c.omponents, and piping to general, pitting, Ch,emistry," and Chapter elements exposed to and crevice corrosion Xl.M32, "One-Time treated water Inspection" 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel tanks exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no stainless steel tanks exposed to treated water in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Loss of material for steel components exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effeGtiveness of the water chemistry control program to manage loss of material. Page 3.4-14 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-14 Steel piping, piping Loss of material due components, and piping to general, pitting, elements, PWR heat and crevice corrosion exchanger components exposed to steam, treated water 3.4.1-15 Steel heat exchanger Loss of material due components exposed to to general, pitting, treated water crevice, and galvanic corrosion 3.4.1-16 Copper alloy, stainless Loss of material due steel, nickel alloy, to pitting and crevice aluminum piping, piping corrosion components, and piping elements, heat exchanger components and tubes, PWR heat exchanger components exposed to treated water, steam 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter Xl.M32, "One-Time Inspection" -. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for steel components exposed to steam or treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no steel condensate system . heat exchanger components exposed to treated water in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Loss of material for stainless steel components exposed to steam or treated water is managed by the Water Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no aluminum, copper alloy or nickel alloy components in the steam and power conversion systems in the scope of license renewal. Page 3.4-15 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component* Mechanism 3.4.1-17 Copper alloy heat Reduction of heat exchanger tubes transfer due to exposed to treated water fouling 3.4.1-18 Copper alloy, stainless Reduction of heat steel heat exchanger transfer due to tubes exposed to treated fouling
water 3.4.1-19 Stainless steel, steel Loss of material due
heat exchanger to general, pitting, components exposed to crevice, galvanic, raw water and microbiologically influenced corrosion; fouling that leads to corrosion 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M2, "Water No Chemistry,'.' and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M2, "Water No Chemistry," and Chapter -Xl.M32, "One-Time Inspection" .. Chapter Xl.M20, "Open-No Cycle Cooling Water System" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to treated water is managed by the Water Chemistry Control -Primary and Secondary Program. The One-Time Inspection Program will verify the effectiveness of the water chemistry control program to manage loss of material. There are no copper alloy heat exchanger tubes with an intended function of heat transfer in the steam and power conversion systems in the scope of license renewal. There are no steel or stainless steel heat exchanger components exposed to raw water in the steam and power conversion in the scope of license renewal. Page 3.4-16 ---,/

Table 3.4.1: Steam and Power Conversion Systems Item, Aging Effect/ Number Component Mechanism 3.4.1-20 Copper alloy, stainless Loss of material due steel piping; piping to pitting, crevice, components, and piping and microbiologically elements exposed to influenced corrosion raw water* 3.4.1-21 Stainless steel heat* Loss of material due exchanger components to pitting, crevice, exposed to raw water and microbiologically-influenced corrosion; fouling that leads to corrosion 3.4.1-22 Stainless steel, copper Reduction of heat alloy, steel heat transfer due to exchanger tubes, heat fouling exchanger components exposed to raw water 3.4.1-23 Stainless steel piping, Cracking due to piping components, and stress corrosion piping elements exposed cracking to closed-cycle cooling water >60°C (>140°F) 3.4.1-24 Steel heat exchanger Loss of material due components exposed to to general, pitting, closed-cycle cooling crevice, and galvanic water corrosion 3.0 Aging Management Review Results \ ' Aging Management Programs Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M20, "Open-Cycle Cooling Water System" Chapter Xl.M21A, "Closed Treated Water Systems" Chapter Xl.M21A, "Closed Treated Water Systems" Further Evaluation . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No There are no copper alloy or stainless steel components exposed to raw water in the steam and power conversion' systems in the scope of license renewal. No There are no stainless steel heat exchanger components exposed to raw water in the steam and power conversion systems in the scope of license renewal. No There are no heat exchanger tubes exposed to raw water with an intended function. of heat transfer in the steam and power conversion systems in the scope of license renewal., No There are no stainless steel components exposed to closed-cycle cooling water >60°C (>140°F) in the steam and power conversion systems in the scope of license renewal. No. There are no steel components exposed to closed-cycle cooling water in .the steam and power conversion systems in the scope of license renewal. Page 3.4-17 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component. Mechanism 3.4.1-25 Steel heat exchanger Loss of material due components exposed to to general, pitting, closed-cycle cooling crevice, and galvanic water corrosion 3.4.1-26 Stainless steel heat Loss of material due exchanger components, to pitting and crevice piping, piping corrosion components, and piping elements exposed to closed-cycle cooling water 3.4.1-27 Copper alloy piping, Loss of material due piping components, and to pitting, crevice, piping elements exposed and galvanic to closed-cycle cooling corrosion water ' 3.4.1-28 Steel, stainless steel, Reduction of heat copper alloy heat transfer due to exchanger components fouling and tubes, heat . exchanger tubes .. exposed to closed-cycle cooling water 3.4.1-29 Steel tanks exposed to Loss of material due air.-outdoor (external) to general, pitting, and crevice corrosion 3.0 Aging Management Review Results Further Aging Management Evaluation i:>rograms Recommended Chapter Xl.M21A, "Closed No. Treated Water Systems" Chapter Xl.M21A, "Closed No Treated Water Systems" Chapter Xl.M21A, "Closed No

Treated Water Systems" Chapter Xl.M21A, "Closed No Treated Water Systems" Chapter Xl.M29, No "Aboveground Metallic , Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no steel components exposed to closed-cyele cooling water in the steam and power conversion systems in the scope of license renewal. There are no stainless steel components exposed to closed-cycle . cooling water in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components exposed to closed-cycle cooling water in the steam and power conversion systems in the scope of license renewal. There are no steel, stainless steel or copper alloy components exposed to closed-cycle cooling water in the steam and power conversion systems in the scope of lice.nse renewal. There are no steel tanks exposed to outdoor air in the steam and power conversion systems in the scope of license renewal. Page 3.4-18 i :

Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-30 Steel, stainless steel, Loss of material due aluminum tanks (within to general (steel the scope of Chapter only), pitting, and Xl.M29, "Aboveground crevice corrosion; Metallic Tanks") cracking due to exposed to soil or stress corrosion concrete, or the cracking (stainless following external steel and aluminum environments air-only) outdoor, air-indoor uncontrolled, moist air, condensation 3.4.1-31 Stainless steel, Loss of material due aluminum tanks (within to pitting, and crevice the scope of Chapter corrosion; cracking Xl.M29, "Aboveground due to stress Metallic Tanks") corrosion cracking exposed to soil or concrete, or the following external environments air-outdoor, air-indoor uncontrolled, moist air, condensation 3.4.1-32 Gray cast iron piping, Loss of material due piping components, and to selective leaching piping ele_ments exposed to soil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M33, "Selective No Leaching" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information *' Discussion At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank constructed on soil or concrete in the scope of license renewal is the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. Page 3.4-19 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-33 Gray cast iron, copper Loss of material due alloy (>15% Zn or >8% to selective leaching Al) piping, piping components, and piping elements exposed to treated water, raw water, closed-cycle cooling water 3.4.1-34 Steel external surfaces Loss of material due exposed to air -indoor, to general corrosion uncontrolled (external),

air-outdoor (external), condensation (external) 3.4.1-35 Aluminum piping, piping Loss of material due. components, and piping to pitting and crevice elements exposed to air corrosion -outdoor 3.0 Aging Management Review Results (. Further Aging Management Evaluation Programs Recommended Chapter Xl.M33, "Selective No Leaching" Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" ' Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for gray cast iron components exposed to treated water is managed by the Selective Leaching Program. Other material environment combinations represented by this item are not applicable to steam and power conversion system components in the ; scope of license renewal. Consistent with NUREG-1801. Loss of material for steel components exposed to indoor or outdoor air is managed by the External Surfaces Monitoring Program. There are no uninsulated steel components exposed to condensation in the steam and power conversion systems. in the scope of license renewal. There are no aluminum components exposed to outdoor air in the steam and power conversion systems in the scope of license renewal. Page 3.4-20 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-36 Steel piping, piping Loss of material due components, and piping to general, pitting, elements exposed to air and crevice corrosion -outdoor (internal) 3.4.1-37 Steel piping, piping Loss of material .due components, and piping to general, pitting, elements exposed to and crevice corrosion condensation (internal) 3.4.1-38 Steel piping, piping Loss of material due components, and piping to general, pitting, elements exposed to crevice, galvanic, raw water and microbiologically-influenced corrosion; fouling that leads to corrosion 3.4.1-39 Stainless steel piping, Loss of material due piping components, and to pitting and crevice piping elements exposed corrosion to condensation (internal) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.M38, No "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for internal surfaces of steel
components exposed to outdoor air (Tables 3.3.2-X) is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components Program. There are no steel components exposed to condensation in the steam and power conversion systems in the scope of license renewal. There are no steel components exposed to raw water in the steam and power conversion systems in the scope of license renewal. There are no stainless steel components exposed to condensation in the steam and power conversion systems in the scope of license renewal. Page 3.4-21 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-40 Steel piping, piping Loss bf material due components, and piping to general, pitting, elements exposed to and crevice corrosion lubricating oil 3.4.1-41 Steel heat exchanger Loss of material due components exposed to to general, pitting, lubricating oil crevice, and I / microbiologically-influenced corrosion 3.4.1-42 Aluminum piping, piping Loss of material due components, and piping to pitting and crevice elements exposed to corrosion lubricating oil 3.4.1-43 Copper alloy piping, Loss of material due piping components, and to pitting and crevice piping elements exposed corrosion to lubricating oil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information
Discµssion Consistent with NUREG-1801. Loss of material for steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. Consistent with NUREG-1801. Loss of material for steel heat exchanger components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. : There are no aluminum components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. Page 3.4-22 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-44 Stainless steel piping, Loss of material due piping components, and to pitting, crevice, piping elements, heat and microbiologically exchanger components influenced corrosion exposed to lubricating oil 3.4.1-45 Aluminum heat* Reduction of heat , exchanger components transfer due to and tubes exposed to fouling lubricating oil 3.4.1-46 Stainless steel, Reduction of heat copper alloy heat transfer due to exchanger tubes fouling exposed to lubricating oil 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Chapter Xl.M39, No "Lubricating Oil Analysis," and Chapter Xl.M32, "One-Time Inspection" Waterford Steam Electric Station; Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. Loss of material for stainless steel components exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. There are no aluminum components exposed to lube oil in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduction of heat transfer for stainless steel heat exchanger tubes exposed to lube oil is managed by the Oil Analysis Program. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program to manage loss of material. There are no steel or copper alloy heat exchanger tubes with a heat transfer intended function in the steam and power conversion systems in the scope of license renewal. Page 3.4-23 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-47 Steel (with coating or Loss of material due wrapping), stainless to general, pitting, steel, nickel alloy piping, crevice .* and piping components, and microbiologically piping elements; tanks influencei:f corrosion exposed to soil or concrete 3.4.1-48 Stainless steel, nickel . Loss of material due alloy bolting exposed to to pitting and crevice soil corrosion 3.4.1-49 Stainless steel, nickel Loss of material due alloy piping, piping to pitting and crevice components, and piping corrosion elements exposed to soil or concrete 3.4.1-50 Steel bolting exposed to Loss of material due soil to general, pitting and crevice corrosion 3.4.1-50.5 Underground stainless Loss of material due steel, nickel alloy, steel to general (steel piping, piping only), pitting and components, and piping crevice corrosion elements 3.0 Aging Management Review Results Further Aging Management* Evaluation Programs Recommended Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Chapter Xl.M41, "Buried No and *underground Piping and Tanks" Chapter Xl.M41, "Buried No and Underground Piping and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no components exposed to soil or concrete in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil or concrete in the steam and power conversion systems in the scope of license renewal. There are no components exposed to soil in the.steam and power conversion systems in the scope of license renewal. There are no underground components in the steam and power conversion systems in the scope of license renewal. Page 3.4-24 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-51 .Steel piping, piping None components, and piping elements exposed to concrete 3.4.1-52 Aluminum piping, piping None components, and piping elements exposed to gas, air -indoor, uncontrolled (internal/ external) 3.4.1-53 Copper alloy (S15% Zn None and S8% Al) piping, piping components, and piping elements exposed to air with borated water leakage 3.4.1-54 Copper alloy piping, None piping components, and piping elements exposed to gas, air -indoor, , uncontrolled (external) 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended None, provided 1) No, if conditions attributes of the concrete are met. are consistent with ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG-1557, and 2) plant OE indicates no degradation of the concrete None NA-NoAEM or AMP None NA-NoAEM or AMP None NA-NoAEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no steel components embedded in concrete in the steam and power conversion systems in the scope of license renewal. There are no aluminum components in the steam and power conversion systems in the scope of license renewal. There are no copper alloy (S15% Zn and S8% Al) components in the steam and power conversion systems in the scope of license renewal. There are no copper alloy components in the steam and power conversion systems in the scope of license renewal. Page 3.4-25 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-55 Glass piping elements None exposed to lubricating oil, air -outdoor, condensation (inter:nal/ external), raw water, treated water, air with. borated water leakage, gas, closed-cycle qooling water, air -indoor, uncontrolled (external) 3.4.1-56 Nickel alloy piping, None piping components, and piping elements exposed to air -indoor, uncontrolled (external) 3.4.1-57 Nickel alloy, PVC piping,* None piping components, and piping elements exposed to air with borated water leakage, air -indoor, uncontrolled, condensation (internal) '* 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended None NA-NoAEM or AMP None NA-NoAEM or AMP None NA""'"" No AEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for relevant (indoor air, condensation, lube oil and treated water) environments .. There are no nickel alloy components in the steam and power conversion systems in the scope of license renewal. There are no nickel alloy or PVC components in the steam and power conversion systems in the scope of license renewal. Page 3A-26 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-58 Stainless steel piping, None piping components, and piping elements exposed to air -indoor, uncontrolled (external), concrete, gas, air -indoor, uncontrolled (internal) 3.4.1-59 Steel piping, piping None components, and piping elements exposed to air -indoor controlled (external), gas 3.4.1-60 Any material, piping, Wall thinning due to . piping components, and erosion piping elements exposed to treated water 3.4.1-61 Metallic piping, piping Loss of material due components, and tanks to recurring internal exposed to raw water or corrosion wastewater 3.0 Aging Management Review Results Aging Management Programs None None Chapter Xl.M17, "Flow-Accelerated Corrosion" A plant-specific aging management program is to be evaluated to address recurring internal corrosion . Further Evaluation Recommended NA-NoAEM or AMP NA-NoAEM or AMP No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for relevant (indoor air) environment. There are no steel steam and power conversion system components exposed to controlled indoor air br gas in the scope of license renewal. Consistent with NUREG-1801. Loss of material due to erosion for steel components exposed to treated water is managed by the Flow-Accelerated Corrosion Program. Yes, plant-specific Recurring internal corrosion was not identified in the WF3 steam and power conversion systems in the scope of license renewal. See Section 3.4.2.2.6. Page 3.4-27 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-62 Steel, stainless steel or Loss of material due aluminum tanks (within to general (steel the scope of Chapter only), pitting, and Xl.M29, "Aboveground crevice corrosion Metallic Tanks") exposed to treated water 3.4.1-63 Insulated steel, stainless Loss of material due steel, copper alloy, to general (steel, and aluminum, or copper copper alloy), pitting, . alloy (> 15% Zn) piping, or crevice corrosion, piping components, and and cracking due to tanks exposed to stress corrosion condensation, air-cracking (aluminum, outdoor stainless steel and copper alloy (>15% Zn) only) 3.4.1-64 Jacketed calcium silicate Reduced thermal or fiberglass insulation in insulation resistance an air-indoor due to moisture uncontrolled or air-intrusion outdoor environment 3.0 Aging Management Review Results " '*. Further Aging Management Evaluation Programs Recommended Chapter Xl.M29, No "Aboveground Metallic Tanks" Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" . or Chapter Xl.M29, "Aboveground Metallic Tanks" (for tanks only) Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" .. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion At WF3, there are no tanks within the scope of Chapter Xl.M29, Aboveground Metallic Tanks. The only outdoor tank in the scope of license renewal i_s the fire water storage tank. There are no indoor tanks with a capacity greater than 100,000 gallons. Consistent with NUREG-1801 for insulated carbon steel and stainless steel components exposed to outdoor air. Loss of material and cracking (stainless steel only) is managed by the External Surfaces Monitoring Program. There are no insulated aluminum or copper alloy piping components in the steam and power conversion systems in the scope of license renewal. Consistent with NUREG-1801. Reduced thermal insulation resistance due to moisture intrusion of jacketed calcium silicate or fiberglass insulation is managed by the External Surfaces Monitoring Program. This item applies to aging management review results presented in Tab!e 3.5.2-4. Page 3.4-28 Table 3.4.1 : Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-65 Jacketed foamglas Reduced thermal (glass dust) insulation in insulation resistance an air-indoor due to moisture uncontrolled or air-intrusion outdoor environment 3.4.1-66 Metallic piping, piping Loss of coating or components, heat lining integrity due to exchangers, tanks with blistering, cracking, internal coatings/linings flaking, peeling, exposed to closed-cycle delamination, rusting, cooling water, raw water, or physical damage, treated water, treated . and spalling for borated water, or cementitious lubricating oil coatings/linings 3.4.1-67 Metallic piping, piping Loss of material due components, heat to general, pitting, exchangers, tanks with crevice, and internal coatings/linings microbiologically exposed to closed-cycle influenced corrosion; cooling water, raw water, fouling that leads to treated water, treated *corrosion borated water, or lubricating oil 3.0 Aging Management Review Results Further
Aging Management Evaluation Programs Recommended Chapter Xl.M36, "External No Surfaces Monitoring of Mechanical Components" Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"
Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no insulation components with an intended function of thermal insulation in the stecim and power conversion systems. There are no metallic components with internal coating or linings in the steam and power conversion systems in the scope of license renewal. There are no metallic components with internal coating or linings in the steam and power conversion systems in the scope of license renewal. Page 3.4-29 Table 3.4.1: Steam and Power Conversion Systems Item Aging Effect/ Number Component Mechanism 3.4.1-68 Gray cast iron piping Loss of material due components with internal to selective leaching coatings/linings exposed to closed-cycle cooling water, raw water, or treated water 3.0 Aging Management Review Results Further Aging Management Evaluation Programs Recommended Chapter Xl.M42, "Internal No Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion There are no gray cast iron components with internal coatings or linings in the steam and power conversion systems in the scope of license renewal. Page 3.4-30 Waterford Steam Electric Stat!on, Unit 3 License Renewal Application Technical Information Notes for Table 3.4.2-1 through 3.4.2-5-6 Generic Notes A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. B. Consi_stent with component, material, environment, aging effect'and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. . , G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component*nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 401. The One-Time Inspection Program will verify effectiveness of the Water Chemistry Control -Primary and Secondary Program. 402. The One-Time Inspection Program will verify the effectiveness of the Oil Analysis Program .. 403. The CASS flow elements were evaluated and determined to not be susceptible to thermal aging embrittlement. 404. These components have openings that expose the internal surfaces to outdoor air. Because the internal and external surfaces are exposed to the same environments, aging effects of the internal surfaces can* be inferred from external surface conditions. 405. For the purposes of evaluating loss of coating integrity and loss of material, this environment can be considered equivalent to the NUREG-1801 environment. 3.0 Aging Management Review Results
Page 3.4-31 Table 3.4.2-1 Condensate Makeup and Storage System Summary of Aging Management Evaluation Table 3.4.2-1: Condensate Makeup and Storage System Aging Effect . Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Stainless *steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Flow element Pressure Stainless steel Air-indoor None None boundary (ext) Flow control Flow element Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Primary Flow control and Secondary Orifice Pressure Stainless steel Air-indoor None None boundary (ext) Flow control Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry boundary (int) Control -Primary Flow control and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces boundary (ext) Monitoring 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Page 3.4-32 Table 3.4.2-1: Condensate Makeup and Storage System Component Intended Type Function Material Environment Piping Pressure Carbon steel Air -indoor (int) boundary Piping Pressure Carbon steel Treated water boundary (int) Piping Pressure Stainless steel Air-indoor boundary (ext) Piping Pressure Stainless steel Treated water boundary (int) Pump casing Pressure Stainless steel Air-indoor boundary (ext) Pump casing Pressure Stainless steel Treated water boundary (int) Thermowell Pressure Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel Treated water boundary (int) Valve body Pressure Carbon steel Air-indoor boundary (ext) Valve body Pressure Carbon steel Treated water boundary* (int) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes V.A.E-29 3.2.1-44 E Vlll.E.SP-73 3.4.1-14 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.E.SP-73 3.4.1-14 A, 401 Page 3.4-33 Table 3.4.2-1: Condensate Makeup and Storage System Aging Effect Component Intended Requiring. Type Function Material Environment Management Valve body Pressure Stainless steel Air-indoor None boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material boundary (int) 3.0 Aging Management Review.Results Aging
Management Program None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3:4.1-58 A Vlll.E.SP-87 3.4.1-16 A, 401 Page 3.4-34 Table 3.4.2-2 Emergency Feedwater System Summary of Aging Management Evaluation Table 3.4.2-2: Emergency Feedwater System Aging Effect Aging Component Intended Requiring Management Type Function Material Environment Management Program Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity boundary (ext) ' Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity boundary (ext) Bolting Pressure High strength Air-indoor Cracking Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of material Bolting Integrity boundary steel (ext) Bolting Pressure High strength Air-indoor Loss of preload Bolting Integrity boundary steel (ext) Bolting Pressure Stainless steel Air-indoor Loss of preload Bolting Integrity boundary (ext) Coil Heat transfer Stainless steel Lube oil (ext) Reduction of heat Oil Analysis transfer Coil Pressure Stainless steel Lube oil (ext) Loss of material Oil Analysis boundary 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.S-03 3.4.1-7 B Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B Vlll.G.SP-102 3.4.1-46 A,402 Vlll.G.SP-79 3.4.1-44 A,402 Page 3.4-35 Table 3.4.2-2: Emergency Feedwater System Component Intended Type Function Material Environment Coil Heat transfer Stainless steel Treated water (int) Coil Pressure Stainless steel Treated water boundary (int) Heat exchanger Pressure Gray cast iron Air-indoor (housing) boundary (ext) Heat exchanger Pressure Gray cast iron Lube oil (int) (housing) boundary Insulated piping Pressure Carbon steel Air -outdoor components boundary (ext) Orifice Pressure Stainless steel Air-indoor boundary (ext) Flow control Orifice Pressure Stainless steel Treated water boundary (int) Flow control Piping Pressure Carbon steel Air-indoor boundary (ext) Piping
Pressure Carbon steel Air -outdoor boundary (ext) Piping Pressure Carbon steel Treated water boundary (int) 3.0. Aging Management Review Results Aging Effect Aging Requiring
Management Management Program Reduction of heat Water Chemistry transfer Control -Primary and Secondary Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Oil Analysis Loss of material External Surfaces Monitoring None None Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material External Surfaces Monitoring
Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.E.SP-96 3.4.1-18 C, 401 Vlll.G.SP-87 3.4.1-16 C, 401 Vlll.H.S-29 3.4.1-34 A Vlll.G.SP-76 3.4.1-41 A,402 Vlll.G.S-402 3.4.1-63 A Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.G.SP-74 3.4.1-13 A, 401 Page 3.4-36 Table 3.4.2-2: Emergency Feedwater System Aging Effect *component Intended Requiring Type Function Material Environment Management Pump casing Pressure Stainless steel Air-indoor None boundary (ext) Pump casing Pressure Stainless steel Treated water Loss of material boundary (int) Tubing . Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Treated water Loss of material boundary (int) Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Treated water Loss of material boundary (int) 3.0 Aging Management Review Results Aging Management Program None Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.G.SP-87 3.4.1-16 A,401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.G.SP-74 3.4.1-13 A, 401 Page 3.4-37 Table 3.4.2-3: Main Feedwater System Component Intended Type Function Material Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel Bolting Pressure High strength boundary steel 3.0 Aging Management Review Results Table 3.4.2-3 Main Feedwater System Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Environment Management Program Air-indoor Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Air -outdoor Loss of material Bolting Integrity (ext) Air -outdoor Loss of preload Bolting Integrity (ext) Air-indoor Cracking Bolting Integrity (ext) Air-indoor Loss of material Bolting Integrity (ext) Air-indoor Loss of preload Bolting Integrity (ext) Air -outdoor Cracking Bolting Integrity (ext) Air -outdoor Loss of material Bolting Integrity (ext) Air -outdoor Loss of preload Bolting Integrity (ext) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.S-03 3.4.1-7 B Vlll.H.SP-84 3.4.1-8 B Vlll.H.SP-83 3.4.1-10 B ----G Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Page 3.4-38 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Bolting Pressure Stainless steel Air-indoor Loss of preload boundary (ext) Bolting Pressure Stainless steel Air -outdoor Cracking boundary (ext) Bolting Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Bolting Pressure Stainless steel Air -outdoor Loss of preload boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material components boundary (ext) Orifice Pressure Stainless steel Air -outdoor Cracking boundary (ext) Orifice Pressure Stainless steel Air -outdoor Loss of material boundary . (ext) Orifice Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Orifice Pressure Stainless steel Treated water Cracking -fatigue boundary > 140°F (int) Orifice Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) 3.0 Aging Management Review Results Aging Management Program Bolting Integrity Bolting Integrity Bolting Integrity Bolting Integrity External Surfaces Monitoring External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-83 3.4.1-10 B ----H Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.01 .S-402 3.4.1-63 A Vlll.01 .SP-118 3.4.1-2 A Vlll.01 .SP-127 3.4.1-3 A -Vlll.01.SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.01 .SP-87 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Page 3.4-39 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Steam (int) Cracking -fatigue boundary Piping Pressure Carbon steel Steam (int) Loss of material boundary Piping Pressure Carbon steel Treated water Cracking -fatigue boundary (int) Piping Pressure Carbon steel Treated water Loss of material boundary (int) Piping Pressure Carbon steel Treated water Loss of material -boundary (int) FAC Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Tubing Pressure Stainless steel Steam (int) Cracking boundary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring TLAA-metal fatigue Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion None External Surfaces Monitoring External Surfaces Monitoring Water Chemistry Control -Primary and Seconda*ry TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.S-41 3.4.1-34 A Vlll.81.S-08 3.4.1-1 c Vlll.A.SP-71 3.4.1-14 C, 401 Vlll.01.S-11 3.4.1-1 A Vlll.01 .SP-74 3.4.1-13 A, 401 Vlll.01 .S-16 3.4.1-5 A Vlll.1.SP-12 3.4.1-58 A Vlll.01 .SP-118 3.4.1-2 A Vlll.01 .SP-127 3.4.1-3 A Vlll.A.SP-98 3.4.1-11 C,401 ----H Page 3.4-40 Table 3.4.2-3: Main Feedwater System Component Intended Type Function Material Environment Tubing Pressure Stainless steel Steam (int) boundary Tubing Pressure Stainless steel Treated water boundary > 140°F (int) Tubing Pressure Stainless steel Treated water boundary > 140°F (int) Tubing Pressure Stainless steel Treated water boundary > (int) Valve body Pressure Carbon steel Air-indoor boundary (ext). Valve body Pressure Carbon steel Air -outdoor boundary (ext) Valve body Pressure Carbon steel Treated water boundary (int). Valve body Pressure Carbon steel Treated water boundary (int) Valve body Pressure Carbon steel Treated water bouridary (int) Valve body. Pressure. Stainless steel Air-indoor boundary (ext) 3.0 Aging Managemellt Review Results Aging Effect . Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Cracking Water Chemi.stry Control -Primary .. and Secondary Cracking -fatigue TLAA-metal fatigue Loss of material Water ChemistT"Y Control -Primary and Seconda,.Y Loss of material External Surfaces Monitoring Loss of material. External Surfaces Monitoring Cracking -fatigue TLAA* -metal fatigue Loss of material
Water Chemistry *-* Co.ntrol -Primary and Secondary Loss of material -Flow-Accelerated FAG Corrosion* None. None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.A.SP-155 3.4.1-16 C, 401 Vlll.D1 .SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.D1 .SP-87 3.4.1-16 A,401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.D1 .S-11 3.4.1-1 A Vlll.D1 .SP-74 3.4.1-13 A, 401 Vlll.D1.S-16 . 3.4.1-5 A VllLl.SP-12 3.4.1-58 A
Page 3.4-41 Table 3.4.2-3: Main Feedwater System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body Pressure Stainless steel Steam (int) Cracking boundary Valve body Pressure Stainless steel Steam (int) Cracking -boundary Valve body Pressure Stainless steel Steam (int) Loss of material boundary Valve body Pressure Stainless steel Treated water Cracking boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Cracking -fatigue boundary > 140°F (int) Valve body Pressure Stainless steel Treated water Loss of material boundary > 140°F (int) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.A.SP-98 3.4.1-11 C, 401 ----H Vlll.A.SP-155 3.4.1-16 C, 401 Vlll.01 .SP-88 3.4.1-11 A, 401 Vll.E1.A-57 3.3.1-2 c Vlll.01 .SP-87 3.4.1-16 A, 401 Page 3.4-42 Table 3.4.2-4: Main Steam System ' Component Intended Type Function Material Bearing housing Pressure Gray cast iron boundary Bearing housing Pressure
Gray cast fron boundary Bearing housing Pressure Gray cast iron boundary Bearing housing Pressure Gray cast iron boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure Carbon steel boundary Bolting Pressure
Carbon steel boundary Bolting Pressure High strength " boundary steel Bolting Pressure High strength boundary steel 3.0 Aging Management Review Results Table 3.4.2-4 Main Steam System Summary of Aging Management Evaluation l Aging_ Effect Aging Requiring Management Environment Management Program Air-indoor L:oss of material External Surfaces (ext) Monitoring Lube oil (int) Loss of material Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information I ,, NUREG-1801 Table 1 Item Item Notes Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,.402 -Treated water Loss of material Selective Leaching Vlll.A.SP-27 3.4.1-33 c (int) Treated water Loss of Water Chemistry Vlll.B1 .SP-74 3.4.1-13 A, 401 (int) Control -Primary and Secondary Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B (ext) Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B (ext) Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 3.4.1-8 B (ext) Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3.4.1-10 B (ext) Air-indoor Cracking Bolting Integrity Vlll.H.S-03 3.4.1-7 B (ext) Air -indoor. Loss of material Bolting Integrity Vlll.H.SP-84 B (ext) Page 3.4-43 Table 3.4.2-4: Main Steam System . Component Intended ; Ty.pe . Function Material* Bolting Pressure . High strength* " boundary steel Bolting Pressure High strength *boundary steel Bolting Pressure
High strength
boundary steel Bolting Pressure High strength boundary . steel " Bolting Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Bolting "Pressure Stainless steel boundary Bolting Pressure Stainless steel boundary Filter housing Pressure Carbon steel boundary Filter housing Pressure Carbon steel boundary Flow element Pressure ,carbon steel '. boundary Flow control 3.0 Aging Management Review Results { I Environment Air-indoor (ext) Air-outdoor (ext) ; .. outdoor * (ext) Air -outdoor (ext) Air-indoor (ext) Air -outdoor . (ext) Air -outdoor (ext) Air -outdoor (ext) Air -iridoor . Lube oil (int) Steam (int) Aging Effect Aging Requiring Management Management Program Loss of preload Bolting Integrity Cracking . Bolting Integrity Loss of material* Bolting Integrity Loss of preload Bolting Integrity Loss of preload Bolting Integrity Cracking Bolting Integrity Loss of material Bolting Integrity LO$S of preload Bolting Integrity Loss of materi9I External Surfaces Monitoring
Loss of material ()ii Analysis Cracking -fatigue TLAA-metal fatigue Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.SP-83 ' 3.4.1-10 B ----G Vlll.H.SP-82 3.4.1-8 B Vlll.H.SP-151 3.4.1-10 B Vlll.H.SP-83 3.4.1-10 B --* --H Vlll.H.SP-82 3.4.1-8 B VllLH.SP-151 3.4.1-10 B Vlll.H.S-29 3.4.:1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.B1.S-08 3.4.1-1 A Page 3.4-44 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Flow element Pressure Carbon steel Steam (int) Loss of material boundary Flow control Flow element Pressure Carbon steel Steam (int) Loss of material -boundary FAC Flow control Flow element Pressure CASS Steam (int) Cracking boundary Flow control Flow element Pressure CASS Steam (int) Cracking -fatigue boundary Flow control Flow element Pressure CASS Steam (int) Loss of material boundary Flow control Heat exchanger Pressure Stainless steel Air-indoor None (channel head) boundary (ext) Heat exchanger Pressure Stainless steel Treated water Loss of material (channel head) boundary (int) Heat exchanger Pressure Carbon steel Air-indoor Loss of material (shell) boundary (ext) Heat exchanger Pressure Carbon steel Lube oil (int) Loss of material (shell) boundary 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary None Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Oil Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.81 .S-15 3.4.1-5 A Vlll.81.SP-98 3.4.1-11 A, 401 403 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.l.SP-12 3.4.1-58 c Vlll.81 .SP-87 3.4.1-16 C, 401 Vlll.H.S-29 3.4.1-34 A Vlll.G.SP-76 3.4.1-41 C,402 Page 3.4-45 Table 3.4.2-4: Main Steam System Component Intended Type Function Material Environment Heat exchanger Pressure Stainless steel Lube oil (int) (tube sheet) boundary Heat exchanger Pressure Stainless steel Treated water (tube sheet) boundary (ext) Heat exchanger Pressure Stainless steel Lube oil (ext) (tubes) boundary Heat exchaf!ger Heat transfer Stainless steel Lube oil (ext) (tubes) Heat exchanger Pressure Stainless steel Treated water (tubes) boundary (int) Heat exchanger Heat transfer Stainless steel Treated water (tubes) (int) Insulated piping Pressure Carbon steel Air -outdoor components boundary (ext) Insulated piping Pressure Stainless steel Air -outdoor components boundary (ext) Insulated piping Pressure Stainless steel Air -outdoor components boundary (ext) Nozzle Pressure Stainless steel Steam (ext) boundary Flow control 3.? Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Oil Analysis Loss of material Water Chemistry Control -Primary and Secondary Loss of material Oil Analysis Reduction of heat Oil Analysis transfer Loss of material Water Chemistry Control -Primary and Secondary Reduction of heat Water Chemistry transfer
Control -Primary and Secondary Loss of material External Surfaces Monitoring Cracking External Surfaces Monitoring Loss of material External Surfaces Monitoring Cracking Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.G.SP-79 3.4.1-44 C,402 Vlll.81.SP-87 3.4.1-16 C, 401 Vlll.G.SP-79 3.4.1-44 C,402 Vlll.G.SP-102 3.4.1-46 C,402 Vlll.81.SP-87 3.4.1-16 C, 401 Vlll.E.SP-96 3.4.1-18 C, 401 Vlll.81 .S-402 3.4.1-63 A Vlll.81 .S-402 3.4.1-63 A Vlll.81 .S-402 3.4.1-63 A Vlll.81.SP-98 3.4.1-11 A, 401 Page* 3.4-46 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Nozzle Pressure Stainless steel Steam (ext) . Cracking -fatigue boundary Flow control Nozzle Pressure Stainless steel Steam (ext) Loss of material boundary Flow control Nozzle Pressure Stainless steel Steam (int) Cracking boundary Flow control Nozzle Pressure Stainless steel Steam (int) Cracking -fatigue boundary Flow control Nozzle Pressure Stainless steel Steam (int) Loss of material boundary Flow control Orifice Pressure Carbon steel Air-indoor Loss of material boundary (ext) Flow control Orifice Pressure Carbon steel Lube oil (int) Loss of material boundary Flow control Orifice Pressure Stainless steel Air-indoor None boundary (ext) Flow control 3.0 Aging Management Review Results Aging Management Program TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Surfaces Monitoring Oil Analysis None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.81.SP-98 3.4.1-11 A, 401 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.l.SP-12 3.4.1-58 A Page 3.4-47 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Orifice Pressure Stainless steel Steam (int) Cracking boundary Flow control Orifice Pressure Stainless steel Steam (int) Cracking -fatigue boundary Flow control Orifice Pressure Stainless steel Steam (int) Loss of material boundary Flow control Piping Pressure Carbon steel Air-indoor Loss of material boundary (ext) . Piping Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Piping Pressure Carbon steel Lube oil (int) Loss of material boundary Piping Pressure Carbon steel Steam (int) Cracking -fatigue boundary Piping Pressure Carbon steel Steam (int) Loss of material boundary Piping Pressure Carbon steel Steam (int) Loss of material -boundary erosion Piping Pressure Carbon steel Steam (int)
Loss of material -boundary FAC 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Oil Analysis TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Flow-Accelerated Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81.SP-98 3.4.1-11 A, 401 ----H Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.81 .S-08 3.4.1-1 A Vlll.81 .SP-71 3.4.1-14 A, 401 ----H Vlll.81 .S-15 3.4.1-5 A Page 3.4-48 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Piping Pressure Stainless steel Air-indoor None boundary (ext) Piping Pressure Stainless steel Air -outdoor Cracking boundary (ext) Piping Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Piping Pressure Stainless steel Lube oil (int) Loss of material boundary Pump casing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Pump casing Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Carbon steel Air-indoor Loss of material boundary (ext) Sight glass Pressure Carbon steel Lube oil (int) Loss of material boundary Sight glass Pressure Glass Air-indoor None boundary (ext) Sight glass Pressure Glass Lube oil (int) None boundary Strainer Filtration Stainless steel Steam (ext) Cracking 3.0 Aging Management Review Results Aging Management Program None External Surfaces Monitoring External Surfaces Monitoring Oil Analysis External Surfaces Monitoring Oil Analysis External Surfaces Monitoring Oil Analysis None None Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-118 3.4.1-2 A Vlll.81.SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.H.S-29 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.l.SP-9 3.4.1-55 A Vlll.l.SP-10 3.4.1-55 A Vlll.81 .SP-98 3.4.1-11 A, 401 Page 3.4-49 Table 3.4.2-4: Main Steam System Component Intended Type Function. Material Environment Strainer Filtration Stainless steel Steam (ext) Strainer housing. Pressure Carbon steel Air-indoor boundary ' (ext) Strainer housing Carbon steel Steam (int) boundary Thermowell Pressure Carbon steel Air -outdoor boundary (ext) Thermowell Pressure Carbon steel Steam (int) boundary ThermoWell Pressure Carbon steel Steam (int) boundary Thermowell Pressure
Stainless steel Air-indoor boundary (ext) Thermowell Pressure Stainless steel
Steam (int) boundary Thermowell Pressure Stainless steel Steam (int) boundary .' Thermowell Pressure Stainless steel Steam (int) boundary. 3.0. Aging Management Review Results Aging Effect Aging Requiring Management Management Program Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Loss of material Water Chemistry Control -Primary and Secondary Loss of material External Surfaces Monitoring Cracking -fatigue TLAA-metal fatigue Loss of material Water Chemistry Control -Primary and Secondary None None Cracking Water Chemistry Control -Primary and Secondary Cracking -fatigue TLAA-metal
fatigue Loss of material Water Chemistry Control -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81.SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.81.SP-71 3.4.1-14 A, 401 Vlll.H.S-41 3.4.1-34 A Vlll.81.S-08 3.4.1-1 A Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Page 3.4-50 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Tubing Pressure Carbon steel Treated water Loss of material boundary (int) Tubing Pressure Stainless steel Air-indoor None boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking boundary (ext) Tubing Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Tubing Pressure Stainless steel Lube oil (int) Loss of material boundary Tubing Pressure Stainless steel Steam (ext) Cracking boundary Tubing Pressure Stainless steel Steam (ext) Cracking -fatigue boundary Tubing Pressure Stainless steel Steam (ext) Loss of material boundary Tubing Pressure Stainless steel Steam (int) Cracking boundary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue boundary 3.0 Aging Management Review Results Aging Management Program External Surfaces Monitoring Water Chemistry Control -Primary and Secondary None External Surfaces Monitoring External Surfaces Monitoring Oil Analysis Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Water Chemistry Control -Primary and Secondary TLAA-metal fatigue Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.H.S-29 3.4.1-34 A Vlll.81 .SP-74 3.4.1-13 A, 401 Vlll.l.SP-12 3.4.1-58 A Vlll.81 .SP-118 3.4.1-2 A Vlll.81 .SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.81.SP-98 3.4.1-11 A, 401 ----H Page 3.4-51 Table 3.4.2-4: Main Steam System Aging Effect Component Intended Requiring Type Function Material Environment Management Tubing Pressure Stainless steel Steam (int) Loss of material boundary Turbine casing Pressure Carbon steel Air-indoor Loss of material boundary (ext) Turbine casing Pressure Carbon steel Steam (int) Loss of material boundary Valve body Pressure Carbon steel Air-indoor Loss of material boundary (ext) Valve body Pressure Carbon steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Carbon steel Lube oil (int) Loss of material boundary Valve body Pressure Carbon steel Steam (int) Cracking -fatigue boundary Valve body Pressure Carbon steel Steam (int) Loss of material boundary Valve body Pressure Carbon steel Steam (int) . Loss of material -boundary FAC Valve body Pressure Carbon steel Treated water Loss of material boundary (int) Valve body Pressure Stainless steel Air-indoor None boundary (ext) 3.0 Aging Management Review Results Aging Management Program Water Chemistry Control -Primary and Secondary External Surfaces Monitoring Water Chemistry Control -Primary and Secondary External Surfaces Monitoring External Surfaces Monitoring Oil Analysis TLAA-metal fatigue Water Chemistry Control -Primary and Secondary Flow-Accelerated Corrosion Water Chemistry Control -Primary and Secondary None Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vlll.81 .SP-155 3.4.1-16 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.81 .SP-71 3.4.1-14 A, 401 Vlll.H.S-29 3.4.1-34 A Vlll.H.S-41 3.4.1-34 A Vlll.A.SP-91 3.4.1-40 C,402 Vlll.81 .S-08 3.4.1-1 A Vlll.81.SP-71 3.4.1-14 A, 401 Vlll.81 .S-15 3.4.1-5 A Vlll.81.SP-74 3.4.1-13 A,401 Vlll.l.SP-12 3.4.1-58 A Page 3.4-52 i Table 3.4.2-4: Main System Aging Effect Component Intended Requiring Type Function Material Environment Management Valve body . . Pressure Stainless steel Air -outdoor Cracking boundary (ext) Valve body Pressure Stainless steel Air -outdoor Loss of material boundary (ext) Valve body Pressure Stainless steel Lube oil (int) Loss of material boundary Valve body Pressure Stainless steel Steam (int) Cracking bqundary Valve body Pressure Stainless steel Steam (int) Cracking -fatigue boundary Valve body Pressure Stainless steel Steam (int) Loss of material boundary ' 3.0 Aging Management Review Results *Aging Management Program External Surfaces Monitoring External Surfaces Monitoring Oil Analysis Water Chemistry Control -Primary and Secondary TLAA -: metal fatigue Water Chemistry Contr9I -Primary and Secondary Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU.REG-1801 Table 1 Item .'Item Notes Vlll.81:SP-118 3.4.1-2 A Vlll.81 .SP-127 3.4.1-3 A Vlll.A.SP-95 3.4.1-44 C,402 Vlll.81 .SP-98 3.4.1-11 A, 401 ----H Vlll.81 .SP-155 3.4.1-16 A, 401 Page 3.4-53 Table 3.4.2-5-1 Slowdown System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging _Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material -Environment Management Program Item Item Notes Accumulator Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Accumulator Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H . .SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload . Bolting Integrity VllLH.SP-83 3.4.1-10 B boundary (eXt) Demineralizer Pressure Carbon steel Air-indoor 'Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) _ Monitoring Demineralizer Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Filter housing Pressure
Stainless steel Air*_ indoor None
None _ VllLLSP-12* 3.4.1-58 A boundary (ext) .. ' , -Filter housing Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-278 3.3.1-95 E . boundary (int) Surveillance and -' .. Preventive ', Maintenance 3.0 Aging Management Review Results Page 3.4-54 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Flow element Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Flow element Pressure Stainle.ss steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Heat exchanger Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A (shell) boundary (ext) Monitoring Heat exchanger Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-78 3.4.1-14 A,401 (shell) boundary (int) Control -Primary and Secondary Orifice Pressure Stainless steel Air-indoor None None Vlll.1.SP-12 3.4.1-58 A boundary (ext) Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C, 401 boundary Control -Primary and Secondary Pipiflg Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAG Corrosion Piping Pressure Carbon steel Treated water Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1-c boundary (int) fatigue 3.0 Aging Management Review Results Page 3.4-55 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.01 .S-408 3.4.1-60 c boundary (int) erosion Corrosion Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.F.S-16 3.4.1-5 A boundary (int) FAC Corrosion Piping Pressure Carbon steel Waste water Loss of material Internal Surfaces in VI I. E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Piping *Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Pump casing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Pump casing Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Pump casing Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.F.S-16 3.4.1-5 A boundary (int) FAC Corrosion Pump casing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) 3.0 Aging Management Review Results Page 3.4-56 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Pump casing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Pump casing Pressure Stainless steel Waste water Loss of material Periodic VI I. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Sight glass Pressure Glass Air-indoor None None Vlll.l.SP-9 3.4.1-55 A boundary (ext) Sight glass Pressure Glass Treated water None None Vlll.l.SP-35 3.4.1-55 A boundary (int) Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74
3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary Tank Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Tank Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C,401 boundary Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-57 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Blowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tank Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Tank Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-75 3.4.1-12 C, 401 boundary (int) Control -Primary and Secondary Tank Pressure Carbon steel Wastewater Loss of material Periodic Vll.E5.AP-278 3.3.1-95 E boundary (int) Surveillance and Preventive Maintenance Tubing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Tubing Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary
and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 c boundary fatigue Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.A.SP-71 3.4.1-14 C, 401 boundary Control -Primary and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.A.S-15 3.4.1-5 c boundary FAC Corrosion Valve body Pressure Carbon steel Treated water Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 c boundary (int) fatigue 3.0 Aging Management Review Results Page 3.4-58 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-1 :Slowdown System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect* Aging Component Intended Requiring Management
NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.F.SP-74 3.4.1-13 A, 401 boundary (int) Control -:-Primary and Secondary Valve body Pressure Carbon steel Treated water Loss of material -Flow-Accelerated VllLA.S-16 3.4.1-5 A boundary (int) FAC Corrosion Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1:..91 c boundary (int) Miscellaneous Piping and Ducting Components Valve body Pressure Carbon steel Wastewater Loss of material Periodic Vll.ES.AP-281 3.3.1-91 E boundary (int) .Surveillance and Preventive Maintenance Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1:-58 A boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Wastewater Loss of material Internal Surfaces in VI I :ES.AP-278 3.3.1-95 c boundary (int) Miscellaneous '. ' Piping and Ducting Components Valve'body Pressure Stainless steel Wastewater Loss of material Periodic* VI I. ES.AP-278 3.3.1-95 E boundary , (int) ' Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.4-59 Table 3.4.2-5-2 Condensate System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary ,of Aging Management Evaluation Table 3.4.2-5-2:Condensate System, Nonsafety-Related Components Affecting Safety.:Related Systems Aging Effect Aging Component Intended Requiring *Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) Piping Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring .
Piping Pressure Carbon st'3el Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) C.ontr9I -Primary and Secondary Piping Pressure Carbon steel Treated water Loss of material -Flow-Accelerated Vlll.D1 .S-408 3.4.1-60 c boundary (int) erosion Corrosion Piping Pressure Carbon steel Waste water
Loss of material Periodic Vll.E5.AP-2.81 3.3.1-91 E boundary (int) . , Surveillance and Preventive Maintenance Sight glass Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Sight glass Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-60 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-2:Condensate System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Sight glass Pressure Glass Air-indoor None None Vlll.l.SP-9 3.4.1-55 A boundary (ext) Sight glass Pressure Glass Treated water None None Vlll.l.SP-35 3.4.1-55 A boundary (int) Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Carbon steel Waste water Loss of material Periodic VII. E5.AP-281 3.3.1-91 E boundary (int) Surveillance and Preventive Maintenance 3.0 Aging Management Review Results Page 3.4-61 Table 3.4.2-5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Condensate Makeup and Storage System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-3:Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) ' Filter housing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Filter housing Pressure Stainless steel Treated water 'Loss .of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Flow element Pressure Stainless steel Air-'-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Flow element Pressure Stainless steel Treated water. Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary .. and Secondary Piping Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Piping Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) . Control -Primary and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext)
Monitoring 3.0 Aging Management Review Results 'Page 3.4-62 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-3:Condensate Makeup and Storage System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.E.SP-73 3.4.1-14 A, 401 boundary (int) Control -Primary and Secondary Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-63 Table 3.4.2-5-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Emergency Feedwater System Nonsafety-Related Components Affecting.Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-4:Emergency Feedwater System, Nonsafety-Related Components .Affecting Safety-Related Systems . . Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Valve body Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.01 .SP-74 '3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-64 Table 3.4.2-5-5 Feedwater System Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-S:Feedwater System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 3.4.1-8 B boundary (eXt) Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3.4.1-10 B boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.01 .S-402 3.4.1-63 A components boundary (ext) Monitoring Orifice Pressure Stainless steel Air -outdoor Cracking External Surfaces Vlll.01.SP-118 3.4.1-2 A boundary (ext) Monitoring Orifice Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.01 .SP-127 3.4.1-3 A boundary (ext) Monitoring Orifice Pressure Stainless steel Treated water Loss of material Water Chemistry Vlll.F.SP-87 3.4.1-16 A, 401 boundary (int) Control -Primary and Secondary Piping Pressure Carbon steel Air -outdoor Loss qf material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Treated water Loss of material Water Chemistry Vlll.01 .SP-74 3.4.1-13 A, 401 boundary (int) Control -Primary and Secondary 3.0 Aging Management Review Results Page 3.4-65 Table 3.4.2-5-6 Main Steam System Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Compo'nent Intended Requiring
Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Bolting Pressure
Carbon steel Air-indoor Loss of material Bolting Integrity Vlll.H.SP-84 3.4.1-8 B boundary (ext) Bolting Pressure Carbon steel . Air-indoor Loss of preload Bolting Integrity Vlll.H.SP-83 3.4.1-10 B boundary (ext) Bolting Pressure Carbon steel Air -outdoor Loss of material Bolting Integrity Vlll.H.SP-82 '3.4.1-8 B boundary (ext) *Bolting Pressure Carbon steel Air -outdoor Loss of preload Bolting Integrity Vlll.H.SP-151 3A.1-10 B boundary (ext) Insulated piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.B1 .S-402 3.4.1-63 A components bounda,.Y (ext) Monitoring Module Support for Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A criterion (a)(1) (ext) Monitoring equipment Module Support for* Carbon steel Air -outdoor Loss of material External Surfaces ---G,404 criterion (a)(1) (int) Monitoring equipment Piping Pressure Carbon steel , Air -indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Piping Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-66 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-G:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Piping Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 A boundary fatigue Piping Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Piping Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Piping Pressure Carbon steel Wastewater Loss of niaterial Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Strainer housing Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Strainer housing Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Strainer housing Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Strainer housing Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.ES.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Trap Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-67 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Trap Pressure Carbon steel Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Trap Pressure Carbon steel Steam (int) Cracking -fatigue TLAA-metal Vlll.81.S-08 3.4.1-1 A boundary fatigue Trap Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81.SP-71 3.4.1-14 A, 401 boundary Control -Primary and Secondary Trap Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81 .S-15 3.4.1-5 A boundary FAC Corrosion Trap Pressure Carbon steel Waste water Loss of material Internal Surfaces in Vll.E5.AP-281 3.3.1-91 c boundary (int) Miscellaneous Piping and Ducting Components Tubing Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Tubing Pressure Stainless steel Air -outdoor Cracking External Surfaces Vlll.81.SP-118 3.4.1-2 A boundary (ext) Monitoring Tubing Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.81 .SP-127 3.4.1-3 A boundary (ext) Monitoring *Tubing Pressure Stainless steel Steam (int) Cracking Water Chemistry Vlll.81 .SP-98 3.4.1-11 A,401 boundary Control -Primary and Secondary Tubing Pressure Stainless steel Steam (int) Cracking -fatigue TLAA-metal ----H boundary fatigue 3.0 Aging Management Review Results Page 3.4-68 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG-1801 Table 1 Type Function Material Environment Management Program Item Item Notes Tubing Pressure Stainless steel Steam (int) Loss of material Water Chemistry Vlll.81 .SP-155 3.4.1-16 A, 401 boundary Control -Primary and Secondary Valve body Pressure Carbon steel Air-indoor Loss of material External Surfaces Vlll.H.S-29 3.4.1-34 A boundary (ext) Monitoring / Valve body
Pressure Carbon steel-Air -outdoor Loss of material External Surfaces Vlll.H.S-41 3.4.1-34 A boundary (ext) Monitoring Valve body Pressure Carbon steel Steam (int) Cracking-fatigue TLAA-metal Vlll.81 .S-08 3.4.1-1 A boundary fatigue . Valve body Pressure Carbon steel Steam (int) Loss of material Water Chemistry Vlll.81.SP-71 3.4.1-14 A, 401 boundary Control -Primary. and Secondary Valve body Pressure Carbon steel Steam (int) Loss of material -Flow-Accelerated Vlll.81.S-15 3.4.1-5 A boundary FAG Corrosion Valve body Pressure Carbon steel Wastewater Loss of material Internal Surfaces in Vll.E5.AP-281 3.3, 1-91 c boundary (int) Miscellaneous Piping and Ducting .. Components Valve body Pressure Stainless steel Air-indoor None None Vlll.l.SP-12 3.4.1-58 A boundary (ext) Valve body Pressure Stainless steel Air -outdoor cracking External Surfaces Vlll.81 .SP-118 3A.1-2 . A boundary (ext) Monitoring Valve body Pressure Stainless steel Air -outdoor Loss of material External Surfaces Vlll.81 .SP-127 3.4.1-3 A boundary (ext) Monitoring 3.0 Aging Management Review Results Page 3.4-69 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.4.2-5-S:Main Steam System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect .Aging Component Intended Requiring Management NUREG-1801 Table 1 Ty.pe Function Material Environment
Management Program Item lterri Notes Valve body Pressure Stainless steel Steam .(int) Cracking Water Chemistry Vlll.81 .SP-98 3.4.1-11 A,401 boundary Control Primary and Secondary Valve body Pressure Stainless steel Steam (int) Cracking.-fatigue Tl.AA-metal ----H boundary fatigue Valve body Pressure Stainless steel Steam (int) Loss of material Water. Chemistry Vlll.81.SP-155 . 3.4.1-16 A, 401 boundary Control -Primary: and Secondary 3.0 Aging Management Review Results Page 3.4-70 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.5 CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS .3.5.1 Introduction This section provides the results of the aging management review for structural components and commodities that are subject to aging management review. The following structures and commodity groups are addressed in this section (descriptions are available in the referenced sections).
Reactor Building (Section 2.4.1)
Nuclear Plant Island Structure (Section 2.4.2)
Turbine Building and Other strudures (Section 2.4.3)
Bulk Commodities (Section 2.4.4) Table 3.5.1, Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and Ill of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 for structures and component supports. Hyperlinks are provided to the program evaluations in Appendix B. 3.5.2 Results The following tables summarize the results of aging management reviews and the NUREG-1801 comparison for structures and component supports.
Table 3.5.2-1 Reactor Building -Summary of Aging Management Evaluation
Table 3.5.2-2 Nuclear Plant Island Structure -Summary of Aging Management Evaluation
Table 3.5.2-3 Turbine Building and Other Structures -Summary of Aging Management Evaluation
Table 3.5.2-4 Bulk Commodities -Summary of Aging Management Evaluation 3.5.2.1 Materials, Environments, Aging Effects Requiring Management and Aging Management Programs The following sections list the materials, environments, aging requiring management, and aging management programs for structures and component supports subject to aging management review. Programs are described in Appendix B. Further details are provided in the structure and commodities tables. 3.0 Aging Management Review Results Page 3.5-1 Waterford Steam Electric Station, Unit 3 " """ License Renewal Application Technical Information 3.5.2.1.1 Reactor Building Materials Reactor building components are constructed of the following materials. .. Carbon steel
Coatings
Concrete
Elastomer
Stainless steel Environments Reactor building components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Air with borated water leakage
Exposed to fluid environment Aging Effects Requiring Management The following aging effects associated with the reactor building require management. * * * * * * *
Cracking Increase in porosity and permeability . Loss of bond Loss of coating integrity Loss of leak tightness Loss of material Loss of preload Loss of sealing Aging Management Programs The following aging m*anagement programs manage the effects of aging on the reactor building.
Boric Acid Corrosion
Containment lnservice Inspection -IWE
Containment Leak Rate
Fire Protection
lnservice Inspection -IWF 3.0 Aging Management Review Results Page 3.5-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Protective Coating Monitoring and Maintenance
Structures Monitoring 3.5.2.1.2 Nuclear Plant Island Structure
Materials Nuclear plant island structure components are constructed of the following materials.
Carbon steel
Concrete
Concrete block
Galvanized steel
Stainless steel Environments Nuclear plant island structure components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Exposed to fluid environment
Soil Aging Effects Requiring Management The following aging effects associated with the nuclear plant island structure require management. * * * * *
Cracking Cracks and distortion Increase in porosity and permeability Loss of bond Loss of material Loss of strength Aging Management Programs The following aging management programs manage the 'effects Cif aging on the nuclear plant island structure components.
Fire Protection 3.0 Aging Management Review Results Page 3.5-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Masonry Wall
Structures Monitoring
Water Chemistry Control -Primary and Secondary 3.5.2.1.3 Turbine Building and Other Structures Materials Turbine building and other structures are constructed of the following materials.
Carbon steel
Concrete
Concrete block
Galvanized steel
Treated wood Environments Turbine building and other structures components are exposed to the following environments.
Air -indoor uncontrolled
Air -outdoor
Exposed to fluid environment
Soil Aging Effects Requiring Management The following aging effects associated with the turbine building and other structures require management. * * * * * *
Change in material properties Cracking Cracks and distortion Increase in porosity and permeability Loss of bond Loss of material Loss of strength 3.p Aging Management Review Results Page 3.5-4 Aging Management Programs Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information The following aging management programs manage the effects of aging on the turbine building and other structures components.
Fire Protection
Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems
Masonry Wall
Structures Monitoring 3.5.2.1.4 Bulk Commodities Materials Bulk commodity components are constructed of the following materials.
Aluminum
Calcium silicate
Carbon steel
Cerablanket
Concrete
Elastomers
Fibergl_ass
Galvanized steel
HEMYC
Kaowool blanket
Silicone elastomer
Siltemp fibersil cloth
Stainless steel
Thermo-lag Environments . Bulk commodity com-porients are exposed to _the following environments.
Air -indoor uncontrolled
Air -outdoor
Air with borated water leakage
Exposed to fluid environment 3.0 Aging Management Review Results Page 3.5-5 Waterford Ster;im Electric Station, Unit 3 ---, License Renewal Application Technical Information Aging Effects Requiring The following. aging effects associated with the bulk commodities require management.
Change in material properties
Cracking
Cracking/delamination, separation
Increase in porosity and permeability
Increased hardness, shrinkage, loss of strength
Loss of bond * * * * *
Loss of material Loss of mechanical function Loss of preload Loss of sealing Reduction in concrete anchor capacity Reduction or loss of isolation function Management Programs The following aging management programs manage the effects of aging on the bulk commodity components.
Boric Acid Corrosion *
External Surface$ Monitoring
Fire Protection
Fire Water System
lnservice Inspection -IWF
Structures Monitoring
Water Chemistry Control -Primary and Secondary 3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 NUREG-1800 indicates that further evaluation is necessary for certain aging effects and other issues discussed in Section 3.5.2.2 of NUREG-1800. The following sections are numbered in accordance with the discussions in NUREG-1800 and explain the WF3 approach to those areas requiring further eyaluation. Programs are described in Appendix B. 3.0 Aging Management Review Results Page 3.5-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.5.2.2.1 PWR and BWR Containments 3.5.2.2.1.1 Cracking and Distortion due to Increased Stress Levels from Settlement; Reduction of Foundation Strength, and* Cracking due to Differential Settlement and Erosion of Porous Concrete Subfoundations 3.5.2.2.1.2 The WF3 containment is a low-leakage free-standing steel containment vessel (SCV) structure consisting of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate* encased in concrete which is completely enclosed by
the reinforced shield building. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the related shield building and the common rigid reinforced concrete foundation structure for the NPIS, as discussed in Section 3.5.2.2.2.1 Item 3. WF3 does not rely on a dewatering system for control of settlement. The WF3
SCV structure's base foundation is integral with the base foundation of the shield building and _is founded on a common rigid reinforced concrete foundation strudure for the NPIS and does not use a porous concrete subfoundation. Additionally, Information Notice 97-11 did not identify WF3 as a plant susceptible* to erosion of porous concrete subfoundations. Therefore, reduction of foundation strength, cracking due to differential settlement, and erosion of porous concrete subfoundations is not applica_ble to the WF3 SCV structure's base foundation concrete. Reduction of Strength and Modulus due to Elevated Temperature The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC . is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is Inaccessible, it is exempted from examinatio.n in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield 3.0 Aging Management Review Results .* Page 3.5-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information building and the Common rigid reinforced concrete foundation structure for the
NPIS and further discussed in Section 3.5.2.2.2.2. Puring normal operation, areas within containment are maintajned below an average temperature of 120°F per technical.specifications, which is below the
threshold temperature of greater than 150°F general area. Process piping carrying hot fluid (pipe temperature greater than 200°F) are routed through penetrations in the SCV that are not.encased in concrete. Therefore, the local
area temperatures greater than 200°F local is not applicable for the WF3 containment. Therefore, change in material properties due to elevated temperature is not ar:i aging effect requiring management for containment concrete. As a result, reduction of strength and modulus of concrete due to elevated . . temperatures are*not aging effects requiring management.for the WF3 standing SCV structure. The aging effect "change in material properties" is equivalent to the NUREG-1801 aging effect "reduction of strength and modulus of elasticity. * . 3.5.2.2.1.3 . Loss of Material due to General, Pitting and Cr,evice Corrosion 1. Loss of m_aterial due to general, pitting, and crevice corrosion could occur in steel of inaccessible areas for all types of PWR and BWR containments. The WF3 containment is a low-leakage free-!:)tanding SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom. liner plate encased in concrete. The WF3_ SCV.structure's base foundation is integral with the base foundation of the shield building. A moisture barrier is provided where the steel liner becomes embedded in the concrete floor. The SCV is inspected in accordance with the requirements of Subsection IWE of the ASME Code Section XI. These inspections include a visual exal'Jlination of the accessible interior and the exterior surfaces of the class MC components, parts and appurtenances .of the steel containment vessei as well as visual inspection of the moisture barrier at the concrete-to-steel interface. Loss of material due to general, pitting and crevice corrosion of the steel elements of accessible areas is managed by the Containment lnseivice Inspection-* 1wE Program, the Containment Leak Rate Program (10 CFR Part 50,* Appendix J Program) and the Boric.Acid Corrosion Program. Interior concrete is monitored for .cracks under the Structures Monitoring Program. Moisture b.arriers are intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining metal containment shell or liner at. concrete-to-metal interfaces and at metal-to-metal interfaces which are not seal welded. The WF3 moisture barrier is the elastomeric sealant between the concrete to metal containment interface. 3.0 Aging Management Review Results Page 3.5-8 3.5.2.2.1.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A review of plant operating experience was conducted from the Containment lnservice Inspection -IWE Program walkdowns. One condition report identified during the performance of visual inspections of the containment during VT-3 inspection of the containment inner moisture barrier (located between the containment vessel and the concrete floor on the ledge on elevation -4), six *damaged locations of the moisture barrier. Damage was primarily age related degradation and mechanical damage to the moisture barrier. The containment moisture barrier is intended to provide long term corrosion protection of the containment vessel. It is not required by Technical Specifications or the Technical Requirements Manual and is not required to support the function of any safety-related structures, systems or components. None of the affected areas showed signs of wetting and no corrosion of the containment vessel was noted. Corrective action removed the damaged portions of moisture barrier and replaced them with new sealant barrier material. The continued monitoring of the WF3 steel containment vessel for loss of material due to general, pitting, and crevice corrosion through the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Program provides -reasonable assurance that loss of material in inaccessible areas of Containme.nt is insignificant and will be detected prior to a loss of an intended function. 2. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus shell of Mark I containments. WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete. The WF3 PWR containment does not have a steel torus shell. Therefore, this item does not apply to WF3. 3. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus ring girders and downcomers of Mark I containments, downcomers of Mark II containments, and interior surface of suppression chamber shell of Mark Ill containments. WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete'. The WF3 PWR containment does not have*a torus ring girder or downcomers. Therefore this item does not apply to WF3. Loss of Prestress due to Relaxation, Shrinkage, Creep, and Elevated Temperature WF3 is a PWR with a free-standing SCV comprised of a cylindrical wall, a hemispherical dome, and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation is integral with the base foundation of 3.0 Aging Management Review Results Page 3.5*9 3.5.2.2.1.5 3.5.2.2.1.6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information the shield building with no prestressed tendons associated with its design. Therefore, loss of prestress due to relaxation, shrinkage, creep, and elevated temperature does not apply. Cumulative Fatigue Damage TLAAs are evaluated in accordance with 10 CFR 54.21(c) as documented in Section 4. By design, the WF3 steel containment vessel is not subject to a TLAA. Fatigue TLAAs for bellows are evaluated as documented in Section 4.6. Other containment mechanical penetration bellows that are located outside the containment building have been screened out of scope because they do not perform a pressure boundc;iry intended function and no fatigue analysis exists. The NUREG-1801 BWR components, e.g., torus, suppression pool shell, vent line bellows, and unbraced downcom.ers, related to Mark I and II containments are not
applicable to the WF3 PWR contai,nment. Cracking due to Stress Corrosion Cracking Stress corrosion cracking (SCC) is not an applicable aging mechanism for the steel containment vessel (SCV) carbon steel penetration sleeves, stainless steel penetration bellows, and. dissimilar metal welds. The WF3 SCV and associated . penetration sleeves are carbon steel. High temperature piping systems \. penetrating the containment are carbon steel. Stress corrosion cracking is only applicable to stainless steel and is predicted only under certain conditions. There are dissimilar metal welds associated with stainless steel bellows welded to carbon steel penetration sleeves, sec of dissimilar metal welds of stainless steel at the penetration sleeves is not considered credible because stainless steel sec requires a concentration of chloride or sulfate contaminants, which are not normally present in significant quantities, as well as high stress and temperatures greaterthan 140°F. Leakage of water in the containment, which might contact the penetration sleeves, is event driven. The containment pressure welds between stainless steel piping and penetration sleeves, with normal operating temperatures above 140°F, are not highly stressed. In addition, the Technical Specification limits the average air temperature inside the primary containment durin*g normal plant operation to 120°F. Therefore cracking of these components due to stress corrosion cracking is not applicable. However, cracking due to SCC of dissimilar metal welds for carbon steel and stainless steel will be managed by the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Pr?gram. NUREG-1801 recommends further evaluation of inspection methods to detect cracking due to stress corrosion cracking (SCC) since visual VT-3 examinations may be unable to detect this aging effect. Potentially susceptible components at WF3 are penetration sleeves and bellows. 3.0 Aging Management Review Results Page 3.5-10 3.5.2.2.1.7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Three factors are necessary to initiate and propagate cracking due to sec, including trahsgranular stress corrosion cracking (TGSCC). These factors are susceptible or sensitized material (resulting from manufacturing or installation process), a high tensile stress (residual or applied), arid corrosive environment (high temperatures, moist or wetted environment or an environment contaminated with chlorides, fluorides, or sulfates). Elimination or reduction of any of these factors will decrease the likelih'ood of SCC. TGSCC of WF3 stainless steel bellows is not considered credible because the corrosive environment (concentration of chloride or sulfate contaminants and temperatures greater than 140°F) does not exist for the bellows .. Therefore, SCC of WF3 stainless steel bellows due to TGSCC is not expected. A review of plant experience did not identify cracking of this component, and containment pressure boundary functions have not been identified as a concern.
sec is not an applitable aging mechanism for the SCV carbon steel penetration sleeves, and dissimilar metal welds. The WF3 SCV and associated penetration sleeves are carbon steel. High temperature piping systems penetrating the containment are generally carbon steel. Stress corrosion cracking is only applicable to*stainless steel and is predicted only under certain conditions as discussed sec of dissimilar metal welds of stainless steel at the penetration sleeves is not considered credible because stainless steel sec
requires a concentration of chloride or sulfate contaminants, which are not present in significant quantities, as well as high stress and greater than 14q°F: Leakage of water in the containment, which mighf contact the penetration sleeves, is not the normal operating environment .. The containment pressure boundary welds between stainless steel piping and penetration sleeves, with normal operating temperatures. above 14.0°F, are not highly stressed. In addition,
the Technical Specification limits the average air temperature inside the primary containment during normal plant operation t.o 120°F. A review of plant operating experience did not identify cracking of these components, and containment pressure boundary functions have not been identified as ;f cqncern. Therefore, cracking of these components due to stress corrosion cracking is not expected. Nevertheless, the Containment lnservice Inspection -IWE Program and the Containment Leak Rate Program manage cracking due to SCC of stainless steel bellows and dissimilar metal welds for carbon steel and steel. Loss of Material (Scaling, Spalling) and Cracking due to Freeze-Thaw
The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure!. for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC 3.0 Aging Management Review Results Page 3.5-11 3.5.2.2.1.8 3.5.2.2.1.9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). The base foundation of the SCV is below grade and protected from the outer environment by the shield building's base foundation and is not subject to freeze-thaw action. The WF3 concrete structures subject to the air-outdoor environment are not exposed to temperatures of 32°F or less of sufficient durations that would cause freeze-thaw aging effects to occur. WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90.
As a result, loss of material and cracking due to freeze-thaw are not aging effects requiring management for WF3 SCV structure's base foundation concrete. Therefore, loss of material and. cracking due to freeze-thaw are not aging effects requiring management for the WF3 SCV concrete base foundation. Cracking due to Expansion from Reaction with Aggregate The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome, and an eliipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's containment that is classified as Class CC equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). Based on ongoing industry operating experience, the Structures Monitoring Program manages cracking due to expansion from reaction with aggregate in accessible concrete areas for the WF3 SCV concrete base foundation. However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield building and the common rigid reinforced concrete foundation structure for the NPIS and further discussed in Section 3.5.2.2.2.1 Item 2. Increase in Porosity and Permeability due to Leaching of Calcium Hydroxide and Carbonation The WF3 containment is a low-leakage free-standing SCV structure consisting of a cylindrical wall, a hemispherical dome and an ellipsoidal bottom liner plate encased in concrete. The WF3 SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The portion of WF3's *containment that is classified as Class CC 3.0 Aging Management Review Results Page 3.5-12 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information equivalent is the common concrete foundation with the shield building. Since the Class CC equivalent concrete foundation slab is inaccessible, it is exempted from examination in accordance with IWL-1220(b). However, the listed aging effects will be addressed under the concrete foundation for the safety-related shield building and the common rigid reinforced concrete foundation structure for the NPIS and further discussed in Section 3.5.2.2:2.1 Item 4. Therefore, increase in porosity and permeability due to leaching of calcium hydroxide and carbonation are not aging effects requiring*management for the WF3 SCV concrete base foundation. 3.5.2.2.2 Safety-Related and Other Structures and Component Supports . 3.5.2.2.2.1 Structure groups and component support groups as used in the following discussions are defined in NUREG-1800, Section 3.5.1. Aging Management of Inaccessible Areas 1. Loss of Material (Spalling, Scaling) and Cracking Due to Freeze-Thaw in Below Grade Inaccessible Concrete Areas of Groups 1-3, 5 and 7-9 Structures The Groups *1-3, 5 and 7-9 Structures at WF3 subject to the air-outdoor environment are not exposed to temperatures of 32°F or less of sufficient durations that would cause freeze-thaw aging effects to occur. WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90. Also, air entraining admixture was used in concrete and total air content including that due to use of chemical admixtures generally ranged between 3.5 and .6.5 percent by volume. A review of the WF3 corrective action program was conducted to
determine whether inspection activities.identified evidence of cracking or spalling due to freeze-thaw degradation. This review found no documented conditions of freeze-thaw degradation in exterior concrete structures exposed to an air-outdoor environment. As a result, loss of material and cracking due to freeze-thaw in below-grade inaccessible concrete areas of Groups 1-3, 5 and 7-9 structures are not aging effects requiring management for WF3. Therefore, loss of material and cracking due to freeze-thaw are not aging effects requiring management for the grade inaccessible concrete areas of WF3 Groups 1-3, 5 and 7-9 structures. 2. Cracking Due to Expansion and Reaction with Aggregates in Below Grade Inaccessible Concrete Areas for Groups 1-5 and 7-9 Structures . The Groups 1-5 C!nd 7-9 Structures at WF3 are designed in accordance with ACI 318-63 and/or ACI 318-71 and constructed in accordance with the recommendations in ACI 318-63 and ACI 318-71 using ingredients/materials 3.0 Aging Management Review Results Page 3.5-13 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information conforming to ACI and ASTM standards. The concrete mix-uses Portland cement conforming to ASTM C150, Type II. Concrete aggregates conform to the requirements of ASTM C33. Materials for concrete used in WF3 concrete structures and components were specifically investigated, tested, and examined in accordance with pertinent ASTM standards. Nevertheless, based on ongoing industry operating experience, cracking due to expansion and reaction with aggregates in below-grade inaccessible concrete areas for WF3 Groups 1-5 and 7-9 structures will be managed. WF3 has not identified operating experience for this aging effect; however, WF3 has *conservatively elected to manage this aging effect by the Structures Monitoring Program. 3. Cracking and Distortion due to Increased Stress Levels from Settlement for Below Grade lnaccessfble Concrete Areas of structures for all Groups and Reduction in Foundation Strength, and Cracking, due to Differential Settlement and Erosion of Porous Concrete Subfoundation in .Below Grade Inaccessible Concrete Areas for Groups 1-3, 5-9 Structures The Groups 1-3 and 5-9 Structures at WF3 are founded on a compacted backfill. For .the inaccessible concrete areas of Groups 1-3 and 5-9 Structures at WF3 the safety-related nuclear plant island structures' (NPIS) foundations (basemat) are. integral and are founded on a common rigid reinforced concrete foundation structure for the NPIS that is founded on a compacted shell filter blanket, which is supported by the Pleistocene sediments. The aging effect cracking and distortion due to increased stress levels from settlement is applicable and will be managed by the Structures Monitoring Program. For the WF3 turbine building and other nonsafety-related concrete structures which are founded on compacted structural backfill or soil, the aging effect cracking and distortion due to increased stress levels from settlement is applicable and will be managed by the structures Monitoring Program. Therefore, cracking and distortion due to increased stress levels from settlement is an applicable aging effect for WF3 Groups 1-3 and 5-9 below-grade inaccessible concrete structures, and for the turbine building and other nonsafety-related concrete structures and will be managed by the structures Monitoring Program. The Groups 1-3 and 5-9 Structures at WF3 do not rely on a dewatering system for control of settlement. The WF3 Groups 1-3 and 5-9 concrete* structures do not use porous concrete subfoundations. Therefore, reduction of foundation strength, and cracking due to differential settlement and erosion of porous concrete subfoundations is not an applicable aging effect for WF3 Groups 1-3 and 5-9 below-grade inaccessible concrete structures. Additionally, the WF3 site configuration does not have Group 6 Structures. Therefore, reduction of foundation strength, and cracking due to differential settlement and erosion of
porous concrete subfoundations in below-grade inaccessible concrete areas is not applicable for WF3 Group 6 structures. 3.0 Aging Management Review Results Page 3.5-14 3.5.2.2.2.2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4. Increase in Porosity and Permeability, and Loss of Strength Due to Leaching of Calcium Hydroxide and Carbonation of Below-grade Inaccessible Concrete Areas of Groups 1-:--5 and 7-9 Structures The Groups 1-5 and 7-9 Structures at WF3 are designed in accordance with ACI 318-63 and/or ACI 318-71 and.constructed in accordance with the
recommendations in ACI 318-63 and ACI 318-71 using ingredients/materials conforming to ACI and ASTM standards. The concrete mix uses Portland cement conforming to ASTM C150, Type IL Concrete aggregates conform to the requirements of ASTM C33. Materials for concrete used in WF3 concrete structures and components were specifically investigated, tested, and examined in accordance with pertinent ASTM standards. The type and size of aggregate, slump, cement and additives have been established to produce durable concrete in accordance with ACI. Cracking is controlled through proper arrangement and distribution of reinforcing steel. Concrete structures and concrete components are constructed of a dense, well-cured concrete with an *amount of cement suitable for strength development and achievement of a water-to-cement ratio that is characteristic of concrete having low permeability. This is consistent with the recommendations and guidance provided by ACI 201.2R-77. The below-grade inaccessible concrete areas of Groups 1-5 and 7-9 concrete structures at WF3 are exposed to groundwater which is considered equivalent to a flowing water environment. Therefore, increase in porosity and permeability, and loss of strength due to leaching* of calcium hydroxide and carbonation in below-grade inaccessible concrete areas is an applicable aging effect for the inaccessible concrete of WF3 Groups 1-5 and 7-9 concrete structures. The Structures Monitoring Program manages increase in porosity and permeability, and loss of strength due to leaching of calcium hydroxide and carbonation in below-grade inaccessible concrete areas of WF3 Groups 1-5 and 7-9 concrete structures. Reduction of Strength and Modulus of Concrete Structures due to Elevated Temperature ACI 349 specifies concrete temperature limits for normal operations or any .other long-term period. During normal operation, areas within the Group 1-5 structures at WF3 are maintained oelow a bulk average temperature of 150°F by plant cooling systems. Process piping carrying hot fluid (pipe temperature greater than 200°F) routed through penetrations in the concrete walls by design do not result in .. temperatures exceeding 200°F locally or result in "hot spot" .on the concrete surface. The penetration configuration includes guard pipes and insulation of the process piping to minimize heat transfer from the process pipe to the exterior environment surrounding the process piping. Therefore, change in material properties due to elevated temperature is not an aging effect requiring management for WF3 Group 1-5 Structures. The aging effect "change in material 3.0 Aging Manageme.nt Review Results Page 3.5-15 3.5.2.2.2.3 3.5.2.2.2.4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information properties" is equivalent to the NUREG-1801 aging effect "reduction of strength and modulus." Aging Management of Inaccessible Areas .for Group 6 structures 1. Loss of Material (Spalling, Scaling) and Cracking Due to Freeze-thaw in grade Inaccessible Concrete Areas of Group 6 Structures. The WF3 site configuration does not have Group 6 Structures. Therefore, loss of material (spallihg, scaling) and cracking due to freeze-thaw in below-grade inaccessible c9ncrete ar,eas is not applicable. 2. Cracking Due to Expansion and Reaction with Aggregates in Below-Grade Inaccessible Concrete Areas of Group 6 Structures The WF3 site configuration does not have Group 6 Structures. Therefore, cracking due to expansion and reaction in below-grade inaccessible concrete areas is not applicable. 3. Increase in Porosity and Permeability and Loss of strength due to Leachin*g of Calcium Hydroxide and Carbonation in *inaccessible Are_as of Concrete Elements of Group 6 structures * * '"'* The WF3 site configuration does not have Group 9 Structures. Therefore, increase in porosity and permeability due to leaching of calcium hydroxide and carbonation in below-grade inaccessible concrete areas is not a*pplicable. Cracking due to Stress Corrosion Cracking and Loss of Material due to Pittjng and Crevice Corrosion NUREG-1800 Section 3.5.2.2.2.4 applies to stainless steel liners for concrete or steel tanks. No tanks with stainless steel liners are included in the structural scope of license renewal. However, the corresponding NUREG-1801 items can be compared to the stainless steel liners of other components, such as reactor cavity and containment sump. These liners can be exposed to a fluid environment and may be subject to loss of material. The stainless steel liners, exposed to fluid environment, are not in an environment conducive to stress corrosion cracking (SCC). Consistent with GALL Report Chapter IX, Sections D arid F, the factors necessary to initiate and propagate sec are combined actions of stress (both applied and residual tensile stresses), and .harsh environment (significant presence of halogens, specifically chlorides), attemperature above 140°F (60°C). Although SCC has been observed in stagnant, oxygenated borated water systems at lower temperatures than* this 140°F threshold, all of these instances have identified a significant presence of contaminants (halogens, specifically chlorides) in the failed components. SCC of stainless steel liners is not credible 3.0 Aging Management Review Results Page 3.5-16 3.5.2.2.2.5 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information because they are not exposed to a harsh environment (significant presence of contaminants [halogens, specifically chlorides]), and the normal operating temperature of the fluid environment to which these stainless steel liners are exposed is less than the SCC threshold temperature of, 140°F. Therefore, cracking due to sec is not an aging effect requiring management for the stainless steel liners exposed to fluid environment. The Structures Monitoring Program manages loss of material by periodic inspections. Cumulative Fatigue Damage due to Fatigue TLAAs are evaluated in accordance with 10 CFR 54.21(c) as documented in Section 4 of this application. During the process of identifying TLAAs in the WF3 current licensing basis, no fatigue analyses were identified for component support members, welds, and support anchorage to building structure for Groups 81 .1, 81 .2; and 81 .3. 3.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components See Appendix 8 Section 8.0.3 for discussion of WF3 quality assurance procedures and administrative controls for aging management programs. 3.5.2.2.4 Ongoing Review of Operating Experience See Appendix 8 Section 8.0.4 for discussion of WF.3 operating experience review of aging management programs. 3.5.2.3 Time-Limited Aging Analysis Potential TLAAs identified for structural components and commodities include fatigue analyses for crane rails and structural girders, expansion bellows and refueling bellows assembly, and steel containment vessel penetrations. TLAAs are discussed in Section 4. 3.5.3 Conclusion The structural components and commodities subject to aging management review have been identified in accordance with the criteria of 1 O CFR 54.21. The aging management programs selected to manage-the.effects of aging on structural components and commodities are identified in Section 3.5.2.1 and the following tables. A description of the aging management programs is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the structural components and commodities will be managed such that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.5-17 Table 3.5.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and Ill of NUREG-1801
Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended Discussion .. : .. :::. :, 3.5.1-1 Concrete: dome; Cracking and ISi (IWL) or Structures Yes, if a de-Waterford 3 (WF3)'does not rely on a de-wall; basemat; ring distortion due to Monitoring Program watering system watering system to control settlement. The girders; buttresses, increased stress is relied upon to WF3 containment system does not utilize a Concrete elements, levels from If a de-watering system is control settlement concrete containment. The WF3 primary all settlement containment is a free-standing steel relied upon for control of containment vessel (SCV) which is settlement, then the completely enclosed by the reinforced licensee is to ensure proper functioning of the concrete shield building. TheWF3SCV structure's base foundation is integral with de-watering system the base foundation of the shield building through the period of and is founded on a common rigid extended operation. " reinforced concrete foundation structure for the nuclear plant island structure (NPIS). Since the WF3 primary containment concrete foundation (basemat) is inaccessible, it is exempted from inspection " and ISl-IWL program does not apply. For further evaluation, see Section 3.5.2.2.1.1. 3.0 Aging Management Review Results Page 3.5-18 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-2 Concrete; . Reduction of Structures foundation; foundation strength Program. subfoundation and cracking due to differential If a de-watering system is settlement and erosion of porous relied upon for control of concrete erosion, then the licensee subfoundation is to ensure proper functioning of the de-watering system through the period of extended operation. 3.5.1-3 Concrete: dome; Reduction of A plant-specific aging wall; basemat; ring strength and management program is to girders; buttresses, modulus due to be evaluated. Concrete: elevated containment; wall; temperature (>150°F basemat, Concrete: general; >200°F basemat, concrete local) fill-in annulus 3.5.1-4 BWRonly 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if a de-watering system is relied upon to control settlement Yes, if temperature limits are exceeded Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 does not have a porous concrete subfoundation or rely on a de-watering system to control settlement. The WF3 SCV structure's base foundation is integral with the base foundation of the shield building and is founded on a common rigid reinforced concrete foundation structure for the NPIS. Therefore, the listed aging effects are not applicable to WF3 primary containment foundation. For further evaluation, see Section 3.5.2.2.1.1. The concrete foundation (basemat) of the WF3 primary containment is not exposed to general and local temperatures that exceed the thresholds. Therefore the listed aging effects are not applicable to the concrete foundation (basemat) of the WF3 primary containment. For further evaluation, see Section 3.5.2.2.1.2. Page 3.5-19 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-5 Steel elements Loss of material due ISi (IWE) and 10 CFR Part (inaccessible areas): to general, pitting 50; Appendix J liner; liner anchors; and crevice integral attachments, corrosion Steel elements * (inaccessible areas): suppression chamber; drywall; drywall head; embedded shell; region shielded by diaphragm floor (as applicable) 3.5.1-6 BWRonly 3.5.1-7 BWRonly 3.5.1-8 Prestressing system; Loss of prestress Yes, TLAA tendons due to relaxation, shrinkage, creep; elevated temperature .. 3.0 Aging Management Review Results Further Evaluation -Recommended Yes, if corrosion is indicated from the IWE examinations. Yes, TLAA Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG 1801. The Containment lnservice Inspection -IWE and the Containment Leak Rate Programs manage the loss of material of the inaccessible interior and the exterior surfaces of the Class MC components of the SCV. For further evaluation, see Section 3.5.2.2.1.3 Item 1. WF3 is a PWR with SCV consisting of a cylindrical. wall, a hemispherical dome, and an ellipsoidal bottom encased in reinforced concrete supported on a common rigid reinforced concrete foundation structure for the NPIS. There are no prestressed tendons associated with WF3 primary containment design. For further evaluation, see Section 3.5.2.2.1.4. Page 3.5-20 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-9 Penetration sleeves; Cumulative fatigue Yes, TLAA penetration bellows, damage due to Steel elements: fatigue (only if torus; vent line; vent [current licensing header; vent line basis] CLB fatigue bellows; analysis exists) downcomers, Suppression pool shell; unbraced downcomers, Steel elements: vent header; down comers 3.5.1-10 Penetration sleeves, Cracking due to ISi (IWE) and 10 CFR Part penetration bellows stress corrosion 50, Appendix J cracking .. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, TLAA Yes, detection of aging effects is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801 for containment penetrations that experience cyclic loading. Fatigue analysis for penetration bellows is a TLAA and evaluated in Section 4. For further evaluation, see Section 3.5.2.2.1.5. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. For further evaluation see Section 3.5.2.2 .. 1.6 .. Page 3.5-21 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-11 Concrete Loss of material Further evaluation is (inaccessible areas): (spalling,. scaling) needed for plants that are dome; wall; and cracking due to located in moderate to basemat; ring freeze-thaw severe weathering girders; buttresses,
conditions (weathering Concrete index >100 day-inch/yr) (inaccessible areas): (NUREG-1557). basemat, Concrete (inaccessible areas): dome; wall; basemat 3.0 Aging Management Review Results Further Evaluation Recommended Yes, for plants located in moderate to severe weathering conditions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and protected from the external environments by the shield building's base foundation. Also WF3 is located in a "Negligible" weathering region per Figure 1 of ASTM C33-90. Therefore, the concrete.elements of the SCV foundation (basemat) are not subject to the listed aging effects due to freeze-thaw. For further evaluation, see Section 3.5.2.2.1.7. Page 3.5-22 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-12 Concrete Cracking due to. Further evaluation is (inaccessible areas): expansion from required to determine if a dome; wall; reaction with plant-specific aging basemat; ring aggregates management program is girders; buttresses, needed. Concrete (inaccessible areas): basemat, Concrete (inaccessible areas): containment; wall; basemat, Concrete (inaccessible areas): basemat, concrete fill-in annulus 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if concrete is not constructed as stated function Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. The listed aging. effect for concrete elements of the SCV foundation {basemat) is addressed by Item 3.5.1-43. For further evaluation, see Section 3.5.2.2.1.8. Page 3.5-23 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Further Item Aging Effect/ Aging Management Evaluation Number Component .Mechanism Programs Recommended 3.5.1-13 Concrete Increase in porosity Further evaluation is Yes, if leaching is (inaccessible areas): and permeability; required to determine if a observed in basemat, Concrete loss of strength due plant-specific aging accessible areas (inaccessible areas): to leaching of management program is that impact dome; wall; basemat calcium hydroxide needed. intended function and carbonation 3.5.1-14 Concrete Increase in porosity Further evaluation is Yes, if leaching is (inaccessible areas): and permeability; required to determine if a observed in dome; wall; loss of strength due plant-specific aging accessible areas basemat; ring to leaching of management program is that impact girders; buttresses, calcium hydroxide needed. intended function Concrete and carbonation (inaccessible areas): containment; wall; bas em at 3.0 Aging Management Review Results ., Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building and protected from the external environments by the shield building's base foundation. Since the WF3 primary containment concrete foundation {basemat) is inaccessible, it is exempted from inspection and the ISl.-IWL program does not apply. Accordingly, WF3 does not have an ISl-IWL program. The listed aging effects are addressed by Item 3.5.1-47. For further evaluation, see Section 3.5.2.2.1.9. NUREG-1801 items referencing this Item Number are associated with PWR concrete. containment and WF3 is a steel containment structure. For further evaluation, see Section 3.5.2.2.1.9. Page 3.5-24 Table 3.5. f: Containment, and ComponentSupports, NUREG-1801 Item Aging Effect/ Number Component Mechanism 3.5.1-15 Concrete Increase in porosity (accessible areas): and permeability;
base mat. loss of strength due to leaching of calcium hydroxide and carbonation 3.5.1-16 Concrete Increase in porosity* (accessible areas): and permeability; basemat, Concrete: cracking; loss of co.ntainment; wall; material (spalling, baseimat scaling) due to aggressive chemical attack .. 3.5.1-17 BWRonly. . ' ( 3.0 Aging Management Review Results Aging Management Programs ISi (IWL). ISi (IWL) or Structures Monitoring Program Further Evaluation . Recommended No -No Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Discussion WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the base liner plate of the SCV .and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Accordingly, WF3 does not have an ISl-IWL program. Therefore the listed aging effects are not applicable to WF3. WF3 has ;;in SCV and does not have accessible concrete (basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the scv which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the ba$e liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore the listed aging effects are not applicable to WF3. Page 3.5-25 Table 3.5.1: Containm.ent, Structures and Comp<;>nent Supports,' NUREG-1801
Further Item Aging Effect/ Aging Management Evaluation Number Component Mechanism Programs Recommended 3.5.1-18 Concrete Loss of material ISi (IWL) No (accessible areas): (spailing, scaling) dome; wall; and cracking due to . basemat; ring freeze-thaw girders; buttresses, Concrete (accessible areas): basemat '. 3.5.1-19 Concrete Cracking due to ISl(IWq No (accessible areas): expansion from dome; wall; reaction with basemat; ring .aggregates *girders; buttresses, Concrete (accessible areas): basemat, Concrete (accessible areas) containment; wall; basemat, concrete fill-in annulus 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has an SCV and does not have an accessible concrete {basemat). The WF3 containment concrete is the circular concrete base foundation (basemat) of the SCV which is integral with the shield
building concrete foundation (basemat).
The SCV concrete basemat is below the base liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the program does not apply. Therefore, the listed aging effects are not applicable to WF3. WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete .is the circular concrete bas'e foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basemat is below the base liner plate the SCV and, therefore,
is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore, the listed aging effect is not applicable to WF3. Page 3.5-26 )

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-20 Concrete .Increase in porosity ISi (IWL) (accessible areas): and permeability; dome; wall; loss of strength due basemat; ring to leaching of girders; buttresses, calcium hydroxide Concrete and carbonation (accessible areas): containment; wall; basemat 3.5.1-21 Concrete Cracking; loss of ISi (IWL) (accessible areas): bond; and loss of dome; wall; material (spalling, basemat; ring scaling) due to girders; buttresses; corrosion of reinforcing steel, embedded steel Concrete (accessible areas): basemat; reinforcing steel, Concrete (accessible areas): dome; wall; basemat; reinforcing steel 3.5.1-22 BWRonly. 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-1801 items referencing this Item Number are associated with PWR concrete containment structures and WF3 has *a steel containment structure. Therefore this aging effect is not applicable to WF3. WF3 has an SCV and does not have an accessible concrete (basemat). The WF3 containment concrete is the circular concrete base* foundation (basemat) of the SCV which is integral with the shield building concrete foundation (basemat). The SCV concrete basema\ is below the base liner plate of the SCV and, therefore, is not accessible. Since concrete in this area is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. Therefore, the listed aging effect is not applicab_le to WF3. Page 3.5-27 Table 3.5.1 :. Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism *Programs 3.5.1-23 Concrete Cracking; loss of ISi (IWL} or Structures (inaccessible areas): bond; and loss of Monitoring Program basemat; reinforcing material (spalling, steel, Concrete scaling) due to (inaccessible areas): corrosion of dome; wall; embedded steel basemat; reinforcing steel 3.5.1-24 Concrete Increase in porosity ISi (IWL) or Structures (inaccessible areas): and permeability, Monitoring Program dome; wall; cracking, loss of basemat; ring material (spalling, girders; buttresses, , scaling) due to Concrete aggressive chemical (inaccessible areas): attack basemat, (accessible areas): .. dome; wall; basemat -3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. Sirice the WF3 primary containment concrete foundation (basemat) is ,inaccessible, it is exempted from and the ISl-IWL program does not apply. The listed aging effects are addressed by Item 3.5.1-66. NUREG-1801 items referencing this Item are not associated with the WF3 steel containment structure. WF3 is a PWR with free-standing SCV supported on a common rigid reinforced concrete foundation structure for the NPIS. The SCV structure's base foundation (basemat) is integral with the base foundation of the shield building. Since the WF3 primary containment concrete foundation (basemat) is inaccessible, it is exempted from inspection and the ISl-IWL program does not apply. The listed aging effects are addressed by Item 3.5.1-67. Page 3.5-28 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-25 Concrete Cracking; loss of ISi (IWL) or Structures (inaccessible areas): bond; and loss of Monitoring Program dome; wall; material (spalling, basemat; ring scaling) due to girders; buttresses; corrosion of reinforcing steel embedded steel 3.5.1-26 Moisture barriers Loss of sealing due ISi (IWE) (caulking, flashing, to wear, damage, and other sealants) erosion, tear, surface cracks, or other defects 3.5.1-27 Penetration sleeves; Cracking due to ISi (IWE) and 10 CFR Part penetration bellows, cyclic loading (CLB 50, Appendix J Steel elements: fatigue analysis torus; vent line; vent does not exist) header; vent line bellows; downcomers, Suppression pool shell 3.5.1-28 Personnel airlock, Loss of material due ISi (IWE) and 10 CFR Part equipment hatch, to general, pitting, 50, Appendix J CRD hatch and crevice corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-1801 items referencing this item are associated with PWR concrete containment structures and WF3 has an SCV. Therefore, this aging effect is not applicable to WF3. Consistent with NUREG 1801. The Containment lnservice Inspection -IWE manages the listed aging effect. WF3 is a PWR with a free-standing SCV that does not have a CLB fatigue analysis. However, WF3 does have a CLB fatigue analysis for penetration bellows, which is evaluated in Section 4.6. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Page 3.5-29 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-29. Personnel airlock, Loss of leak ISi (IWE) and 10 CFR Part equipment hatch, tightness due to 50, Appendix J CRD hatch: locks, mechanical wear of hinges, and closure locks, hinges .and mechanisms closure mechanisms 3.5.1-30 Pressure-retaining Loss of preload due ISi (IWE) and 10 CFR Part bolting to self-loosening 50, Appendix J 3.5.1-31 Pressure-retaining Loss of material due ISi (IWE) bolting, Steel to general, pitting, elements: and crevice " downcomer pipes corros.ion .. 3:5.1-32

Prestressing system: Loss of material due ISi (IWL) tendons; anchorage to corrosion
components 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The : Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. Consistent with NUREG-1801. The . Containment lnservice lnspeCtion IWE Program manages the pressure-retaining bolting aging effect. The steel elements: downcomer pipes are associated with BWR Mark I and Mark II containments. WF3 is a PWR. NUREG.:.1801 items referencing this item are associated with concrete containments and applicable to PWR and BWR prestressed concrete containments. WF3 is a PWR with free-standing SCV. There are no prestressed tendons associated with WF3 primary containment design. Therefore this aging effect is not applicable to WF3. Page 3.5-30 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-33 Seals and gaskets Loss of sealing due 10 CFR Part 50, Appendix to wear, damage, J erosion, tear, surface cracks, or other defects 3.5.1-34 Service Level I Loss of coating Protective Coating coatings integrity due to Monitoring and blistering, cracking, Maintenance Program flaking, peeling, delamination, rusting, or physical damage 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Containment Leak Rate Program manages the listed aging effect. Consistent with NU REG 1801. The Protective Coating Monitoring and Maintenance Program manages the listed aging effect. Page 3.5-31 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-35 Steel elements Loss of material due ISi (IWE) and 10 CFR Part (accessible areas): to general, pitting, 50, Appendix J liner; liner anchors; and crevice integral attachments, corrosion Penetration sleeves, Steel elements (accessible areas): drywell shell; drywell head; drywell shell in sand pocket regions; Steel elements (accessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable}, Steel elements (accessible areas): drywell shell; drywell head 3.5.1-36 BWRonly. 3.5.1-37 BWRonly. 3.5.1-38 BWRonly. 3.5.1-39 BWRonly. 3.0 Aging Management Review Results Further Evaluation Recommended No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Containment lnservice Inspection -IWE and Containment Leak Rate Programs manage the listed aging effect. WF3 is a PWR with free-standing SCV and it does not contain a drywell and components associated with sand pocket region. Page 3.5-32 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-40 BWR only. 3.5.1-41 BWRonly. Safety-Relc1tedi:J.nd0ther StnJctures; and CorTiponerit Supports '< 3.5.1-42 Groups 1-3, 5, 7-9: Loss of material Further evaluation i$ Concrete. (spalling, scaling) required for plants that are (inaccessible areas): and cracking due to located in moderate to foundation freeze-thaw severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557) 3.5.1-43 All Groups except Cracking due to Further evaluation is Group 6: Concrete expansion from required to determine if a (inaccessible areas): reaction with plant-specific aging all aggregates management program is needed. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, for plants located in moderate to severe weathering conditions Yes, if concrete is not constructed as stated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion <' ,, WF3 is located in a region where weathering conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the concrete elements are not subject to listed aging effects due to freeze-thaw. For further discussion, see Section 3.5.2.2.2.1 Item 1. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. For further evaluation, see Section 3.5.2.2.2.1 Item 2. Page 3.5-33 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-44 All Groups: Cracking and Structures Monitoring concrete: all distortion due to Program increased stress levels from If a system is settlement relied upon for control of settlement, then the licensee .is to ensure proper functioning of the de-watering system through the periqd of extended operation. BWRonly. 3.5.1-46 Groups 1-3, 5-9: Reduction in . Structures Monitoring . concrete: foundation strength, Program ,, foundation; cracking due to subfoundation differential .If.a system is settlement, erosion relied upon for control of of porous concrete settlemen( then the subfoundation licensee is to ensure . ' proper functioning of the .. de-watering system through.the period .of extended operation. 3.0 Aging Management Review Results Further .Evaluation Recommended
Yes, if a de-watering system is relied upon to control settlement *. Yes, if a de-watering system is relied upon to control settlement Waterford Steam Electric Station, Unit 3 License Renewal Application. Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. WF3 does not rely on a de-watering system to control settlement. For further evaluation, see Section 3.5.2.2.2.1 *Item 3. WF3 does not rely on a de-watering system to control settlement and it does not have porous concrete subfoundation. Therefore, the listed aging effects are not .applicable to WF3 fourdation; subfoundation. For fu.rther evaluation, see Section 3.5.2.2.2. 1 Item 3.
Page 3.5-34 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-47 Groups 1-5, 7-9: Increase in porosity Further evaluation is concrete and permeability; required to determine if a . (inaccessible areas): loss of strength due plant-specific aging exterior above and to leaching of management program is below-grade; calcium hydroxide needed. foundation and carbonation 3.5.1-48 Group 1-5: concrete: Reduction of A plant-specific aging all strength and management program is to modulus due to be evaluated. elevated temperature (>150°F general; >200°F local) 3.5.1-49 Groups 6 -concrete Loss of material Further evaluation is (inaccessible areas): (spalling, scaling) required for plants that are exterior above-and and cracking due to located in moderate to below-grade; freeze-thaw severe weathering foundation; interior conditions (weathering slab index :>.100 day-Inch/yr)* (NUREG-1557) 3.5.1-50 Groups 6: concrete Cracking due to Further evaluation is (inaccessible areas): expansion from required to determine if a all reaction with plant-specific aging aggregates management program is needed. 3.0 Aging Management Review Results Further Evaluation Recommended Yes, if leaching is observed in accessible areas that impact intended function Yes, if temperature limits are exceeded Yes, for plants located in moderate to severe weathering conditions Yes, if concrete is not constructed as stated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. For further evaluation, see Section 3.5.2.2.2.1 Item 4. WF3 concrete in areas for this grouping are not exposed to general and local temperatures that exceed the listed thresholds. Therefore the listed aging effect is not applicable to WF3 structures in this group. For further evaluation, see* Section 3.5.2.2.2.2. WF3 has not identified components for this grouping. Therefore this line item was not used. For fur.ther evaluation, see Section 3.5.2.2.2.3 Item 1. WF3 has not identified components for this grouping. Therefore this line item was not used. For further evaluation, see Section 3.5.2.2.2.3 Item 2. Page 3.5-35 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-51 Groups 6: concrete Increase in porosity Further evaluation is (inaccessible areas): and permeability; required to determine if a exterior above-and loss of strength due plant-specific aging below-grade; to leaching of management program is foundation; interior calcium hydroxide needed. slab and carbonation 3.5.1-52 Groups 7, a*-steel Cracking due to A aging components: tank stress corrosion management program is to liner cracking; Loss of be evaluated. material due to
pitting and crevice corrosion 3.5.1-53 Support members; Cumulative fatigue Yes, TLAA welds; bolted damage due to connections; support fatigue (Only if CLB anchorage to fatigue analysis building structure exists) 3.5.1-54 All groups except 6: Cracking due to Structures Monitoring concrete (accessible expansion from Program areas): all reaction with aggregates. 3.0 Aging Management Review Results *Further Evaluation Recommended Yes, if leaching is observed in accessible areas that impact intended function Yes, plant-specific ' Yes, TLAA No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has not identified components for this grouping. Therefore this'line item was not used. For further evaluation, see Section 3.5.2.2.2.3 ltem3. Consistent with NUREG-11;!01. The Structures Monitoring Program _manages loss of material for this group of components. Cracking due to stress corrosion is not an aging effect requiring management for an environment of water-standing< 140°F (< 60°C). There are no stainless steel tank liners with intended functions exposed to an environment of water-standing> 140°F (> 60°C). For further evaluation, see Section . 3.5.2.2.2.4. No CLB fatigue analysis exists for component supports members, welds, and support anchorage to building structure. For further evaluation, see Section 3.5.2.2.2.5. Consistent with NUREG-1801. The Structures Program manages the listed aging effect. Page 3.5-36
Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-55 Building concrete at Reduction in Structures Monitoring locations of concrete .anchor Program expansion and capacity due to local grouted anchors; concrete grout pads for degradation/ service support base plates induced cracking or other concrete aging mechanisms 3.5.1-56 Concrete: exterior Loss of material due Regulatory Guide 1.127, above-and below-to abrasion; "Inspection of Water-grade; foundation; cavitation Control Structures interior slab Associated with Nuclear Power Plants" or the FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-57 Constant and Loss of mechanical ISi (IWF) variable load spring function due to hangers; guides; corrosion, distortion, stops dirt, overload, fatigue due to vibratory and cyclic thermal loads 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. . This NUREG 1801 line item is specific to Group 6 components. WF3 has not identified components for this grouping. Therefore this line item was not used. Consistent with NUREG-1801. The ISl-IWF Program m*anages the listed aging effect. Page 3.5-37 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Programs 3.5.1-58 Earthen water-Loss of material; Regulatory Guide 1.127, control structures: lpss of form due to "Inspection of Water-dams; erosion, settlement, Control Structures embankments; sedimentation, frost Associated with Nuclear reservoirs; channels; action, waves, Power Plants" or the canals and ponds .currents, surlace FERG/US Army Corp of runoff, seepage Engineers dam inspections and maintenance . programs . 3.5.1-59 Group 6: concrete Cracking; loss of Regulatory Guide 1.127, (accessible areas): bond; and loss of "Inspection ofWater-all material (spalling, Control Structures scaling) due to . Associated with Nuclear corrosion of Power Plants" or the embedded steel FERC/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-60 Group 6: concrete Loss of material Regulatory Guide 1.127, (accessible areas): (spalling, scaling) "Inspection of Water-exterior above-and and cracking due to : Control Structures below-grade; freeze-thaw Associated with Nuclear foundation Power Plants" or the FERC/US. Army Corp of Engineers dam inspections and maintenance programs. 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion This NUREG 1801 line item is specific to Group 6 components. WF3 has not identified components for this grouping. Therefore, this line item was not used. WF3 has not identified components for this grouping. Therefore, this line item was nof used. WF3 has not identified components for this . grouping. Therefore, this line item was not used. Page 3.5-38 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-61 Group 6: concrete Increase in porosity Regulatory Guide 1.127, (accessible areas): and permeability; "Inspection of Water-exterior above-and loss of strength due Control Structures below-grade; to leaching of Associated with Nuclear foundation; interior calcium hydroxide Power Plants" or the slab and carbonation FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-62 Group 6: Wooden. Loss of material; Regulatory Guide 1.127, Piles; sheeting change in material Inspection of Water-properties due to Control Structures weathering, Associated with Nuclear chemical Power Plants" or the degradation, and FERG/US Army Corp of insect infestation Engineers dam inspections repeated wetting and maintenance and drying, fungal programs. decay 3.5.1-63 Groups 1-3, 5, 7-9: Increase in porosity Structures Monitoring concrete (accessible and permeability; Program areas): exterior loss of strength due above and below-to leaching *of grade; foundation calcium hydroxide , and carbonation 3.0 Aging Management Review Results Further Evaluation Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 has not identified components for this grouping. Therefore, this line item was not used. WF3 Structures Monitoring Program manages the listed aging effects for the wooden piles associated with fire pump house. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Page 3.5-39 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-64 1-3, 5, 7-9: Loss of material Structures Monitoring concrete (accessible (spalling, scaling) Program areas): exterior and cracking due to above and below-freeze-thaw grade; foundation 3.5.1-65 Groups 1-3, 5, 7-9: Cracking; loss of Structures Monitoring concrete bond; and loss of Program (inaccessible areas): material (spalling, below-grade scaling) due to exterior; foundation, corrosion of Groups 1-3, 5, 7-9: embedded steel concrete (accessible areas): below-grade exterior; foundation, Grqups 6: concrete (inaccessible areas): all 3.5.1-66 Grpups 1-5, 7, 9: Cracking; loss of Structures Monitoring concrete (accessible bond; and loss of Program areas): interior and material. (spalling, above-grade exterior scaling) due to corrosion of embedded steel 3.0 Aging Management Review Results Further Evaluation . Recommended No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion WF3 is located in a region where weathering .conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the concrete elements associated with these groups are not subjectto the listed aging effects due to freeze-thaw. The Structures Monitoring Program manages the listed aging effects for listed groups except for Group 6. WF3 has not identified components for Group 6; therefore, it is not applicable. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effeqts. Page 3.5-40 *, *,

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-67 Groups 1-5, 7, 9: Increase in porosity Structures Monitoring Concrete: interior; and permeability; Program above-grade cracking; loss of exterior, Groups 1-3, material (spalling, 5, 7-9 -concrete scaling) due to (inaccessible areas): aggressive chemical below-grade attack exterior; foundation, Group 6: concrete (inaccessible areas): all 3.5.1-68 High-strength due to ISi (IWF) structural bolting stress corrosion cracking 3.0 Aging Management Review Results Further Evaluation Recommended No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion The Structures Monitoring Program manages the listed aging effects for listed groups except for Group 6. WF3 has not identified components for Group 6, therefore it is not applicable. NUREG-1801 item referencing this item defines the bolting susceptible to sec as: high strength (actual measured yield strength greater than or equal to 150 kilo-pound per square inch [ksi] or greater than or equal to 1,034 MPa) for structural bolts greater than 1 inch (25 mm) in diameter. Per EPRI 1015078, a periodically wetted environment and the use of thread lubricant containing molybdenum disulfide must be present to initiate sec in high yield-strength bolting. Since Molybdenum disulfide thread lubricants are not used at WF3, for structural bolting applications, sec of high strength structural bolting is not an aging effect requiring management at WF3. Page 3.5-41 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-69 High-strength Cracking due to Structures Monitoring structural bolting stress corrosion Program Note: .ASTM A cracking 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone bSCC. SCC potential need not be evaluated for these bolts. 3.5.1-70 Masonry walls: all Cracking due to Masonry Wall Program restraint shrinkage,* creep, and .aggressive environment 3.5.1-71 Masonry walls: all Loss of material Masonry Wall Program (spalling, scaling) and cracking due to freeze-thaw 3.5.1-72 Seals; gasket; Loss of sealing due Structures \ moisture barriers to deterioration of Program (caulking, flashing, seals, gaskets, and and other sealants)

moisture barriers (caulking, flashing, and other sealants) 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion As defined in this line item, ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. V\(F3 procedures do not identify the use of high strength bolts ASTM A325 and A-490 for structural applications. Therefore, the listed aging effect is not applicable for WF3 high strength bolting. Consistent with NUREG-1801. lhe Masonry Wall Program manages the listed aging effect. WF3 is located in a region where weathering conditions are considered negligible as shown in ASTM C33-90, Fig. 1. Therefore, the masonry walls associated with this line item are not subject to the listed aging effects due to freeze-thaw. Consistent with NUREG-1801, the Structures Monitoring Program manages the listed aging effect. Page 3.5-42

( Table 3.5.1: Containment, Structures and Component Supp9rts, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-73 Service Level I Loss of coating Protective Coating coatings integrity due to Monitoring and blistering, cracking, Maintenance flaking, peeling, delamination, rusting, or physical damage 3.5.1-74 Sliding support Loss of mechanical Structures Monitoring bearings; sliding function due to Program support surfaces

corrosion, distortion, dirt, debris, overload, wear 3.5.1-75 Sliding surfaces Loss of mechanical ISi (IWF) function due to corrosion, distortion, dirt, debris, overload, wear 3.5.1-76 Sliding surfaces: Loss of mechanical Structures Monitoring radial beam seats in function due: to Program BWRdrywell corrosion, distortion, dirt, overload, wear 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Protective Coating Monitoring and Maintenance Program manages the listed aging effect. NUREG-1801 item referencing this item is associated with Lubrite plates. Lubrite plates are not subject to aging management because the listed aging mechanisms are event driven and typically can be avoided though proper design. NUREG-1801 item referencing this item is associated with Lubrite plates. Lubrite plates are not subject to aging management because the listed aging mechanisms are event driven and typically can be avoided though proper design. Loss of material which could cause loss of mechanical function is addressed under Item 3.5.1-77 related to component support members. This NUREG-1801 item is for BWR having a drywall with radial beam seats. WF3 is a PWR with a free-standing SCV containment and does not have radial beam seats. Page 3.5-43 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management' Number Component Mechanism Programs 3.5.1-77 Steel components: Loss of material due Structures Monitoring all structural steel to corrosion Program 3.5.1-78 Steel components: Cracking due to Water Chemistry and fuel pool liner *stress corrosion Monitoring of the spent fuel cracking; Loss of . pool water level in material due to accordance with technical pitting *and crevice specifications and leakage corrosion from the leak chase channels. '\ 3.5.1-79 Steel components: Loss of material due Structures Monitoring piles to corrosion Program 3.5.1-80 Structural bolting Loss of material due Structures Monitoring to general, pitting Program and crevice corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No, unless leakages have been detected through the SFP liner that cannot be accounted for from the leak chase channels No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Consistent with NUREG-1801. The Water Chemistry Control -Primary and Secondary Program and monitoring of the spent fuel pool water level manage loss of material on the spent fuel pool liner. Monitoring spent fuel pool water level in accordance with technical specifications and monitoring leakage from the leak chase channels will also continue during the period of extended operation. Cracking due to stress corrosion is not an aging effect requiring management for an environment oftreatec;I water< 140°F (< 60°C). There are no stainless steel spent fuel components with intended functions exposed to an environment of treated water > 140°F (> Not applicable. WF3 has no steel piles subject to the listed aging effect; therefore this .line *item was not used. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Page 3.5-44 \

Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number

Component Mechanism Programs 3.5.1-81 Structural bolting Loss of material due ISi (IWF) to general, pitting and crevice corrosion 3.5.1-82 Structural bolting Loss of material due Structures Monitoring to general, pitting Program and crevice corrosion 3.5.1-83 Structural bolting Loss of material due Chapter Xl.S7, "Regulatory to general, pitting Guide 1.127, Inspection of and crevice Water-Control Structures corrosion Associated with Nuclear Power Plants" or the FERG/US Army Corp of Engineers dam inspections and maintenance programs. 3.5.1-84 Structural bolting Loss of material due Water Chemistry and ISi to pitting and crevice (IWF) corrosion 3.0 Aging Management Review Results Further Evaluation Recommended No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. Consistent with NU REG-1801. The Structures Monitoring Program manages the listed aging effect. The Structures Monitoring Program manages the listed aging effect. NUREG-1801 item referencing this Item Number is associated with ASME Class MC stainless steel structural bolting in a fluid environment. WF3 does not have this componenU material/environment combination. Therefore this line item was not used. Page 3.5-45 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs. 3.5.1-85 Structural bolting Loss of material due Water Chemistry for BWR to pitting and crevice water, and ISi (IWF) corrosion 3.5.1-86 Structural bolting Loss of material due ISl(IWF) to pitting and crevice corrosion 3.5.1-87 Structural bolting Los.s of preload due ISi (IWF) to self-loosening 3.5.1-88 bolting Loss of preload due Structures Monitoring to self-loosening Program 3.5.1-89 Support members; Loss of material due Boric Acid Corrosion welds; bolted to boric acid Program connections; support corrosion . anchorage to building structure 3.5.1-90 Support members; Loss of material due Water Chemistry for BWR welds; bolted to general (steel water, and ISi. (IWF) connections; support only), pitting, and anchorage to crevice corrosion building structure 3.0 Aging Management Review Results ( Further Evaluation Recommended* No No No No No No Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion NUREG-'1801 item referencing this Item Number is associated with ASME Class 1, 2 and 3 stainless steel structural bolting in a fluid environment for a BWR. WF3 is a PWR and does not have this component/ material/environment combination. Therefore this line item was not used. Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the list.ed aging effect. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. Consistent with NUREG-1801. The Boric Acid Corrosion Program manages the listed aging effect. WF3 is a PWR with SCV. The WF3 Water Chemistry Control -Primary and Secondary and lnservice Inspection -IWF Programs manage the listed aging effect. Page 3.5-46 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-91 Support members; Loss of material due ISi (IWF) welds; bolted to general and connections; support pitting corrosion anchorage to building structure 3.5.1-92 Support members; Loss of material due Structures Monitoring welds; bolted to general and Program* connections; support pitting corrosion anchorage to building structure 3.5.1-93 Support members; Loss of material due Structures Monitoring welds; bolted to pitting and crevice Program connections; support corrosion anchorage to building structure 3.5.1-94 Vibration isolation Reduction or loss of ISi (IWF) elements* isolation function due to radiation hardening, temperature, humidity, sustained vibratory loading 3.0 Aging Management Review Results Further Evaluation Recommended No No No No* Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG-1801. The lnservice Inspection -IWF Program manages the listed aging effect. The Structures Monitoring and Fire Water System Programs manage the listed aging effect. Consistent with NUREG-1801. The Structures Monitoring Program manages the listed aging effect. No ISl-IWF vibration isolation elements have been identified at WF3, however for non-IWF in-scope commodities, the Structures Monitoring Program manages the listed aging effects. Page 3.5-47 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Item Aging Effect/ Aging Management Number Component Mechanism Programs 3.5.1-95 Aluminum, None None galvanized steel and stainless steel support members; welds; bolted connections; support anchorage to building structure exposed to Air*-indoor, uncontrolled 3.0 Aging Management.Review Results Further Evaluation Recommended NA-NoAEM or AMP Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Discussion Consistent with NUREG 1801. Page 3.5-48 Notes for Table 3.5.2-1 through 3.5.2-4 Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line -item. AMP is c_onsistent with NUREG-1801.AMP description. 8. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consist.ent with NUREG-1801 AMP description. D. Component is different, but consistent with material,* environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 501. Steel piles driven into undisturbed soils are unaffected by corrosion. Where steel piles are driven into disturbed soils, operating experience has shown that only minor to moderate corrosion has occurred that would not significantly affect the performance of the component intended function during the license renewal term. The steel piles* are steel casings used as forms for the concrete inside the steel piles. The concrete inside the steel casing is not susceptible to degradation that could impair the ability of the concrete to perform its intended function. Therefore, no aging management is required. 3.0 Aging Management Review Results Page 3.5-49 Table 3.5.2-1: Reactor Building Intended Component Type Function Crane: rails and HS, SNS structural girders Crane -structural HS, SNS girders Penetration bellows EN, HS, PB, SSR Penetration bellows EN, HS, PB, SSR Penetration sleeves EN, HS, PB, MB, SNS, SRE, SSR Penetration sleeves EN, HS, PB, SNS, SRE, SSR Plant stack SSR Steel components: MB,PB, SSR annulus access lock 3.0 Aging Management Review Results Table 3.5.2-1 Reactor Building Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Summary of Aging Management Evaluation Aging Effect Aging Requiring Management NU REG-Table 1 Material Environment Management Programs 1801 Item Item Notes Carbon steel Air-indoor Loss of material Inspection of Vll.B.A-07 3.5.1-52 A uncontrolled
OVHLL Carbon steel Air-indoor Cracking TLAA-metal Vll.B.A-06 3.3.1-1 A uncontrolled fatigue Stainless Air-indoor Cracking TLAA-metal ll.A3.C-13 3.5.1-9 A steel uncontrolled fatigue Stainless Air-indoor Cracking Cll-IWE 11.A3.CP-38 3.5.1-10 A steel uncontrolled Containment Leak Rate Carbon steel Air-indoor Loss of material Cll-IWE ll.A3.CP-36 3.5.1-35 A uncontrolled Containment Leak Rate Stainless Air-indoor None None lll.B2.TP-8 3.5.1-95 c steel uncontrolled Carbon steel Air-indoor Loss of material Structures 111.A 1.TP-302 3.5.1-77 c Monitoring Carbon steel Air-indoor Loss of material Structures llf.A1.TP-302 3.5.1-77 c uncontrolled or Monitoring Air -outdoor Page 3.5-50 Table 3.5.2-1: Reactor Building Intended Component Type Function Material En:vironment Steel components: FB Carbon steel Air-indoor annulus access lock uncontrolled /Air -outdoor Steel components: EN, HS, MB, Carbon steel Air-indoor beams, columns and SNS, SSR uncontrolled plates Steel components: EN, HS, MB, Carbon steel Air with borated beams, columns arid SNS, SSR water leakage plates Steel components: HS, MB, Carbon steel Air-indoor impingement barriers SSR uncontrolled Steel components: HS, MB,
Carbon steel Air with borated impingement barriers SSR water leakage Steel components: HS, SNS Carbon steel Air-indoor jib cranes uncontrolled Steel components: HS, SSR Stainless Exposed to fluid liner plate steel environment Steel components: HS, SSR Stainless Air-indoor liner plate steel uncontrolled Steel components: MB, PB, Carbon steel Air-indoor maintenance. hatch SSR uncontrolled or shield door Air -outdoor Steel components: FB Carbon steel Air-indoor maintenance hatch uncontrolled /Air shield door -outdoor ' 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Fire Protection Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monito.ring Loss of material Structures Monitoring None Nm1e Loss of material Structures Monitoring Loss of material Fire Protection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 . 1801 Item Item Notes Vll.G.A-21 3.3.1-59 c Vll.G.A-22 lll.A4.TP-302 3:5.1-77 A lll.B5.T-25 3.5.1-89 c lll.A4.TP-302 3.5.1-77 A lll.B5.T-25 3.5.1-89 c lll.A4.TP-302 3.5.1-77 A lll.A7.T-23 3.5.1-52 E lll.B5.TP-8 3.5.1-95 c II l.A4. TP-302 3.5.1-77 c Vll.G.A-21 3.3:1-'59 G Vll.G.A-22 Page 3.5-51 Table 3.5.2-1 : Reactor Building Intended Component Type Function Material Environment Steel components: HS, SNS Carbon steel Air -indoor
monorails uncontrolled Steel components: EN, PB, Carbon steel Air-indoor personnel airlock, SNS, SRE, uncontrolled escape lock, SSR construction hatch, maintenance hatch Steel components: FB Carbon steel Air-indoor personnel airlock, uncontrolled /Air escape lock, -outdoor construction hatch, maintenance hatch Steel components: PB,SSR Carbon steel Air-indoor personnel airlock, uncontrolled escape lock, construction hatch; maintenance hatch: locks, hinges, and closure mechanisms Steel components: PB,SSR Carbon steel Air-indoor personnel airlock, uncontrolled escape lock, construction hafoh; maintenance hatch: locks, hinges, and closure mechanisms 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of leak tightness Aging Management Programs Structures Monitoring Cll-IWE Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II 1.A4. TP-302 3.5.1-77 c ll.A3.C-16 3.5.1-28 A Containment Leak Rate Fire Protection Vll.G.A-21 3.3.1-59 c Vll.G.A-22 Cll-IWE ll.84.CP-148 3.5.1-31 A Cll-IWE ll.A3.CP-39 3.5.1-29 A Containment* Leak Rate Page 3.5-52 Table 3.5.2-1 : Reactor Building Intended -Component Type Fun.ction Material Environment Steel components: PB,SSR. Stainless Air-indoor personnel airlock, steel uncontrolled escape lock, construction hatch; maintenance hatch: locks, hinges, and closure mechanisms Steel components: HS, PB, SSR Carbon steel Air-indoor pressure retaining Stainless uncontrolled bolting steel Steel components: MS, PB, SSR Carbon steel Air-indoor pressure retaining uncor:itrolled bolting
Steel component: HS, MB, Carbon steel Air-indoor reactor missile shield SSR uncontrolled Steel component: HS, MB, Carbon steel Air with borated reactor missile shield SSR water leakage Steel component: FLB, HS, Stainless Exposed to fluid reactor cavity seal SNS, SSR steel environment ring and hatches Steel component: FLB, HS, Stainless Air-indoor reactor cavity seal *sNS, SSR steel uncontrolled ring and hatches Steel components: HS, SNS Carbon steel Air-indoor refueling uncontrolled maintenance structure 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of leak tightness Loss of preload Loss of material Loss of material Loss of material Loss of material None Loss of material Aging Management Programs Cll-IWE Waterford Steam Electric Station, Unit 3
License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes ll.A3.CP-39 3.5.1-29 A Containment Leak Rate Cll-IWE ll.A3.CP-150 3.5.1-30 A Containment Leak Rate Cll-IWE ll.A3.CP-148 3.5.1-31 A Structures lll.A4.TP-302 3.5.1-77 c Monitoring Boric Acid lll.B5.T-25 3.5.1-89 c Corrosion Structures lll.A7.T-23 3.5.1-52 E Monitoring None lll.B5.TP-8 3.5.1-95 A Structures lll.A4.TP-302 3.5.1-77 c Monitoring Page 3.5-53 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Steel components: HS, SNS Carbon steel Air-indoor refueling platform uncontrolled equipment assembly and rails Steel elements EN, HS, PB, Carbon steel Air-indoor (accessibfe areas): SRE, SSR uncontrolled liner; liner anchors; integral attachments (steel containment vessel) Steel elements EN, HS, PB, Carbon steel Air with borated (accessible areas): SRE, SSR water leakage liner; liner anchors; integral attachments (steel containment vessel) Steel elements EN, HS, PB, Carbon steel Air-indoor (inaccessible areas): SRE, SSR uncontrolled liner; liner anchors; integral attachments (steel containment vessel) Steel elements: SIS HS, SSR Stainless Exposed to fluid sump screens/ steel environment strainers 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of material Loss of material Loss of material Loss of material Loss of material
Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Inspection of Vll.B.A-07 3.3.1-52 A OVHLL Cll-IWE 11.A2.CP-35 3.5.1-35 A Containment Leak Rate Boric Acid 111.85.T-25 3.5.1-89 A Corrosion* Cll-IWE 11.A2.CP-98 3:5.1-5 A Containment Leak Rate Structures lll.A7.T-23 3.5.1-52 E Monitoring Page 3.5-54 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Steel elements: HS, SSR Stainless Air-indoor SIS sump screens steel uncontrolled I strainers Support members: HS, SSR Carbon steel Air-indoor welds; bolted uncontrolled connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) Support members: HS, SSR Carbon steel Air with borated welds; bolted water leakage connections; support anchorage to building structure (supports and restraints for the steam generators, pressurizer, and reactor coolant pumps) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None .Loss of material ISl-IWF Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes 111.85.TP-8 3.5.1-95 c 111.81 .1.T-24 3.5.1-91 A 111.81 .1.T-25 3.5.1-89 A Page 3.5-55 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Support members: HS, SSR Carbon steel Air-indoor welds; bolted uncontrolled connections; support anchorage to '. building structure (supports and restraints for the reactor pressure vessel) Support members: HS, SSR Carbon steel Air with borated
welds; bolted water leakage. connections; support* anchorage to building structure (supports and restraints for the reactor pressure vessel) Beams, columns, EN,HS, MB, Concrete Air-indoor floor slabs and SNS, SRE, uncontrolled interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and missile shield and barriers) 3.0 Aging Management Review Results / : Aging Effect Aging Requiring : Management Management Programs Loss of material ISl-IWF " Loss of material Boric Acid Corrosion Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) \. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.B1 .1.T-24 3.5.1-91 A : lll.B1.1.T-25 3.5.1-89 A lll.A4.TP-28 3.5.1-67 A Page 3.5-56 Table 3.5.2-1 : Reactor Building Intended Component Type Function Material Beams, columns, EN, HS, MB, Concrete floor slabs and SNS, SRE, interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and missile shield and barriers) Beams, columns, EN, HS, MB, Concrete floor slabs and SNS, SRE, interior walls (primary SSR and secondary shield walls; pressurizer compartments; reactor cavity; and
missile shield and barriers) Concrete (accessible EN, FLB, Concrete areas): shield MB, PB, building; all SNS, SRE, SSR Concrete (accessible EN, FLB, *Concrete areas): shield MB, PB, building; all SNS, SRE, SSR 3.0 Aging Management Review Results Aging Effect Requiring Environment Management Air-indoor Cracking, loss of uncontrolled bond, and loss of material (spalling, scaling) Air-indoor Cracking uncontrolled Air-indoor Cracking uncontrolled or Air -outdoor Air-indoor Increase in uncontrolled or porosity and Air -outdoor permeability, cracking, loss of material (spalling, scaling) Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A4.TP-26 3.5.1-66 A lll.A4.TP-25 3.5.1-54 A lll.A1.TP-25 3.5.1-54 A lll.A4.TP-28 3.5.1-67 A Page 3.5-57 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield. MB, PB, uncontrolled or building; all SNS, SRE,. Air -outdoor SSR Concrete (accessible EN, MB, Concfete Air-indoor areas): refueling SNS, SRE, -uncontrolled canal SSR Concrete (accessible EN, HS, MB, Air-indoor areas): refueling SNS, SRE, uncontrolled canal SSR Concrete (accessible EN, HS, MB, Concrete Air-indoor areas): refueling SNS, SRE, uncontrolled canal SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): Shield MB, PB, uncontrolled _or building wall and SNS, SRE, Air -outdoor dome; interior and. SSR above-grade exterior 3.0 Aging Management Review Results Aging Effect Aging Requiring -Management Management Programs Cracking, loss of Structures bond, and loss of Monitoring material (spalling, . scaling) Cracking Structures Monitoring Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) -r Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A4.TP-26 3.5.1-66 A lll.A5.TP-25 3.5.1-54 A lll.A4.TP-28 3.5.1-67 A lll.A4.TP-26 3.5.1-66 A 111.A1.TP-26 3.5.1-66 A Page 3.5-58 Table 3.5.2-1: Reactor Building Intended Component Type Function Material Environment Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield MB, SNS, uncontrolled or building wall and SRE, SSR Air -outdoor dome; interior and above-grade exterior Concrete (accessible EN, FLB, Concrete Air-indoor areas): shield MB, SNS, uncontrolled or building wall and
SRE, SSR Air -outdoor dome; interior and above-grade exterior Concrete EN, HS,MB,. Concrete Air-indoor (inaccessible areas): SNS, SRE, uncontrolled refueling canal SSR Concrete EN, FLB, Concrete Air-indoor (inaccessible areas): MB, SNS, uncontrolled or shield building; all .. SRE, SSR Air -outdoor Compressible seals PB,SSR Elastomer Air-indoor for annulus lock; uncontrolled escape lock; personnel lock; maintenance hatch Containment FB, PB, SSR Elastomer Air-indoor penetration seals uncontrolled and sealant 3.0 Aging Management Review Results. Aging Effect Requiring Management Increase in porosity and permeability,. cracking, loss of material (spalling, scaling) Cracking Cracking Cracking
Loss of sealing Loss of sealing, Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam El.ectric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A1.TP-28 3.5.1-67 A lll.A1.TP-25 3.5.1-54 A lll.A5.TP-204 3.5.1-43 E .111.A1.TP-204 3.5.1-43 E Containment Leak ll.A3.CP-41 3.5.1-33 A Rate ' Containment Leak .ll.A3.CP-41 3.5.1-33 A Rate Page 3.5-59 Table 3.5.2-1: Reactor Building Intended ..
Component Type Function Material Environment Inflatable seal for PB, SSR Elastomer Air-indoor maintenance hatch uncontrolled shielding door Moisture barrier EN,SSR Elastomer Air-indoor uncontrolled . Service Level I .SNS Coatings Air-indoor coating$ uncontrolled Service Level I SNS Coatings Air-indoor coatings uncontrolled ". 3.0 Aging Management Review Results Aging Effect Re.quiring Management of sealing Loss of sealing *' Loss of coating '. integrity Loss of coating integrity Aging Management Programs Structures Monitoring .Cll-IWE Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1
1801 Item Item Notes 111.A6.TP-7 3.5.1-72 A 3.5.1-26 A . Protective Coating ll.A3.CP-152 3.5.1-34 A Monitoring -and* . Maintenance Protective Coating lll.A4.TP-301 3.5.1-73 A Monitoring and Maintenance .. . Page 3.5-60 Table 3.5.2-2 Nuclear Plant Island Structure Summary of Aging Management Evaluation. Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Program*s Control room ceiling SNS Carbon steel Air-indoor Loss of material Structures support system uncontrolled Monitoring Cooling tower fill/mist HS, SSR Stainless Exposed to fluid Loss of material Structures eliminators steel environment Monitoring Cranes: rails SNS Carbon steel Air-indoor Loss of material Inspection of uncontrolled
OVHLL Cranes: structural SNS Carbon steel Air-indoor Loss of material Inspection of girders uncontrolled OVHLL Cranes: structural SNS Carbon steel Air-indoor Cumulative fatigue TLAA-metal girders uncontrolled damage fatigue* Steel components: EN, SNS, Carbon steel Air-indoor Loss of material Structures all structural steel SRE, SSR uncontrolled or _Monitoring Air -outdoor Steel components: EN, SNS, Galvanized Exposed to fluid Loss of material Structures all structural steel SRE, SSR steel environment Monitoring Steel components: FLB, HS, Stainless Air-indoor None None fuel pool gate SSR steel uncontrolled 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II 1.A3. TP-302 3.5.1-77 A 111.AB.T-23 3.5.1-52 E Vll.B.A-07 3.3.1-52 A Vll.B.A-07 3.3.1-52 A Vll.B.A-06 3.3.1-1 A II l.A3.TP-302 3.5.1-77 c II I.AS. TP-302 lll.A6.TP-221 3.5.1-77 E 111.84.TP-8 3.5.1-95 c Page 3.5-61 Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Intended Requiring Component Type Function Material Environment Management Steel components: FLB, HS, Stainless Exposed to fluid Loss of material fuel pool gate SSR steel environment Steel components: *HS, SSR Stainless Air-indoor None fuel pool liner plate steel uncontrolled Steel components: HS, SSR Stainless Exposed to fluid Loss of material fuel pool liner plate steel environments Steel components: EN, HS, Stainless Exposed to fluid Loss of material CSP liner plate SSR steel environments 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management NU REG-Table 1 Programs 1801 Item Item Notes Water Chemistry lll.A5.T-14 3.5.1-78 A Control -Primary and Secondary Monitoring of spent fuel storage pool level per Tech Spec and monitoring leakage from leak chase channel None 111.84.TP-8 3.5.1-95 c Water Chemistry lll.A5.T-14 3.5.1-78 A Control -Primary and Secondary Monitoring of spent fuel storage pool level per Tech Spec and monitoring leakage from leak chase channel Structures lll.A7.T-23 3.5.1-52 E Monitoring Water Chemistry Control -Primary and Secondary Page 3.5-62 Table 3.5.2-2: Nuclear Plant Island Structure Intended Component Type Function Material Environment Steel components: EN, HS, Stainless Exposed to fluid RWSP liner plate SSR steel environments Steel components: SNS Carbon steel Air-indoor monorails uncontrolled Steel components: EN, SSR Stainless Exposed to fluid vortex breakers/ steel environments screens/strainers Beams, columns, EN, FLB, Concrete Air-indoor floor slabs and pipe HS, MB, uncontrolled chase SNS, SRE, SSR Beams, columns, EN, FLB, Concrete Air-indoor floor slabs and pipe HS, MB, uncontrolled chase SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): all HS, MB, uncontrolled/ Air SNS, SRE, -outdoor/ Soil I SSH Exposed to fluid environment 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring Water Chemistry Control -Primary and Secondary Loss of material Structures Monitoring Loss of material Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Cracking Structures Monitoring Cracking Structures Monitoring Waterford Steam Electric Station, Unit 3. License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A7.T-23 3.5.1-52 E 111.A3.TP-302 3.5.1-77 c lll.A5.TP-302 lll.A7.T-23 3.5.1-52 E lll.A3.TP-26 3.5.1-66 A lll.A5.TP-26 lll.A3.TP-25 3.5.1-54 A lll.A5.TP-25 lll.A3.TP-25 3.5.1-54 A 111.AS.TP-25 Page 3.5-63 Table 3.5.2-2: Nuclear Plant Island Structure r Intended
Component Type Function Material Environment I Concrete (accessible EN, FLB, Concrete Exposed to fluid areas): all HS, MB, environment SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Exposed to fluid areas): all HS, MB, environment SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Soil areas): below-grade HS, MB, exterior; foundation SNS, SRE, SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): interior and HS, MB, uncontrolled or above-grade exterior SNS, SRE, Air -outdoor SSR Concrete (accessible EN, FLB, Concrete Air-indoor areas): interior and HS, MB, uncontrolled or above-grade exterior SNS, SRE, Air -outdoor SSR Concrete (accessible EN, FLB, Concrete Soil areas): NPIS exterior HS, MB, above-and below-SNS, SRE, grade; foundation SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability; Loss of strength Cracking, loss of Structures bond, and loss of *material (spalling, Monitoring scaling) Cracking, loss of Structures bond, and .loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability; cracking; loss of material (spalling, scaling) Cracking and Structures distortion Monitoring Waterford Steam Electric Station, Unil 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-27 3.5.1-65 A lll.A5.TP-27 lll.A3.TP-24 3.5.1-63 A 111.A5.TP-:24 lll.A3.TP-27 3.5.1-65 A lll.A5.TP-27 lll.A3.TP-26 3.5.1-66 A lll.A5.TP-26 lll.A3.TP-28 3.5.1-67 A 111.A5.TP-28 lll.A3.TP-30 3.5.1-44 A lll.A5.TP-30 Page 3.5-64 Table 3.5.2-2: Nuclear Plant Island Structure Intended Component Type Function Material Environment Concrete EN, FLB, Concrete Air-indoor (inaccessible areas): HS, MB, uncontrolled/ Air all SNS, SRE, -outdoor/ Soil/ SSR Exposed to fluid environment Concrete EN, FLB, Concrete Soil (inaccessible areas): HS, MB, exterior above-and SNS, SRE, below-grade; SSR foundation Concrete EN, FLB, Concrete Soil (inaccessible areas): HS, MB, exterior above-and SNS, SRE, below-grade; SSR foundation Masonry walls EN, SNS, Concrete Air-indoor SRE, SSR block uncontrolled Masonry walls FB Concrete Air-indoor block uncontrolled Masonry walls FB Concrete Air-indoor block uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking
Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Masonry Wall Cracking Structures Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes II l.A3. TP-204 3.5.1-43 E lll.A5.TP-204 lll.A3.TP-212 3.5.1-65 A lll.A5.TP-212 lll.A3.TP-29 3.5.1-67 A lll.A5.TP-29 lll.A3.T-12 3.5.1-70 A lll.A5.T-12 Vll.G.A-90 3.3.1-60 c Vll.G.A-91 3.3.1-62 c Page 3.5-65 Table 3.5.2-2: Nuclear Plant Island Structure Aging Effect Intended Requiring Component Type Function Material Environment Management Roof slabs EN, MB, Concrete Air-indoor Cracking, loss of SRE, SSR uncontrolled/ Air bond, and loss of -outdoor material (spalling, scaling) 3.0 Aging Management Review Results Aging Management Programs Structures Moniforing . Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-26 3.5.1-66 A 111.AS.TP-26 Page 3.5-66 Table 3.5.2-3 Turbine Building and Other Structures Summary of Aging Management Evaluation Table 3.5.2-3: Turbine Building and Other Structures Aging Effect Aging Intended Requiring Management Component Type Function Material Environment Management Programs Cranes: rails and SNS Carbon steel Air-indoor Loss of material Inspection of structural girders OVHLL Steel components: EN, SNS, Carbon steel Air-indoor Loss of material Structures all structural steel SRE uncontrolled or Monitoring Air -outdoor Steel components: EN, SNS Galvanized Air-indoor Loss of material Structures Metal siding steel uncontrolled or Monitoring Air -outdoor Steel components: EN Galvanized Air-indoor Loss of material Structures Roof decking or floor steel uncontrolled or Monitoring decking Air -outdoor Steel components: FB Galvanized Air-indoor Loss of material Fire Protection Roof decking or floor steel uncontrolled decking Steel piles SRE Carbon Steel Soil None None Transmission tower, SRE Galvanized Air-indoor Loss of material Structures angle tower, pull-off steel Monitoring tower Beams, columns, EN, SNS, Concrete Air-indoor Cracking, loss of Structures floor slabs SRE uncontrolled bond, and loss of Monitoring material (spalling, scaling) 3.0 Aging Management Review Results Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes G lll.A3.TP-302 3.5.1-77 A lll.A3.TP-302 3.5.1-77 A II l.A3.TP-302 3.5.1-77 A Vll.G.AP-150 3.3.1-58 c I, 501 111.82.TP-6 3.5.1-93 c lll.A3.TP-26 3.5.1-66 A Page 3.5-67 Table 3.5.2-3: Turbine Building and Other Strucrtures '. Aging Effect , Intended '* Requiring Component Type Function Material Environment Management Beams, columns, EN, SNS, Air :-indoor Cracking floor slabs SRE *uncontrolled
Concrete (accessible EN, SNS,
Concrete Air-indoor Cracking areas): all SRE *' uncontrolled or . Air -outdoor Concrete (accessible EN, SNS, Concrete : Soil Cracking, loss.of *' areas): below-grade SRE bond, and loss of exterior; foundation material (spalling, *. scaling) Concrete (accessible EN, SNS,* Concrete Air-indoor Cracking, loss of areas): interior and SRE
uncontrolled or bond, and loss of above-wade exterior . Air -outdoor , material (spalling, scaling) Concrete (accessible EN, SNS, Concrete Air-indoor Increase in interior and SRE uncontrolled or and above-grade exterior. Air -outdoor permeability; cracking; loss of ; material (spalling, scaling) Concrete (accessible EN, SNS,** Concrete Exposed to flt} id, Increase in areas): exterior SRE environment
porosity and above-and .below-. permeability; Loss grade; foundation :of strength Concrete (accessible EN, SNS, Concrete . Soil . . Cracking and areas): exterior SRE distortion above-and below-grade; foundation ., 3.0 Aging Management Review Results Aging Management Programs . Monitoring Structures
Monitoring Structures Monitoring Structures
Monitoring Structures llJ!onitoring Structures . Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-* Table 1 1801 Item Item Notes lll.A3.TP-25 3.5.1-54 A lll.A3.TP-25 3.5.1-54 A lll.A3.TP-27 3.5.1-65 A Ul.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A lll.A3.TP-24 3.5.1-63 A lll.A3.TP-30 3.5.1-44 A Page 3.5-68 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Concrete EN, SNS, Concrete Air-indoor (inaccessible areas): SRE uncontrolled/ Air all -outdoor/ Soil I Exposed to fluid environment Concrete EN, SNS, Concrete Soil (inaccessible areas): SRE exterior above-and -below-grade; foundation Concrete EN, SNS, Concrete Soil (inaccessible areas): SRE exterior above-and below-grade; foundation Duct banks EN, SNS, Concrete Soil SRE Duct banks EN, SNS, Concrete Soil SRE 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity. and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking and Structures distortion Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item .Item Notes I I I .A3. TP-204 3.5.1-43 A lll.A3.TP-212 3.5.1-65 A lll.A3.TP-29 3.5.1-67 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A Page 3.5-69 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Duct banks EN, SNS, Concrete Soil SRE Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Soil switchyard, transformers, tanks, circuit breakers) Foundations (e.g., SNS, SRE Concrete Air -outdoor switchyard, transformers, tanks, circuit breakers) 3.0 Aging Management Review Results Aging Effect Requiring Management Increase in porosity and permeability, cracking, loss of material (spalling, scaling) Cracking and distortion Cracking, loss of bond, and loss of material (spalling, scaling) Increase in porosity and permeability, cracking, loss of material (spalling, scaling) Cracking, loss of bond, and loss of material (spalling, scaling) / Aging Management Programs Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-29 3.5.1-67 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A lll.A3.TP-29 3.5.1-67 A lll.A3.TP-26 3.5.1-66 A Page 3.5-70 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Foundations (e.g., SNS,SRE Concrete Air -outdoor switchyard, transformers, tanks, circuit breakers) Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Air -outdoor hand holes SNS, SRE Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Loss of material Structures (spalling, scaling) Monitoring and cracking Cracking and Structures distortion Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-28 3.5.1-67 A lll.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A I I l.A3. TP-23 3.5.1-64 A lll.A3.TP-30 3.5.1-44 A lll.A3.TP-212 3.5.1-65 A Page 3.5-71 Table 3.5.2-3: Turbine Building and Other Structures Intended Component Type Function Material Environment Manholes and EN, FLB, Concrete Soil hand holes SNS, SRE Manholes and FB Concrete
Air -outdoor hand holes Manholes and FB Concrete Air -outdoor -handholes *-Masonry wall SNS. Concrete Air-indoor
block uncontrolled Masonry wall FB Concrete Air-indoor block uncontrolled Masonry wall FB Concrete Air-indoor block uncontrolled Wooden .Piles SNS Treated wood Soil 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking, loss of Structures material Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection ,Cracking Masonry Wall -,, Cracking Structures Monitoring Fire Protection Loss of material Structures Monitoring Fire Protection Loss of material Structures Change in material Monitoring
properties Waterford Steam Electric Station, Unit 3 _ License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes lll.A3.TP-29 3.5.1-67 A Vll.G.A-92 3.3.1-61 A Vll.G.A-93 3.3.1-62 A-. lll.A3.T-12 3.5.1-70 A Vll.G.A-90 3.3.1-60 c Vll.G.A-91 3.3.1-62 c II 1.A6. TP-223 3.5.1-62 E Page 3.5-72 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE, embedments SSR Anchorage/ SNS, SRE1 embedments SSR Anchorage I SNS, SRE, embedments SSR Anchorage I SNS, SRE, embedments SSR 3.0 Aging Management Review Results Table 3.5.2-4 Bulk Commodities Summary of Aging Management Evaluation Aging Effect Aging Requiring Management Materiiil Environment Management Programs Carbon steel Air-indoor Loss of material Structures uncontrolled or Monitoring Air -outdoor Carbon steel Air-indoor Loss of material Structures uncontrolled or Monitoring Air -outdoor Carbon steel Air-indoor Loss of material ISl-IWF uncontrolled or Air -outdoor Carbon steel Exposed to fluid Loss of material Structures environment Monitoring Carbon steel Air with borated Loss of material 8oricAcid water leakage Corrosion Stainless Exposed to fluid Loss of material Water Chemistry steel environment Control -Primary (temp< 140) and Secondary ISl-IWF Stainless Air-indoor None None steel uncontrolled Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1. TP-302 3.5.1-77 c II l.A3. TP-302 II 1.A4. TP-302 II I.AS. TP-302 111.82.TP-43 3.5.1-92 c 111.81.1.T-24 3.5.1-91 c . 111.81 .2.T-24 lll.A6.TP-221 3.5.1-83 E 111.82.T-25 3.5.1-89 c 111.81.1.TP-10 3.5.1-90 c " 111.82.TP-8, 3.5.1-95 c 111.83.TP-8, 111.84.TP-8, 111.85.TP-8 Page 3.5-73 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Anchorage/ SNS, SRE, Stainless Air with borated embedments SSR steel water leakage Cable tray SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Cable tray SNS, SRE, Carbon steel Air with borated SSR water leakage Cable tray SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Cable tray SNS, SRE, Galvanized Air with borated SSR steel water leakage Cable tray SNS, SRE, Galvanized Air -outdoor SSR steel Conduit SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Conduit SNS, SRE, Carbon steel Air with borated SSR water leakage Conduit SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Conduit SNS, SRE, Galvanized Air with borated SSR steel water leakage Conduit SNS, SRE, Galvanized Air -outdoor SSR steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Leiss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-4 3.5.1-95 c 111.83.TP-4 111.84.TP-4 111.85.TP-4 111.82.TP-43 3.5.1-92 c 111.82.T-25 3.5.1-89 c 111.82.TP-8 3.5.1-95 c 111.82.TP-3 3.5.1-89 c lll.B2.TP-6 3.5.1-93 c 111.82.TP-43 3.5.1-92 c 111.82.T-25 3.5.1-89 c lll.B2.TP-8 3.5.1-95 c lll.B2.TP-3 3.5.1-89 c lll.B2.TP-6 3.5.1-93 c Page 3.5-74 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Constant and SRE, SSR Carbon steel, Air-indoor variable load spring Galvanized uncontrolled hangers; guides; steel stops (Supports for ASME Class 1, 2 and 3 piping and components) Doors EN, FLB, Carbon steel Air-indoor MB, PB uncontrolled Doors EN, FLB, Carbon steel Air -outdoor MB, PB Doors EN, FLB, Carbon steel Air with borated MB, PB water leakage Fire doors FB Carbon steel Air-indoor
uncontrolled Fire doors SRE Carbon steel Air-indoor uncontrolled Fire doors SRE Carbon steel Air with borated water leakage Fire hose reels SRE Carbon steel Air-indoor uncontrolled or Air -outdoor 3.0 Aging Management Review Results Aging Effect Requiring Management Loss of mechanical function Loss of material Loss of.material Loss of material Loss of material Loss of material Loss of material Loss of material Aging Management Programs ISl-IWF Structures Monitoring Structures Monitoring Boric Acid Corrosion Fire Protection Structures Monitoring Boric Acid Corrosion ., Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B1.1:T-28 3.5.1-57 A lll.B1 .2.T-28 lll.B1.3.T-28 lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 lll.A4.TP-302 II l.A5. TP-302 lll.A1 .TP-302 3.5.1-77 c lll.A3.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Vll.G.A-21 3.3.1-59 A lll.A1.TP-302 3.5.1-77 c II l.A3. TP-302 lll.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Fire Water System lll.B2.TP-43 3.5.1-92 E Page 3.5-75 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Fire hose reels SRE Carbon steel Air with borated water leakage Fire protection FB Carbon steel Air-indoor components -uncontrolled
miscellaneous steel including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Fire protection SNS,SRE Carbon steel Air with borated components -water leakage miscellaneous steel including framing steel, curbs, vents and louvers, radiant energy shields, tray covers Manways, hatches, EN, FLB, Carbon steel Air-indoor manhole covers and PB, MB, uncontrolled or hatch covers SNS, SRE, Air -outdoor SSR Manways, hatch.es, EN, FLB, Carbon steel. Air with borated manhole covers and PB, MB, water leakage hatch covers SNS, SRE, SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material Fire Protection Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B2.T-25 3.5.1-89 c Vll.G.A-21 3.3.1-59 c lll.B2.T-25 3.5.1-89 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 II l.A4. TP-302 II I.AS. TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-76 Table 3.5.2-4: Bulk Commodities . Intended Component Type Function Material Environment Mirror insulation SNS Stainless Air-indoor steel uncontrolled Mirror insulation SNS Stainless. Air with borated steel water leakage Missile shields EN, MB Carbon steel Air-indoor uncontrolled or Air -outdoor Missile shields EN, MB Carbon steel Air with borated
water leakage Miscellaneous steel EN, FLB, Carbon steel 'Air -indoor (decking, grating, SNS, SSR
uncontrolled or handrails, ladders, Air -outdoor enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Carbon steel Air with borated (decking, grating, SNS, SSR
water leakage handrails, ladders, enclosure plates, *-stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None, None None None Loss of material Structures ' Monitoring Loss of material Boric Acid Corrosion Loss of material Structures Monitoring Loss bf material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-17 3.3.1-120 c lll.B2.TP-4 3.5.1-95 c lll.A7.TP-302 .3.5.1-77 c ' lll.B2.T-25 3.5.1-89 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 .111.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-77 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Miscellaneous steel EN, FL8, Galvanized Air-indoor (decking, grating,* SNS,SSR steel
uncontrolled handrails, ladders, enclosure plates, platforms, stairs, .. vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Galvanized Air -outdoor (decking, grating, SNS,SSR steel handrails, ladders, enclosure plates, *. platforms, stairs, *' vents and louvers, framing steel, etc) Miscellaneous steel EN, FL8, Galvanized Air with borated * (decking, grating, SNS, SSR steel water leakage
handrails, ladders, enclosure plates, ... stairs, vents and louverf\, framing steel, etc) Miscellaneous steel EN, FLB, Aluminum Air:-indoor (decking, grating, SNS, SS.R ' uncbritrolled handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc)* 3.0 Aging Management Review Results Aging Effect *Aging Requiring
Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None, None " .. '. Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-8 3.5.1-95 c 111.85.TP-8 Ill.A 1.TP-302 3.5.1-77 c II l.A3. TP-302 II l.A4. TP-302 II l.A5. 111.82.TP-3 3:5.1-89 c . 111.82.TP-8 3,5.1-95 c 111.85.TP-8 Page 3.5-78 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Miscellaneous steel EN, FLB, Aluminum Air -outdoor (decking, grating, SNS, SSR handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Miscellaneous steel EN, FLB, Aluminum Air with borated (decking, grating, SNS, SSR water leakage handrails, ladders, enclosure plates, platforms, stairs, vents and louvers, framing steel, etc) Penetration seals FB Carbon steel Air-indoor (end caps) uncontrolled Penetration seals EN, FLB, Carbon steel Air-indoor (end caps) PB, SNS, uncontrolled or SSR Air -outdoor Penetration seals EN, FLB, Carbon steel Air with borated (end caps) PB, SNS, water leakage SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Fire Protection Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-6 3.5.1-93 c lll.B2.TP-3 3.5.1-89 c lll.B5.TP-3 Vll.G.A-21 3.3.1-59 c lll.A1.TP-302 3.5.1-77 c lll.A3.TP-302 lll.A4.TP-302 lll.A5.TP-302 lll.B2.T-25 3.5.1-89 c Page 3.5-79 Table 3.5.2-4: Bulk Commodities Intended Type* Function Material Environment Penetration sleeves FB Carbon steel Air-indoor (mechanical/ uncontrolled electrical not penetrating PC boundary) Penetration sleeves EN, FLB, . Carbon steel Air-indoor (mechanicai/ PB, SNS, uncontrolled or electrical not SSR ' Air_: outd9or
penetrating PC boundary) Penetration sleeves EN, FLB, Carbon steel Air with borated (mechanical/ PB, SNS, water leakage electrical not SSR penetrating PC boundary) Racks, panels, . ' EN, SNS, Carbon steel Air-indoor cabinets and SRE, SSR uncontroiled or enclosures* for Air -outdoor electrical equipment.* and instrumentation Racks, panels, . EN, SNS, Carbon steel
Air with borated cabinets and SRE, SSR water leakage enclosures for electrical equipment and instrumentation 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Fire Protection .. Loss of material
Structures Monitoring .. Loss of material Boric Acid* Corrosion Loss of material Structures Monitoring Loss of material
BoricAcid .. Corrosion .. ... Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.G.A-21 3.3.1-59 c '* -lll.B2.TP-43 3.5.1-92 c lll.B2.T-25 3.5.1-89 c lll.B3.TP-43 3.5.1-92 c lll.B3.T-25 3.5.1-89 c -Page 3S80 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Racks, panels, EN, SNS, Galvanized Air-indoor cabinets and SRE, SSR steel uncontrolled enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Galvanized Air -outdoor cabinets and SRE, SSR steel enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Galvanized Air with borated cabinets and SRE, SSR steel water leakage enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Stainless Air-indoor cabinets and SRE, SSR steel -uncontrolled enclosures for electrical equipment and instrumentation Racks, panels, EN, SNS, Stainless Air -outdoor cabinets and SRE, SSR steel enclosures for electrical equipment and instrumentation 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.83.TP-8 3.5.1-95 c 3.5.1-92 c 111.83.TP-3 3.5.1-89 c 111.83.TP-8 3.5.1-95 c 111.82.TP-6 3.5.1-93 c 111.84.TP-6 Page 3.5-81 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Racks, panels, EN, SNS, Stainless Air with borated cabinets and SRE, SSR steel water leakage enclosures for electrical equipment and instrumentation Tube track SNS, SRE, Carbon steel Air-indoor SSR uncontrolled or Air -outdoor Tube track SNS, SRE, Carbon steel Air with borated SSR water leakage Tube track SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Tube track SNS, SRE, Galvanized Air -outdoor SSR steel Tube track SNS, SRE, Galvanized Air with borated SSR steel water leakage Supports for ASME SRE, SSR Carbon steel Air with borated Class 1, 2 and 3 water leakage piping and components (Constant and variable load spring hangers; guides; stops) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion None None Loss of material Structures Monitoring Loss of material Boric Acid Corrosion Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.B3.TP-4 3.5.1-95 c lll.B2.TP-43 3.5.1-92 c lll.B2.T-25 3.5.1-89 c lll.B2.TP-8 3.5.1-95 c lll.B2.TP-6 3.5.1-93 A lll.B2.TP-3 3.5.1-89 c lll.B1.1.T-25 3.5.1-89 A lll.B1.2.T-25 Page 3.5-82 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Supports for ASME SRE, SSR Galvanized Air with borated Class 1, 2 and 3 steel water leakage piping and components (Constant and variable load spring hangers; guides; stops) Support members; SNS, SRE, Carbon steel Air-indoor welds; bolted SSR uncontrolled or connections; support Air -outdoor anchorage to building structure Support members; SNS, SRE, Carbon steel Air-indoor welds; bolted SSR uncontrolled or connections; support Air -outdoor anchorage to building structure Support members; SNS, SRE, Carbon steel Air with borated welds; bolted SSR water leakage connections; support anchorage to building structure 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material ISl-IWF Loss of material Structures Monitoring Loss of material 8oricAcid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-3 3.5.1-89 A 111.81.2.TP-3 lll.B1 .1.T-24 3.5.1-91 A lll.B1.2.T-24 lll.B2.TP-43 3.5.1-92 A lll.B3.TP-43 111.84.TP-43 111.BS.TP-43 lll.B1.1.T-25 3.5.1-89 A 111.Bt.2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 Page 3.5-83 Table 3.5.2-4: . Bulk Commodities Intended Component Type Function Material Environment Support members; SNS, SRE, Galvanized Air-indoor welds; bolted SSR steel uncontrolled connections; support anchorage to building structure Support members; SRE, SSR Galvanized Air -outdoor welds; bolted steel connections; support anchorage to building structure Support members; SNS, SRE, Galvanized Air with borated welds; bolted SSR steel water leakage connections; support anchorage to building structure Support members; SNS, SRE, Galvanized Air -outdoor welds; bolted SSR steel connections; support anchorage to building Support members; SNS, SRE, Galvanized Air -outdoor welds; bolted SSR steel connections; support anchorage to building structure 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material ISl-IWF Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring Loss of material Structures . Monitoring Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information NUREG-1801
Table 1 Item Item Notes 111.81.1.TP-8 3.5.1-95 A 111.81 .2.TP-8 111.82.TP-8 111.83.TP-8 111.84.TP-8 111.85.TP-8 111.81.1.T-24 3.5.1-91 A 111.81.2.T-24 111.81 .1.TP-3 3.5.1-89 A 111.81-2.TP-3 111.82.TP-3 111.83.TP-3 111.84.TP-3 111.85.TP-3 111.82.TP-6 3.5.1-93 A 111.84.TP-6 111.83.TP-43 3.5.1-92 A 111.85.TP-43 Page .3.5-84 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Support members; SNS, SRE, Stainless Air-indoor welds; bolted SSR steel uncontrolled connections; support anchorage to building structure Support members; SNS, SRE, Stainless Air -outdoor welds; bolted SSR steel connections; support anchorage to building structure Support members; SNS, SRE, Stainless Air with borated welds; bolted SSR steel water leakage connections; support anchorage to building structure Anchor bolts SNS, SRE, Carbon steel Air-indoor SSR uncontrolled Anchor bolts SNS, SRE, Carbon steel Air -outdoor SSR 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Structures Monitoring None None Loss of material Structures Monitoring Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-8 3.S.1-9S A 111.83.TP-8 111.82.TP-6 3.S.1-93 A 111.84.TP-6 111.82.TP-4 3.S.1-9S A 111.83.TP-4 lll.A1.TP-248 3.S.1-80 A II l.A3. TP-248 II l.A4. TP-248 II I.AS. TP-248 I II .A6. TP-248 111.A1.TP-274 3.S.1-82 A lll.A3.TP-274 II l.A4. TP-27 4 I I I .AS. TP-27 4 Page 3.5-85 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Anchor bolts SNS, SRE, Carbon steel Air with borated SSR water leakage Anchor bolts SNS, SRE, Carbon steel Exposed to fluid SSR environment Anchor bolts SNS, SRE, Galvanized Air-indoor SSR steel uncontrolled Anchor bolts SNS, SRE, Galvanized Air*-outdoor SSR steel Anchor bolts SNS, SRE, Galvanized Air with borated SSR steel water leakage -Anchor bolts SNS, SRE, Galvanized Exposed to fluid SSR steel environment Anchor bolts SNS, SRE, Stainless Air-indoor SSR steel uncontrolled Anchor bolts SNS, SRE, Stainless Air -outdoor SSR steel 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Boric Acid Corrosion Loss of material Structures Monitoring None None Loss of material Structures . Monitoring Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring None None Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Applic?tion Technical Information NUREG-1801 .*Table 1 Item Item Notes 111.81.1.T-25 3.5.1-89 c 111.81.2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 lll.A6.TP-221 3.5.1-83 111.82.TP-8 3.5.1-95 c 111.A 1 .TP;.27 4 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 lll.A5.TP-274 111.81 .1.TP-3 3.5.1-89 c 111.81-2.TP-3 111.82.TP-3 -111.83.TP-3 111.84.TP-3 111.85.TP-3 lll.A6.TP-221 3.5.1-83 E 111.82.TP-8 3.5.1-95 c 111.82.TP-6 3.5.1-93 c 111.84.TP-6 Page3.5-86 Table 3.5.2-4: Bulk Gommodities Intended Component Type Function Material Environment Anchor bolts SNS, SRE, Stainless Air with borated SSR steel water leakage Anchor bolts SNS, SRE, Stainless Exposed to fluid SSR steel environment (Temp< 140) High strength SNS, SRE, Carbon steel Air-indoor structural bolting SSR uncontrolled (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Carbon steel Air with borated structural bolting SSR water leakage (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Stainless Air-indoor structural bolting SSR steel uncontrolled (Supports for ASME Class 1, 2, and 3 piping and components) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Loss of material Water Chemistry Control -Primary and Secondary ISl-IWF Loss of material ISl-IWF Loss of material 8oricAcid Corrosion None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.82.TP-4 3.5.1-95 c 111.83.TP-4 111.81.1.TP-10 3.5.1-90 c 111.81.1.TP-226 3.5.1-81 A 111.81 .2.TP-226 111.81.1.T-25 3.5.1-89 A 111.81 .2.T-25 111.81 .1.TP-8 3.5.1-95 A 111.81 .2.TP-8 Page 3.5-87 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material High strength SNS, SRE, Stainless structural bolting SSR steel (Supports for ASME Class 1, 2, and 3 piping and components) High strength SNS, SRE, Carbon steel structural bolting SSR Stainless (Supports for ASME steel Class 1, 2, and 3 piping and components) Structural bolting; SNS, SRE, Carbon steel Structural steel and SSR miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management
Environment Management Programs Air with borated None None water leakage Air-indoor Loss of preload ISl-IWF uncontrolled or Air with borated water leakage Air-indoor Loss of material Structures uncontrolled Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-4 3.5.1-95 A 111.81 .2.TP-4 111.81 .1.TP-229 3.5.1-87 A 111.81 .2.TP-229 lll.A1.TP-248 3.5.1-80 A II l.A3. TP-248 lll.A4.TP-248 lll.A5.TP-248 Page 3.5-88 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Structural bolting; SNS, SRE, Carbon steel Air -outdoor Structural steel and SSR miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, Structural bolting; SNS, SRE, Carbon steel Air with borated Structural steel and SSR water leakage miscellaneous steel connections, including high strength bolting _/ (decking, grating, handrails, ladders, : platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Structures Monitoring . Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 111.85.T-25 3.5.1-89 c Page 3.5-89 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Structural bolting; SNS, SRE, Galvanized Structural steel and SSR steel miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) Structural bolting; SNS, SRE, Galvanized Structural steel and SSR steel miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Environment Management Programs Air-indoor None None uncontrolled Air -outdoor Loss of material Structures Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.85.TP-8 3.5.1-95 c lll.A1.TP-274 3.5.1-82 A 111.A3.TP-274 lll.A4.TP-274 111.A5.TP-274 Page 3.5-90 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Structural bolting; SNS, SRE, Galvanized Air with borated Structural steel and SSR steel water leakage miscellaneous steel connections, including high strength bolting (decking, grating, handrails, ladders, platforms, stairs, vents and louvers, framing steel, etc) Structural bolting SNS, SRE, Carbon steel Air-indoor SSR uncontrolled Structural bolting SNS, SRE, Carbon steel Air-indoor SSR uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring *Management Management Programs Loss of material 8oricAcid Corrosion Loss of material Structures Monitoring Loss of material ISl-IWF Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.85.TP-3 3.5.1-89 c II I.A 1.TP-248 3.5.1-80 A lll.A3.TP-248 II l.A4. TP-248 lll.A5.TP-248 111.82.TP-248 111.83.TP-248 111.84.TP-248 111. 85. TP-248 111.81.1.TP-226 3.5.1-81 A 111.81 .2.TP-226 Page 3.5-91 Table 3.5.2-4: Bulk Commodities Aging Effect Intended Requiring Component Type Function Material Environment Management Structural bolting SNS, SRE, Carbon steel Air -outdoor Loss of material SSR Structural bolting SNS, SRE, Carbon steel Air -outdoor Loss of material SSR Structural bolting SRE, SSR Carbon steel Air -outdoor Loss of material Structural bolting SNS, SRE, Carbon steel Air with borated Loss of material SSR water leakage Structural bolting SNS, SRE, Galvanized Air-indoor None SSR steel uncontrolled 3.0 Aging Management Review Results Aging Management Programs Structures Monitoring Structures Monitoring ISl-IWF 8oricAcid Corrosion None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A lll.A3.TP-274 lll.A4.TP-274 II I.AS. TP-27 4 111.82.TP-274 111.83.TP-274 111.84.TP-274 111.85.TP-274 lll.A6.TP-221 3.5.1-83 E 111.81 .1.TP-235 3.5.1-86 A 111.81 .2.TP-235 111.81 .1.T-25 3.5.1-89 c 111.81 .2.T-25 111.82.T-25 111.83.T-25 111.84.T-25 111.85.T-25 111.81 .1.TP-8 3.5.1-95 c 111.81.2.TP-8 111.82.TP-8 111.83.TP-8 111:84.TP-8 111.85.TP-8 Page 3.5-92 Table 3.5.2-4: Bulk Commodities Aging Effect Intended Requiring Component Type Function Material Environment Management Structural bolting SNS, SRE, Galvanized Air -outdoor Loss of material SSR steel Structural bolting SRE, SSR Galvanized Air -outdoor Loss of material steel Structural bolting SRE, SSR Galvanized Air with borated Loss of material steel water leakage Structural bolting SRE, SSR Stainless Air-indoor None steel uncontrolled Structural bolting SNS, SRE, Stainless Air -outdoor Loss of material SSR steel Structural bolting SRE, SSR Stainless Air -outdoor Loss of material steel 3.0 Aging Management Review Results Aging Management Programs Structures Monitoring ISl-IWF Boric Acid Corrosion None Structures Monitoring ISl-IWF Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-274 3.5.1-82 A I 11.A3. TP-27 4 II l:A4. TP-27 4 lll.A5.TP-274 111.82.TP-274 111.83.TP-274 111.84.TP-274 111.85.TP-274 111.81 .1.TP-235 3.5.1-86 A 111.81 .2.TP-235 111.81.1.TP-3 3.5.1-89 c 111.81-2.TP-3 111.82.TP-3 111.83.TP-3 111.84.TP-3 111.85.TP-3 111.81 .1.TP-8 3.5.1-95 c 111.81 .2.TP-8 111.82.TP-8 111.83.TP-8 111.82.TP-6 3.5.1-93 A 111.84.TP-6 111.82.TP-6 3.5.1-93 E Page 3.5-93 Table 3.5.2-4: Bulk Commodities Intended Component Type
Function Material Environment Structural bolting SRE, SSR Stainless Air with borated steel water leakage Structural bolting SNS, SRE, Carbon steel, Air-indoor SSR Stainless uncontrolled or steel, Air -outdoor or Galvanized Air with borated steel water leak_age Structural bolting SNS, SRE, *Carbon steel, Air-indoor SSR Stainless uncontrolled or steel, Air -outdoor or Galvanized Air with borated steel water leakage Building concrete at SNS, SRE, Concrete Air-indoor locations of SSR uncontrolled or expansion and Air -outdoor grouted anchors; grout pads for ,_ suppor:t base plates Equipment pads/ SNS, SRE, Concrete Air-indoor foundations SSR uncontrolled or Air -outdoor* 3.0 Aging Management Review Results Aging Effect Aging.* Requiring Management
Management Programs None -None Loss of preload Structures Monitoring _Loss of preload ISl-IWF Reduction in Structures concrete anchor Monitoring *.capacity Cracking, loss of Structures bond, and loss of-Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.81.1.TP-4 3.5.1-95 c 111.81.2.TP:..4 111.82.TP-4 111.83.TP-4 111.A1.TP-261 3.5.1-88 A lll.A4.TP-261 lll.A5.TP-261 111.83.TP-261-111.85.TP-261 111.81 .1. TP-229 3.5.1-87 A 111.81 .2.TP-229 . -* 111.81 .1.TP-42 3.5.1-55 A 111.81 .2. TP-42 111.82.TP-42 111.83.TP-42 111.84.TP-42 ' -111.BS.TP-42 .. lll.A1.TP'-26 A lll.A3.TP-26 I I I .A4.TP-26 lll.A5.TP-26 'Page 3.5-94 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Equipment pads/ SNS, SRE, Concrete Air-indoor foundations
SSR uncontrolled or Air -outdoor Equipment pads/ SNS, SRE, Concrete Air-indoor foundations SSR uncontrolled or Air -outdoor Curbs FLB, Concrete Air-indoor SNS,SRE uncontrolled Curbs FLB, SNS, Concrete Air-indoor SRE uncontrolled Curbs FLB, SNS, Concrete Air -: indoor . SRE uncontrolled Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs .Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes lll.A1.TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 111.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 lll.A3.TP-26 3.5.1-66 A lll.A3.TP-28 3.5.1-67 A lll.A3.TP-25 3.5.1-54 A Ill.A 1.TP-26 3.5.1-66 A lll.A3.TP-26 lll.A4.TP-26 lll.A5.TP-26 Page 3.5-95 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor Manways, hatches, FLB, PB, Concrete Air-indoor manhole covers and SNS, SRE, uncontrolled or hatch covers SSR Air -outdoor Manways, hatches, FB Concrete Air-indoor manhole covers and uncontrolled hatch covers Manways, hatches, FB Concrete Air-indoor manhole covers and uncontrolled hatch covers Manways, hatches, FB Concrete Air -outdoor manhole covers and hatch covers Manways, hatches, FB Concrete Air -outdoor manhole covers and hatch covers Missile shields MB Concrete Air-indoor uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking Fire Protection Structures Monitoring Cracking. loss of Fire Protection material Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1. TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 lll.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 Vll.G.A-91 3.3.1-62 A Vll.G.A-90 3.3.1-60 A Vll.G.A-92 3.3.1-61 A Vll.G.A-93 3.3.1-62 A 111.A?.TP-26 3.5.1-66 *A Page 3.5-96 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Missile shields MB Concrete Air-indoor uncontrolled Missile shields MB Concrete Air-indoor uncontrolled Structural fire FB Concrete Air-indoor barriers; walls, Uncontrolled ceilings, floor slabs, curbs, dikes Structural fire FB Concrete Air-indoor barriers; walls, Uncontrolled ceilings, floor slabs, curbs, dikes Structural fire FB Concrete Air -outdoor barriers; walls, ceilings, floor slabs, curbs, dikes Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Cracking -Fire Protection Structures Monitoring Loss of material Fire Protection Structures Monitoring Cracking, loss of Fire Protection material Structures Monitoring Cracking, loss of Structures bond, and loss of Monitoring material (spalling, scaling) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes 111.A?.TP-28 3.5.1-67 A 111.A?.TP-25 3.5.1-54 A Vll.G.A-90 3.3.1-60 A VILG.A-91 3.3.1-62 A Vll.G.A-92 3.3.1-61 A lll.A1.TP-26 3.5.1-66 A lll.A3.TP-26 lll.A4.TP-26 lll.A5.TP-26 Page 3.5-97 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Mate.rial Environment Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor Support pedestals SSR, SNS, Concrete Air-indoor SRE uncontrolled or Air -outdoor Compressible joints SNS, SSR Elastomers Air-indoor and seals uncontrolled or Air -outdoor Compressible joints SNS, SSR Elastomers Exposed to fluid and seals environment Fire stops FB Cerablanket, Air-indoor kaowool uncontrolled blanket, HEMYC, Siltemp fibersil cloth, Thermo-lag, elastomers 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Increase in Structures porosity and Monitoring permeability, cracking, loss of material (spalling, scaling) Cracking Structures Monitoring Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Loss of material, Fire Protection Change in material properties, Cracking/ delamination, separation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes II I.A 1.TP-28 3.5.1-67 A lll.A3.TP-28 lll.A4.TP-28 lll.A5.TP-28 lll.A1.TP-25 3.5.1-54 A lll.A3.TP-25 lll.A4.TP-25 lll.A5.TP-25 lll.A6.TP-7 3.5.1-72 A lll.A6.TP-7 3.5.1-72 A j Page 3.5-98 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Fire wrap FB Cera blanket, Air-indoor Kaowool uncontrolled blanket, HEMYC, Siltemp fibersil cloth, Silicone elastomers, Thermo-lag, elastomers Insulation (includes SNS Fiberglass, Air-indoor jacketing, wire mesh, . calcium uncontrolled tie wires, straps, silicate clips) Insulation (includes IN Fiberglass, Air-indoor jacketing, wire mesh, calcium uncontrolled tie wires, straps, silicate clips) Insulation (includes SNS Aluminum Air-indoor jacketing, wire mesh, uncontrolled tie wires, straps, clips) Insulation (includes SNS Aluminum Air with borated jacketing, wire mesh, water leakage tie wires, straps, clips) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material, Fire Protection Change in material properties, Cracking/ delamination, separation Loss of material, Structures Change in material Monitoring properties Reduced thermal External Surfaces insulation Monitoring resistance None* None Loss of material Boric Acid Corrosion Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item . Item Notes J J Vlll.S-401 3.4.1-64 A .. Vll.J.AP-36 3.3.1-113 c 111.82.TP-3 3.5.1-89 c Page 3.5-99 Table 3.5.2-4: Bulk Commodities Intended Component Type Function Material Environment Insulation (includes SNS Stainless Air-indoor jacketing, wire mesh, steel uncontrolled tie wires, straps, clips) Insulation (includes IN, SNS Stainless Air with borated jacketing, wire mesh, steel water leakage tie wires, straps, clips) Penetration seals FB Elastomers Air-indoor uncontrolled Penetration seals EN, FLB, Elastomers Air-indoor PB, SNS uncontrolled or Air -outdoor Roof membranes EN, SNS Elastomers Air -outdoor Seals and gaskets FLB, PB,
Elastomers Air-indoor (doors, manways SSR uncontrolled or and hatches) Air -outdoor Vibration isolators SNS, SSR Elastomers Air-indoor uncontrolled 3.0 Aging Management Review Results Aging Effect Aging Requiring . Management Management Programs None None None None Increased Fire Protection hardness, shrinkage, loss of strength Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Loss of sealing Structures Monitoring Reduction or loss Structures of isolation function Monitoring Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NUREG-1801 Table 1 Item Item Notes Vll.J.AP-17 3.3.1-120 c lll.B2.TP-4 3.5.1-95 c VII G.A-19 3.3.1-57 A lll.A6.TP-7 3.5.1-72 A lll.A6.TP-7 3.5.1-72 c lll.A6.TP-7 3.5.1-724 A lll.B4.TP-44 3.5.1-94 E Page 3.5-100 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 3.6 ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.1 Introduction This section provides the results of the aging management review for WF3 electrical components which were subject to aging management review. Consistent with the methods described in NEI 95-10, the electrical and l&C aging management reviews focus on commodity groups rather than systems. As discussed in Section 2.5, the following electrical commodity groups requiring aging management review are addressed in this section.
High-voltage insulators
Non-EQ insulated cables and connections -Cable connections (metallic parts) -Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements -Electrical cables not subject to 1 O CFR 50.49 EQ requirements used in instrumentation circuits -Fuse holders (insulation material) -Inaccessible 400 V) cables (e.g., installed underground in conduit, duct bank or direct buried) not subject to 1 O CFR 50.49 EQ requirements
Metal-enclosed bus
Switchyard bus and connections
Transmission conductors and connections Table 3.6.1, Summary of Aging Management Programs for Electrical Components Evaluated in Chapter VI of NUREG-1801, provides the summary of the aging management reviews, and the programs evaluated in NUREG-1801 for the electrical and l&C components. This table uses the format described in the introduction to Section 3. Hyperlinks are provided to the program* evaluations in Appendix B.
3.6.2 Results Table 3.6.2-1, Electrical and l&C Components-Summary of Aging Management Evaluation, summarizes the results of aging management reviews and the NUREG-1801 comparison for electrical and l&C components. 3.6.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The* following sections list the materials, environments, aging effects requiring management, and aging management programs for electrical and l&C components subject to aging management review. Programs are described in Appendix B. Further details are provided in Table 3.6.2-1. 3.0 Aging Management Review Results Page 3.6-1 Materials Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Electrical and l&C components subject to aging management review are constructed of the following materials.
Aluminum
Copper
Cement
Elastomers
Galvanized metals (including steel)
Insulation material -various organic polymers
Porcelain
Steel and steel alloys
Stainless steel
Various metals used for bus and electrical connections Environments Electrical and l&C components subject to aging management review are exposed to the following environments. * *
*
Air -indoor controlled Air -indoor uncontrolled Air -outdoor Air with borated water leakage Heat, moisture, or radiation and air Significant moisture Aging Effects Requiring Management The following aging effects associated with electrical and l&C components require management. * * * *
Change in material properties Increased resistance of connection Increased resistance of connection due to corrosion of connector contact surfaces caused by intrusion of borated water Loss of material Reduced insulation resistance (IR) 3.0 Aging Management Review Results Page 3.6-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Aging Management Programs The following aging management programs will manage the effects of aging on electrical and l&C components.
Boric Acid Corrosion
Metal Enclosed Bus Inspection
Non-EQ Electrical Cable Connections
Non-EQ lnaccessi.ble. Power Gables (2'.. 400 \/) *
Non-EQ Insulated Cables and Connections
Non-EQ Sensitive.Instrumentation Circuits Test.Review 3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 indicates that further evaluation*is necessary for certain aging effects and other issues. Section of NUREG-1800 discusses these aging effects and other issues that require further evaluation. The following sections, corresponding to the in NUREG-1800, explain the WF3 approach to these areas requiring further evaluation. Programs are described in Appendix B. of this application.
3.6.2.2.1 *Electrical Equipment Subject to Environmental Qualification Electrical equipment environmental qualification (EQ) analyses may be TLAAs as defined in 10 CFR 54.3: TLAAs are evaluated in accordance with 10 CFR54.21(c). The evaluation of EC:l' TLAAs are addressed in Sectiort4.4 .. EQ components are subject to replacem*ent based on a qualified life. Therefore, in accordance with 10 CFR 54.21(a)(1)(ii), EQ components are not subject to aging management review. 3.6.2.2.2 Degradation of Insulator Quality due to Presence of Any Salt Deposits and Surface Contamination, and Loss of Material due to Mechanical Wear The discussion in NUREG-1800 concerns effects of these aging mechanisms ori high voltage insulators .. High voltage insulators are subject to aging management review if they are necessary for the alternate AC (AAC) source for SBO, or recovery of offsite power following an SBO. Other high voltage insulators are not subject to aging management review since they do not perform a license* renewal intended function. The high voltage insulators evaluated for WF3 license renewal are those used to support uninsulated, high-voltage electrical components such as transmission conductors and switchyard buses that are in the scope of license renewal. Various airborne materials such as dust, salt and industrial effluents can contaminate insulator surfaces. The buildup of surface contamination is gradual and in most areas washed away by rain. The glazed insulator surface aids this contamination removal. . 3.o Aging Management Review Results Page 3.6-3 Waterford steam Electric Station, Unit 3 License Renewal Application Technical Information A large buildup of contamination enables the conductor voltage to track along the surface more easily and can lead to insulator flashover.
Surface contamination can be a problem in. c;ireas where there are greater. concentrations of airborne particles such as near facilities that discharge soot or near the seacoast where salt spray is prevalent. WF3 is located near the seacoast and
near other sources of airborne particles. However, salt spray buildup is a short-term concern based on local weather conditions (event-driven). Flashover due to salt contamination of insulators is caused .by events, typically storms, regardless of the age of the insulators. This is clearly*not an effect of aging. Surfa.ce contamination is not an applicable aging mechanism for high-voltage insulators at WF3; however,* because of the significance of this event, system walkdowns are performed periodically to do a visual inspection of the swjtchyard high-voltage insulators that are in-scope of license renewal. Therefore, reduced insulation resistance due to surface* contamination is n9t an applicable aging effect for high-voltage insulators at WF3. Loss of material due to mechanical wear is a potential aging effect for strain and suspension insulators subject to movement. Although this aging effect is possible, .industry experience has shown transmission conductors do not normally swing and when subjected to a substantial wind, movement.will*subside after a short period. Wear has not been apparent during routine inspections and is not a credible aging effect.
Wind loading could cause transmission conductor vibration or sway. Wind loading
that can cause a transmission line and insulators to vibrate is considered in the design and.installation of transmission conductors at WF3. Loss of material (wear) and fatigue that cot.lid be caused by transmission conductor vibration or sway are not applicable aging effects in that they would not cause a loss of intended function if left unmanaged for the period of extended operation. There are no aging effects requiring management for WF3 high-voltage insulators. 3.6.2.2.3 Loss of Material due to Wind Induced Abrasion and Fatigue. Loss of Conductor Strength due to Corrosion. and Increased Resistance of Connection due to Oxidation or Loss of Pre-load
Transmission conductors are uninsulated, stranded electrical cables used outside buildings in high voltage applications. The transmission conductor commodity group includes the associated fastening hardware but excludes the high-voltage insulators. Major active equipment assemblies include their associated transmission conductor terminations. Transmission conductors are subject to aging management review if they are necessary for recovery of offsite power following an SBO. At WF3, transmission conductors from the WF3 230 kV switchyard to the startup transformers (3A and 38) support recovery from an SBO. Other transmission conductors are not subject to 3.0 Aging Management Review Results Page 3.6-4*

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information aging management review since they do not perform a license renewal intended function. Switchyard bus is uninsulated, un-enclosed, rigid electrical conductors used in medium-and high-voltage applications. Switchyard bus includes the hardware used to secure the bus to high-voltage insulators. Switchyard bus establishes electrical connections to disconnect switches, switchyard breakers, and transformers. Switchyard bus is subject to aging management review if it is necessary for recovery of offsite power following an SBO. *At WF3, switchyard bus from the 230 kV -switchyard breakers to the 230 kV transmission conductors support recovery from an SBO. Other switchyard bus does not require aging management review !;ince it does* not perform a license renewal intended function. Loss of Material due to Wind Induced Abrasion and Fatigue Wind loading could cause transmission conductor vibration or sway. Wind loading that can cause a transmission line and insulators to vibrate is considered in the

design ahd installation' of transmission conductors at WF3. Loss of material (wear) and fatigue that .could be caused by transmission conducfor vibration or sway are not applicable-aging effects in that they would not *cause"a*loss of intended function if left unmanaged for the period of extended operation.* Switchyard bus is connected to active equipment by short sections of flexible conductors that the rigid bus does not normally vibrate, since it is supported by insulators and ultimately by static, structu*ral such as concrete footings and structural steel. Vibration issues occur early in plant life and as a *result of inadequate design, installation, or maintenance. The flexible conductors withstand the minor vibrations associated with the active switchyard components. Flexible conductors are part of the switchyard bus commodity group. Vibration is not applicable since flexible connectors connecting switchyard bus fo active components eliminate potential for vibration. .* A review of industry operating experience and NRC generic communications related to the aging of transmission conductors ensu.red that iio additional aging effects exist beyond those previously identified. A-review of plant-specific operating experience di_d not identify any unique aging effects for transmission conductors. . -Therefore, loss of material due to wear of transmission conductors is not an aging effect requiring management-at WF3. Therefore, loss of m*aterial due to wear-of switchyard bus is not an aging effect requiring management at WF3.
3.0 Aging Management Review Results Page 3.6-5
Loss of Conductor Strength due to Corrosion ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The aging effeqt loss of conductor strength (corrosion) applies to aluminum conductor steel reinforced (ACSR) transmission conductors. The most prevalent mechanism contributing to loss of conductor strength .of an ACSR transmission conductor is corrosion, which includes corrosion of the steel core and aluminum strand. pitting. For ACSR transmission conductors, degradation begins as a loss of zinc from the galvanized steel core wires. WF3 ACSR conductors are susceptible to environmental influences, such as sulfur dioxide (S02) concentration in the air. When the steel core of an ACSR conductor loses its galvanjze.d co*ating, it wi!I continually corrode causing a in ultimate strength.
Corrosion in ACSR conductors is a very slow acting mechanism, and the corrosion rates depend largely on air quality, which includes suspended particles chemistry, 802 concentration in air, precipitation, fog chemistry and meteorological conditions .. perforr:ned by Ontario Hydroe[ectric showed a 30 percent loss of composite conductor strength of an 80-year-old ACSR conductor due to corrosion. The License Renewal Electrical_ Handbook (LREH) makes statements relative to transmission -_conductor a,ged strengths based upon testi_ng performed Ontario Hydro. This specific conductor construction type at WF3 was included in the Ontario *.Hydroelectric test so the results of this test are representativ_e* of the WF3 230 kV condu9tors. The 336.4 thousand circular mils (MCM) 26/7 ACSR transmission
identified in the .Ontario Hydro electric test, as documented in the companion paper, "Aged ACSR Conductors, Part II-Prediction of Remaining Life," bounds the WF3, transmissio11 conductors. The example presented in LREH
compares a 410 ACSR conductor to the Ontario Hydroelectric Study. The same-comparison method is made here for.the WF3 transmission conductors. There is a set percentage of composite c*onductor strength established at which a trans_missiori conductor is repiaced. As illustrated below, there is ample strength :margin to maintain the WF3 transmissio_n conductor intended function through the of extended operation.
The National Electrical Safety Code (N.ESC) requires that tension on inst.ailed conductors be a maximum of 60 percent of the ultimate conductor strength. _The NESC.also sets the maximum tension a conductor must be designed to withstand under heavy load requirements; which includes consideration of ice, wind and temperature. These requirements are reviewed concerning the specific conductors included in this The fo.llowing evaluation of the conductor type with the smallest ultimate strength margin (4/0 ACSR) in the NESC illustrates the conservative nature of the design of WF3 transmission conductors required for offsite power recovery. 3.0 Aging Management Review Results Page 3.6-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The ultimate strength and the NESC heavy load tension requirements of 410 ACSR are 8350 lbs. and 2761 lbs. respectively. The margin between the NESC Heavy Load and the ultimate strength is 5589 lb.; i.e., there is a 67 percent of ultimate strength margin. The Ontario Hydroelectric study showed a 30 percent loss of composite conductor strength in an 80-year-old conductor. In the case of the 4/0 ACSR transmission conductors, a 30 percent loss of ultimate strength would mean that there would still be a 37 percent ultimate strength margin between what is required by the . NESC and the actual conductor strength. The 4/0 ACSR conductor type has the lowest initial design margin of transmission conductors included in the AMR. This illustrates with reasonable assurance that transmission conduetors will have ample strength through the period of extended operation. A review of industry operating experience and NRC generic communications related to the aging of transmission conductors ensured that no additional aging effects exist beyond those identified. A review of plant-specific operating experience did not identify any unique aging effects for transmission conductors:
Therefore, loss of conductor strength is not an aging effect requiring management for transmission conductors. Increased Resistance of Connection due to Oxidation Corrosion due to surface oxidation for aluminum switchyard bus and connections are not applicable since switchyard bus connections requiring AMR are welded connections. However, the flexible conductors, which are welded to the switchyard bus, are bolted to the other switchyard com*ponents. These* steel and steel:-alloy switchyard component connections are included in the infrared inspection of the 230 kV switchyard connections, which verifies the* effectiveness of the connection design and installation practices. WF3 performs infrared inspections of the 230 kV switchyard connections and transformer yard connections to verify the integrity of the connections at least once a year. This inspection and the absence of plant-specific operating experience verifies that this aging effect is not significant for WF3. Increased connection resistance due to surface oxidation is a potential aging mechanism, but is not significant enough to cause a loss of intended function. The aluminum, and steel alloy components in the switchyard are exposed to precipitation, . but these components do not experience aging effects in this environment, except for *minor oxidation, which does not affect the ability of the connections to perform their intended function. At WF3, switchyard connection surfaces are coated with an oxidant compound (i.e., a grease-type sealant) prior to tightening the connection to
prevent the formation of oxides on the metal surface and to prevent moisture from entering the connections thus reducing the chances of corrosion. Based on operating experience (WF3 and the industry), this method of installation provides a resistant low electrical resistance connection. In addition, the infrared inspection of the 230 kV switchyard verifies that this aging effect is not-significant for WF3. This 3.0 Aging Management Review Results Page 3.6-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information discussion .is applicable for bolted connections of transmission conductors and switchyard bus.
Therefore, increased connection resistance due to general corrosion resulting from oxidation of switchyard connection metal surfaces is not an aging effect requiring management at WF3. Increased Resistance of Connection due to Loss of Pre-load Increased connection resistance due to loss of pre-load (torque relaxation) for switchyard connections is not an aging effect requiring management. The LREH does not list this as an applicable aging effect. The design of the transmission conductor bolted connections precludes torque relaxation as confirmed by specific operating experience. The WF3 operating experience report did not identify any failures of switchyarc;t connections. The design of switchyard bolted connections includes Bellville washers and an anti-oxidant compound (no-ox grease). The type of bolting plate and the use of Bellville washers is the industry standard to preclude torque relaxation. This combined with. the proper sizing of the conductors eliminates the need to consider this aging mechanism; therefore, increased connection resistance due to loss of pre-load is not an aging effect requiring management. This discussion is applicable for bolted connections of transmission conductors and switchyard bus. In-scope transmission conductors at WF3 are to the connections from the 230 kV switchyard to *Startup Transformers 3A and 3B for the off-site pc;>wer recovery paths. WF3 performs infrared inspection of the 230 kV.switchyard connections as part of a repetitive preventive maintenance task to verify the integrity of the connections. These routine inspections and the absence of plant-specific operating experience verifies that this aging effect is not significant for WF3. Based on this information, incr:eased connection resistance due to loss of pre-load of .transmission conductor and switchyard bus connections is not an aging effect requiring management for WF3. . . . There are no applicable aging effects that could cause loss of the intended function of the transmission conductors for the period of extended operation. There are no aging effects requiring management .tor WF3 transmission conductors. and switchyard bus connections. 3.6.2.2.4 Quality Assurance for Aging Management of Nonsafety-Related Components
See Appendix B Section B.0.3 for discussion of WF3 quality assurance procedures
and administrative controls for aging management programs. 3.0 Aging Management Review Results Page 3.6-8 3.6.2.2.5 Ongoing Review of Operating Experience Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information See Appendix B Section B.0.4 for discussion of WF3 operating experience revieVI.'. programs. 3.6.2.3 Time-Limited Aging Analysis The only TLAAs identified for the *electrical and l&C commodity componen_ts are evaluations for environmental qualification (EQ) associated with 1 o* CFR 50.49. The EQ TLAAs are evaluated in Section 4.4. 3.6.3 Conclusion Electrical and l&C components that are subject to aging management review have been identified in accordance with the requirements of 10 CFR 54.21 (a)(1 ). Aging management programs selected to manage aging effects for the electrical and l&C components are identified in Section 3.6.2.1 and in the followingJables. A description of aging management programs is provided in Appendix B of this application, along with the demonstration that the aging effects will. be managed for the period of extended operation. Based on the demonstrations provided in Appendix B, the effects of aging associated with electrical and l&C components will be managed such that there is reasonable assurance the* intended0functions will be maintained consistent with the current licensing basis during the period of extended operation. 3.0 Aging Management Review Results Page 3.6-9 Table' 3.6.1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical. Information Summary .of Aging Management Programs for the EiC Components Evaluated in Chapter VI of NUREG-1801 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-1 Electrical equipment Various aging effects .subject to 1 o CFR 50.49 due to various EQ requirements mechanisms in composed of various accordance with polymeric and metallic 10CFR 50.49 materials exposed to adverse localized environment caused by heat, radiation, o><Ygen, moisture, or voltage .. 3.0 Aging Management Review Results Aging Management Programs EQ is a time-limited aging analysis (TLM) to be evaluated for the period of extended operation. See the Standard Review Plan, Section 4.4, "Environmental Qualification (EQ) of Electrical Equipment," for acceptable methods for meeting the requirements of 10 CFR54.21(c)(1)(i)
and (ii). l See Chapter X.E1, "Environmental Qualification (EQ) of Electric Components, of this report for meeting the requirements of 10 CFR 54.21 (c)(1 )(iii). J Further Evaluation Recommended Discussion Yes, TLAA EQ equipment is not subject to aging management review because the equipment is subject to replacement based on a qualified life. EQ analyses are evaluated as potential TLMs in Section 4.4. See Section 3.6.2.2.1 for further evaluation. Page 3.6-10 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-2 High-voltage insulators Loss of material due to composed of porcelain; mechanical wear malleable iron; aluminum; caused by wind galvanized steel; cement *blowing on exposed to air -outdoor transmission conductors 3.6.1-3 High-voltage insulators Reduced insulation composed of porcelain; resistance due to malleable iron; aluminum; presence of salt galvanized steel; cement deposits or surface exposed to air -outdoor contamination 3.6.1-4 Transmission conductors Loss of conductor composed of aluminum; strength due to steel exposed to air -corrosion outdoor ' 3.6.1-5 Transmission connectors Increased resistance of composed of aluminum; connection due to steel exposed to air -oxidation or loss of pre-outdoor .. load 3.0 Aging Management Review Results Aging Management Programs A plant-specific aging management program is to be evaluated A plant-specific aging management program is to be evaluated for plants located such that the potential exists for salt
deposits or surface contamination (e.g., in the vicinity of salt water bodies or industrial pollution) A plant-specific aging management program is to be evaluated for ACSR A plant-specific aging management program is to be evaluated Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant specific NUREG-1801 aging effects are not applicable td WF3. See Section 3.6.2.2.2 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.2 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Page 3.6-11 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-6 Switchyard bus and of material due to connections composed of wind-induced abrasion; aluminum; copper; Increased resistance of bronze; stainless steel; connection due to galvanized steel exposed oxidation or loss of pre-to air -outdoor load 3.6.1-7 Transmission conductors Loss of material due to composed of aluminum; wind-induced abrasion steel exposed to air -outdoor 3.6.1-8 Insulation material for Reduced insulation electrical cables and resistance due to -connections (including thermal/ therm oxidative terminal blocks, fuse degradation of holders, etc.) Qomposed organics, radiolysis, of various organic and photolysis (UV polymers (e.g., EPR, SR, sensitive materials EPDM, XLPE) exposed to only) of organics; adverse localized radiation-induced environment caused by . oxidation; moisture heat, radiation, or intrusion moisture 3.0 Aging Management Review Results Aging. Management Programs A plant-specific aging management program is to be evaluated A plant-specific aging management program is to be evaluated for AGAR andACSR Chapter Xl.E1, "Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements" Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Further Evaluation Recommended Discussion Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaluation. Yes, plant specific NUREG-1801 aging effects are not applicable to WF3. See Section 3.6.2.2.3 for further evaiuation. No Consistent with NUREG-1801. The Non-EQ Insulated Cables and Connections Program will manage the effects of aging. This program includes inspection of non-EQ electrical and l&C
penetration cables and conn*ections. WF3 EQ electrical and l&C penetration assemblies are covered under the program. Page 3.6-12 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-9 Insulation material for Reduced insulation electrical cables and resistance due to connections used in thermal/ thermoxidative instrumentation circuits degradation of that are sensitive to organics, radiolysis, reduction in conductor and photolysis (UV insulation resistance (IR) sensitive materials composed of various only) of organics; organic polymers (e.g., radiation-induced EPR, SR, EPDM, XLPE) oxidation; moisture exposed to adverse intrusion localized environment caused by heat, radiation, or moisture 3.6.1-10 Conductor insulation for Reduced insulation inaccessible power resistance due to cables greater than or moisture equal to 400 volts (e.g., installed in conduit or direct buried) composed of various organic polymers (e.g., EPR, SR, EPDM, XLPE) exposed to adverse localized environment caused by significant moisture 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.E2, "Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits" Chapter Xl.E3, "Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Non-EQ Sensitive Instrumentation Circuits Test Review Program will manage the effects of aging. This program includes review of calibration results or surveillance findings for instrumentation circuits. No Consistent with NUREG-1801. The Non-EQ Inaccessible Power Cables (;::: 400 V) Program will manage the effects of aging. This program includes inspection and testing of power cables exposed to significant moisture as required. Page 3.6-13 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-11 Metal enclosed bus: cracking, enclosure assemblies crazing, scuffing, composed of elastomers dimensional change exposed to air -indoor, * (e.g. "ballooning" and controlled or uncontrolled "necking"), shrinkage, or air -outdoor discoloration,* hardening and loss of strength due to elastomer degradation 3.6.1-12 Metal enclosed bus: bus/ Increased resistance of connections composed of connection due to the various metals used for loosening -of bolts electrical bus and caused by thermal connections exposed to cycling and ohmic air -indoor, controlled. or heating uncontrolled or air -outdoor 3.6.1-13 Metal enclosed bus: Reduced insulation insulation; insulators resistance due to composed of porcelain; thermal/thermoxidative xenoy; degradation of . organic polymers organics/ exposed to air -indoor, thermoplastics, controlled or uncontrolled radiation-induced or air -outdoor oxidation, moisture/ debris intrusion, and ohmic heating 3.0 Aging Management Review Results Aging Management Programs Chapter Xl.E4, "Metal
Enclosed Bus," or Chapter Xl.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components" Chapter Xl.E4, "Metal Enclosed Bus" .. Chapter Xl.E4, "Metal Enclosed Bus" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Metal. Enclosed Bus Inspection Program will manage the effects of aging. This program includes elastomers associated with flexible boots. No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of interior portions of bus. No Consistent with NUREG-1801. The. Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of interior portions of the bus. Page 3.6-14 Table 3.6.1: EiC Components . Item Aging Effect/ Number Component Mechanism 3.6.1-14 Metal enclosed bus: Loss of material due to external surface of general, pitting, and enclosure assemblies crevice corrosion composed of steel exposed to air -indoor, uncontrolled or air -outdoor 3.6.1-15 Metal enclosed bus: Loss of material due to external surface of pitting and crevice enclosure assemblies corrosion composed of galvanized steel; aluminum exposed to air -outdoor 3.0 Aging Management Review Results \ 5 J Aging Management Programs Chapter Xl.E4, "Metal Enclosed Bus," or Chapter Xl.S6, "Structures Monitoring" Chapter Xl.E4, "Metal Enclosed Bus," or Chapter Xl.S6, "Structures Monitoring" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of exterior portions of the bus. No Consistent with NUREG-1801. The Metal Enclosed Bus Inspection Program will manage the effects of aging. This program includes visual inspection of exterior portions of the bus. Page 3.6-15 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-16 Fuse holders (not part of Increased resistance of active equipment): connection due to metallic clamps chemical composed of various contamination, metals used for electrical corrosion, and connections exposed to oxidation (in an air, air -indoor, uncontrolled indoor controlled environment, increased resistance of connection due to chemical contamination, corrosion and oxidation do not apply); fatigue due to ohmic heating, thermal cycling, electrical transients 3.0 Aging Management Review.Results Aging Management Programs Chapter XI.ES, "Fuse Holders" ' Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No NUREG-1801 aging effects are not applicable to WF3. A review of WF3 documentation indicated that fuse holders utilizing metallic clamps are either located in circuits that perform no license renewal intended function, or part of an active component. Therefore, fuse holders with metallic clamps at WF3 are not subject to aging management review, and do not have aging effects that require an aging management program. Page 3.6-16 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-17 Fuse holders (not part of Increased resistance of active equipment): connection due to metallic clamps fatigue caused by composed of various frequent manipulation metals used for electrical or vibration connections exposed to air -indoor, controlled or uncontrolled 3.6.1-18 Cable connections Increased resistance of (metallic parts) composed connection due to of various metals used for thermal cycling, ohmic electrical contacts heating, electrical to air -indoor, transients, vibration, controlled or uncontrolled chemical or air -outdoor contamination, corrosion, and oxidation 3.0 Aging Management Review Results Aging Management Programs Chapter XI.ES, "Fuse Holders" .No aging management program is required for those applicants who can demonstrate these fuse holders are located in an environment that does not subject them to environmental aging mechanisms or fatigue caused by frequent manipulation or vibration Chapter Xl.E6, "Electrical Cable Connections Not Subject to 10 CF.R 50.49 Environmental Qualification Requirements" Further Evaluation Waterford.Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No NUREG-1801 aging effects are not applicable to WF3. A review of WF3 documents indicated that fuse holders utilizing metallic clamps are either located in circuits that perform no license renewal intended function, or part of an active component. Therefore, fuse holders with metallic clamps at WF3 are not subject to aging management review, and do not have aging effects that require an aging management program. No Consistent with NUREG-1801. The one-time inspection program (Non-EQ Electrical Cable Connections) will verify the absence of aging effects requiring management. Page 3.6-17 Table 3.6.1: EiC Components Item Aging Effect/ Number Component Mechanism 3.6.1-19 Connector contacts for Increased resistance of electrical connectors connection due to exposed to borated water corrosion of connector leakage composed of contact surfaces Various metals used for caused by intrusion of electrical contacts borated water exposed to Air with borated water leakage 3.6.1-20 Transmission conductors Loss of conductor composed of aluminum strength due to exposed to air -outdoor corrosion 3.6.1-21 Fuse holders (not part of None a larger assembly): insulation material, metal . enclosed bus: external surface of enclosure assemblies composed of insulation material: bake lite;. phenolic melamine or ceramic; molded polycarbonate; other, galvanized steel; aluminum, steel exposed to air -indoor, controlled or uncontrolled 3.0 Aging Management Review Results .,-\.. Aging' Management Programs Chapter Xl.M10, "Boric Acid Corrosion" Further Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Recommended Discussion No Consistent with NUREG-1801. The Boric Acid Corrosion Program will manage the effects of aging. None -for Aluminum . No NUREG-1801 materi.al and aging Conductor Aluminum Alloy effects are not applicable to WF3. Reinforced (ACAR) None NA-NoAEM or Consistent with NUREG-1801. AMP ,. ' Page 3.6-18 r ( i \, ' ' '

Notes for Table 3.6.2-1 Generic Notes Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information A. Consistent with component, material, environment, agirig effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. 8. Consistent with component, material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. C. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP is consistent with NUREG-1801 AMP description. D. Component is different, but consistent with material, environment, aging effect and aging management program listed for NUREG-1801 line item. AMP has exceptions to NUREG-1801 AMP description. E. Consistent with NUREG-1801 material, environment, and aging effect but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F. Material not in NUREG-1801 for this component. G. Environment not in NUREG-1801 for this component and material. H. Aging effect not in NUREG-1801 for this component, material and environment combination. I. Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J. Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant-Specific Notes 601. WF3 fuse holders with metallic fuse clips are either part of an active component or located in circuits that perform no license renewal intended function and thus are not subject to aging management review. Therefore, fuse holders (metallic clamp) at WF3 do not have aging effects that require an aging management program. 3.0 Aging Management Review Results Page 3.6-19 Table 3.6.2-1 Electrical and l&C Components Summary of Aging Management Evaluation Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 3.6.2-1 : Electrical and l&C Aging E.ffect . Aging Intended Requiring. Management NU REG-Table 1 Component Type Function Material Environment Management Programs 1801 Item Item Notes Cable connections CE Various Air-indoor Increased Non-EQ Electrical Vl.A.LP-30 3.6.1-18 A (metallic parts) metals used* controlled or resistance of

Cable Connections Vl.A-1 for electrical uncontrolled or connection (LP-12) connections Air -outdoor Insulation material IN Insulation Heat, moisture, Reduced insulation Non-EQ Insulated Vl.A.LP-33 3.6.1-8 A for electrical._cables material-or radiation and resistance (IR) Cables and Vl.A-2 and connections various air Connections (L-01) (including terminal organic blocks, fuse holders, polymers etc.) not subject to 1 OCFR50.49 EQ requirements '. (includes non-EQ . electrical and l&C penetration conductors and connections) Insulation material IN Insulation Heat, moisture, Reduced insulation Non-EQ Sensitive VIALP-34 3.6.1-9 A for electrical cables material-or radiation and resistance (IR) Instrumentation Vl.A-3 not subject to 10 various air Circuits Test (L-02) CFR 50.49 EQ organic Review requirements used in polymers instrumentation circuits 3.0 Aging Management Review Results Page 3.6-20 /' /

Table 3.6.2-1 : Electrical and l&C Components -Intended Component Type Function Material Environment Fuse holders (not IN Insulation Air-indoor part of active material-controlled or equipment): various uncontrolled insulation material organic polymers Fuse holders (not CE Various Air-indoor part of active metals used controlled or equipment): metallic for electrical uncontrolled clamps connections Fuse holders (not CE Various Air-indoor part of active metals used controlled or equipment): metallic for electrical uncontrolled clamps connections High voltage IN Porcelain, Air -outdoor insulators (high galvanized voltage insulators for metal, cement SBO recovery) High voltage IN Porcelain, Air -outdoor insulators (high galvanized voltage insulators for metal, cement SBO recovery) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None < None None None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-24 3.6.1-21 A Vl.A-7 (LP-02) Vl.A.LP-31 3.6.1-17 I, 601 Vl.A-8 (LP-01) Vl.A.LP-23 3.6.1-16 I, 601 Vl.A-8 (LP-01) Vl.A.LP-32 3.6.1-2 I Vl.A-10 (LP-11) Vl.A.LP-28 3.6.1-3 I Vl.A-9 (LP-07) Page 3.6-21 \ Table 3.6.2-1: Electrical and l&C Components Intended Component Type Function Material Environment Conductor insulation IN Insulation Significant for inaccessible material-moisture power cables various 400 V) not subject organic to 10 CFR 50.49 EQ polymers; requirements paper and oil Metal enclosed bus: CE Various Air -indoor, bus/connections metals used controlled or for electrical uncontrolled or bus and Air -outdoor connections Metal enclosed bus: CE Elastomers Air -indoor, enclosure controlled or assemblies uncontrolled or Air -outdoor Metal enclosed bus: CE Galvanized Air -indoor, external surface of steel; controlled or enclosure aluminum uncontrolled assemblies Metal enclosed bus: CE Galvanized Air -outdoor external surface of steel; enclosure aluminum assemblies Metal enclosed bus: CE Steel Air -indoor, external surface of controlled enclosure assemblies 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Reduced insulation Non-EQ resistance (IR) Inaccessible Power Cables 400 V) Increased Metal Enclosed connection Bus Inspection resistance Change in material Metal Enclosed properties Bus Inspection None None Loss of material Metal Enclosed Bus Inspection None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-35 3.6.1-10 B Vl.A-4 (L-03) Vl.A.LP-25 3.6.1-12 A Vl.A.LP-29 3.6.1-11 A Vl.A.LP-41 3.6.1-21 A Vl.A.LP-42 3.6.1-15 A Vl.A.LP-44 3.6.1-21 A Page 3.6-22 Table 3.6.2-1: Electrical and l&C Components Intended Component Type Function Material Environment Metal enclosed bus: CE Steel Air -indoor, external surface of uncontrolled or enclosure Air -outdoor assemblies Metal enclosed bus: IN Porcelain; Air -indoor, insulation; insulators insulation controlled or material-uncontrolled or various Air -.outdoor organic polymers Switchyard bus and CE Aluminum, Air -outdoor connections steel, steel (switchyard bus for alloy SBO recovery) Transmission CE Aluminum Air -outdoor conductors (transmission conductors for SBO recovery) Transmission CE Aluminum Air -outdoor conductors (transmission conductors for SBO recovery) 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs Loss of material Metal Enclosed Bus Inspection Reduced insulation Metal Enclosed resistance Bus Inspection None None None None None None Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A.LP-43 3.6.1-14 A Vl.A.LP-26 3.6.1-13 A Vl.A.LP-39 3.6.1-6 I Vl.A-15 (LP-9) --Vl.A.LP-46 3.6.1-4 c Vl.A-16 (LP-08) Vl.A.LP-47 3.6.1-7 I Vl.A-16 (LP-08) Page 3.6-23 Table 3.6.2-1 : Electrical and l&C Components Intended Component Type Function Material Environment Transmission CE Aluminum, Air -outdoor connectors steel, steel (transmission alloy connectors for SBO recovery) Connector contacts CE Various Air with borated for electrical metals used water leakage connector§ exposed for electrical to borated water contacts leakage 3.0 Aging Management Review Results Aging Effect Aging Requiring Management Management Programs None None Increased Boric Acid resistance of Corrosion connection due to corrosion bf connector contact surfaces caused by intrusion of borated water Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information NU REG-Table 1 1801 Item Item Notes Vl.A:LP-48 3.6.1-5 I Vl.A-16 (LP-08) Vl.A.LP-36 3.6.1-19 A Vl.A-5 (L-04) Page 3.6-24

r [ 4.0 TIME-LIMITED AGING ANALYSES Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section provides the results of evaluations of time-limited aging analyses (TL,A.As) and exemptions based on a TLAA. This s.ection evaluates each identified TLAA in accordance with 10 CFR 54.21(c). Section 4.1 provides the 10 CFR Part 54 definition of TLAAs and requirements for evaluation of TLAAs and summarizes the process used for identifying .and evaluating TLAAs and exemptions. Subsequent sections of this chapter describe the evaluation of TLAAs within the following categories. *
Section 4.2, Reactor Vessel Neutron Embrittlement
Section 4.3, Metal Fatigue .
Section 4.4, Environmental Qualification (EQ) of Electric Equipment
Section 4.5, Concrete C.ontainment Tendon Prestress
Section 4.6, Containment Liner Plate, Metal Containments, and Penetrations Fatigue Analysis
Section 4.7, Other Plant-Specific TLAAs* References for Section 4 are provided in Section 4.8. 4.1* IDENTIFICATION OF TIME-LIMITED AGING ANALYSES Time-limited aging analyses are defined in 10 CFR 54.3. Time-limited aging analyses, for the purposes of this part, are those licensee calculations and analyses that: (1) Involve systems, structures, and components within the scope of license renewal, as delineated in § 54.4(a); * (2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, for example, 40 years; (4) Were determined to be relevant by the licensee in making a safety determination; * (S) Involve conclusions or provide the basis for conclusions related to the capability
of the system, structure, and component to perform its intended functions, as delineated in§ 54.4(b); and (6) Are contained or incorporated by reference in the CLB. 4.0 Time-Limited Aging Analyses Page 4.1-1 Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Section 10 CFR 54.21(c) requires a list of TLAAs be included in an application for a renewed license. Section 10 CFR 54.21 (c)(2) requires a list of exemptions granted pursuant to 1 O CFR 50.12 that are based on a TLAA to be in the application for a renewed license. § 54.21 Contents of application -technical information. (c) An evaluation of time-limited aging analyses. (1) A list of time-limited aging analyses, as defined in§ 54.3, must be provided. The applicant shall demonstrate that-(i) The analyses remain valid for the period of extended operation; (ii) The analyses have been projected to the end of the period of extended operation; or (iii) The effects of aging on the intended function(s) will be adequately managed for the period of extended operation. (2) A list must be provided of plant-specific exemptions granted pursuant to 10 CFR 50.12 and in effect that are based on time-limited aging analyses as defined in § 54.3. The applicant shall provide an evaluation that justifies the continuation of these exemptions for the period of extended operation. 4.1.1 Identification of TLAAs The process for identifying time-limited aging analyses is consistent with the guidance provided in NEI 95-10 (Ref. 4-1). Calculations and analyses that potentially meet the definition of a TLAA in 10 CFR 54.3 were identified by searching current licensing basis documents including the following. -* Final Safety Analysis Report (FSAR)
Technical Specifications and Bases
Technical Requirements Manual *
Facility Operating License
Fire protection program documents
lnservice inspection procedures _
Relevant NRC safety evaluation reports (SERs)
Relevant Westinghouse Commercial Atomic Power reports (WCAPs)
Docketed licensing correspondence Industry documents that list generic TLAAs were also reviewed to provide additional assurance of the_ completeness of the identification of WF3 TLMs. These documents included NEI 95-1 O (Ref. 4-1); NUREG-1800 (Ref. 4-2); and EPRI Report TR-105090 (Ref. 4-4). Table 4.1-1 provides a summary listing of the TLAAs applicable to WF3. Table 4.1-2 provides a comparison of the WF3 TLAAs to the potential TLAAs identified in NUREG-1800. 4.0 Time-Limited Aging Analyses Page 4.1-2 )

4.1.2 Identification of Exemptions Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Exemptions for WF3 were identified through a review of the FSAR, the operating license, the Technical Specifications, NRG SERs, ASME Section XI Program documentation, fire protection program documents, NRG Agencywide Documents Access and Management System (ADAMS) database, and docketed correspondence. There are no exemptions that were granted in accordance with 1 O GFR. 50 .12 that are based on a TLAA, regardless of whether the exemptions remain in effect for the period of extended operation. 4.0 Time-Limited Aging Analyses Page 4.1-3 TLAA Description Table 4.1-1 List of TLAAs **_Reactor Ve$$e1 Embrittlement Analy!;es Reactor vessel fluence Upper-shelf energy Pressurized thermal shock Pressure-temperature limits Low temperature overpressure protection (LTOP) setpoints . MetalFatigue , , ,, .r* Reactor vessel Reactor vessel internals Pressurizer Steam generators Control element drive mechanisms Reactor coolant pumps Reactor coolant system Class 1 piping Non-class 1 piping and in-line components Flexible connections and expansion joints 4.0 Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information . Resolution Option .. Analysis projected 10 CFR 54.21(c)(1)(ii) Analysis projected 10 CFR 54.21(c)(1)(ii) Analysis projected 10 CFR 54.21 (c)(1 )(ii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) . ' .'.* Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Aging effect managed 10 CFR 54.21 (c)(1 )(iii) Analysis remains valid 10 CFR 54.21(c)(1)(i) Analysis remains valid 10 CFR 54.21(c)(1)(i) LRA Section 4.2 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.3 4.3.1.1 4.3.1.2 4.3.1.3 4.3.1.4 4.3.1.5 4.3.1.6 4.3.1.7 4.3.2.1 4.3.2.2 Page 4.1-4 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 4.1-1 (Continued) List of TLAAs TLAA Description Non-Class 1 heat exchangers with fatigue analysis Effects of reactor water environment on fatigue life Resolution Option Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21(c)(1)(iii) qualification Equipment ;"< '" . *, ' .,,,.,,, . -.* Environmental qualification analyses of electrical equipment cbrltrete '* ... ,., . *' Concrete containment tendon prestress analysis r Containment vessel design Containment penetration bellows analyses . *** .. ' . "' ,. .. *.**-.. Other Plant-Specific.TLAAs' * ' . . . ' Crane load cycle analysis Leak-before-break analysis Postulation of high energy line break (HELB) locations Reactor vessel internals evaluations (other than fatigue) 4.0 Time-Limited Aging Analyses *':,, Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) ,,, ,i .... ' ,* ' 1::' None. WF3 containment does not include tendons. No TLAA identified for containment vessel design . . Analysis remains valid 10 CFR 54.21(c)(1)(i) ,.-i .:'*. .. .. Analysis remains valid 10 CFR 54.21 (c)(1 )(i) Aging effect managed 10 CFR 54.21(c)(1)(iii) Aging effect managed 10 CFR 54.21 ( c)(1 )(iii) Aging effects managed 10 CFR 54.21 (c)(1 )(iii) . . LRA Section 4.3.2.3 4.3.3 4.4 4.4 4.5 4.5 4.6 4.6 4.6 4.7 47.1 4.7.2 4.7.3 4.7.4 Page 4.1-5. Waterford Steam Electric Station, Unit 3 License Renewal Application

Technical lnformati1on Table 4.1-2 Comparison of WF3 TLAAs to NUREG-1800 Potential TLAAs NUREG-1800 Applicable-to WF3 TLAA Description (Yes/No) :Y .** Reactor vessel neutron embrittlement Metal fatigue Environmental qualification *of electrical equipment Concrete containment tendon prestress lnservice local metal containment corrosion analyses lntergranular separation in the affected zone of reactor vessel low-alloy steel under austenitic stainless steel (SS) cladding.
Low-temperature overpressure protection (LTOP) analyses Fatigue a*nalysis for the main steam supply lines to the turbine-driven *auxiliary feedwater pumps Fatigue analysis of the reactor coolant pump flywheel Fatigue analysis of polar crane Flow-induced vibration endurance *limit for the reactor vessel internals Transient cycle count assumptions for the reactor vessel internals Ductility [sic] reduction of fracture toughness for the reactor vessel internals 4,0 Time-Limited Aging Analyses Yes Yes Yes No. There are no pre-stressed tendons in the WF3 containment structure . . No. There are no metal containment corrosion analyses. No. There are no analyses associated with underclad cracking. Yes* Yes. Included with non-Class 1 fatigue. No. Does not meet the definition of TLAAs, since it does not involve limited assumptions defined by the current operating term. Yes No.* There is no RVI flow-induced vibration analysis meeting the definition of TLAAs. Yes Yes LRA *section 4.2 4.3 4.4 4.5 NA NA 4.2.5 4.3.2 NA 4.7.1 NA 4.3.1.2 4:7.4 Page 4.1-6 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Table 4.1-2 (Continued) Comparison of WF3 TLAAs to NUREG-1800 Potential TLAAs NUREG-1800 Applicable to WF3 LRA TLAA Description (Yes/No) Section Leak before break Yes 4.7.2 analysis for the containment liner No. No fatigue evaluation performed for NA plate containment vessel design. Containment penetration pressurization Yes 4.6 cycles Metal corrosion allowance No. No TLAAs were identified for metal NA corrosion allowances. High-energy line-break postulation based Yes 4.7.3 on fatigue cumulative usage factor lnservice flaw growth analyses that No. No analyses were identified that meet NA demonstrate structure stability for 40 years the definition of TLAAs. 4.0 Time-Limited Aging Analyses Page4.1-7 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT The regulations governing reactor vessel integrity are in 1 O CFR Part 50. Light-water reactors are required by 10 CFR 50.60 to meet the fracture toughness, pressure-temperature limits, and material surveillance program requirements for the reactor coolant pressure boundary set forth in Appendices G arid Hof 10 CFR Part 50 (Ref. 4-6, 4-7). The operating license for WF3 expires on December 18, 2024. With a renewed license, the license will expire on December 18, 2044. Through mid-year 2014, WF3 had accumulated approximately 24.7 EFPY of operation. Assuming WF3 is operated at a capacity factor qf 99 percent from mid-year 2014 until the end of the renewed license period will result in the following estimate of the EFPY at the end of the period of extended operation. 24.7 + 0.99 (30.5 years of operation after mid-year 2014) =approximately 54.9 EFPY. Therefore, 55 EFPY will .be used to bound the expected EFPY for WF3 at the end of the period of extended operation. 4.2.1 Reactor Vessel Fluence ' . Fluence is calculated based on a period of operation defined by the operating license term. Fluence projected to the end of the period of e?<tended operation is a time-limited assumption used in neutron embrittlement analyses. Therefore, analyses that evaluate reactor *vessel neutron embrittlement based on projected fluence are TLAAs. The neutron fluence values for the WF3 reactor pressure vessel have been projected to 55 EFPY of operation. (Ref. 4-11) The methods used to calculate the WF3 vessel fluence satisfy the criteria set forth in Regulatory Guide (RG) 1.190 (Ref. 4-8). These methods have been approved by the NRC and are described in detail in WCAP-14040-A, Revision 4, and WCAP-16083-NP-A, Revision 0. (Ref. 4-9, 4-10) FSAR Section 5.3.1.6 additional information on the specimen capsules and the associated dosimeters. See Section B.1.34 for additional information on the -Reactor Vessel Surveillance Program. Figure 4.2-1 and Figure 4.2-2 identify the vessel weld and plate names used in this section. *The reactor vessel beltline components with fluence values greater than 1.0 x 1017 n/cm2 (E > 1.0 MeV) at 55 EFPY are the three upper shell plates, three upper shell longitudinal welds, upper to intermediate shell circumferential weld, the three lower shell plates, three intermediate shell plates, three intermediate shell longitudinal welds, three lower shell longitudinal welds, and the intermediate shell to lower shell circumferential weld. Locations with fluence values that are greater than 1.0 x 1017 n/cm2 (E > 1.0 MeV) are in Tables 4.2-1 and 4.2-3. 4.0 Time-Limited Aging Analyses Page 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Contrary to the definition of TLAAs in 1 O CFR 54.3, the calculation of fluence does not consider the effects of aging. Nevertheless, it is treated as a TLAA that has been projected to the end of the period of extended operation in accordance with 1 O CFR 54.21 (c)(1 )(ii). 4.0 Time-Limited Aging Analyses . Page 4.2-2 Figure 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Reactor Vessel Weld Identification for WF3 4.0 Time-Limited Aging Analyses Page 4.2-3

/ Figure 4.2-2 Waterford Steam Electric Station, Unit 3 License Ren.ewal Application Technical Information Reactor Vessel Plate Identification for WF3 4.0 Time-Limited Aging Analyses Page 4.2-4 Table 4.2-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculated Maximum Fast Neutron Fluence (E+19 n/cm2, E > 1.0 MeV) Projections for the WF3 Vessel Welds and Plates at 55 EFPY %T At Clad/Base Location (Thickness )(a) Metal Interface , Intermediate Shell Plates M-1003-1, 2, and 3 2.575 4'.28 Lower Shell Plates M-1004-1, 2, and 3 2.575 4.32 Intermediate Shell Longitudinal Weld 101-124A 2.575 4.28 Intermediate Shell Longitudinal Welds 101-1248 and C 2.575 2.62 Lower Shell Longitudinal Weld 101-142A 2.575 4.32 Lower Shell Longitudinal Welds 101-1428 and C 2.575 2.65 Intermediate to Lower Shell Circumferential Weld 101-171 2.575 4.28 Upper Shell Plates M-1002-1, 2, and 3 0.035 0.0582 Upper Shell Longitudinal Welds 101-122A, 8, and C 0.035 0.0582 Upper to Intermediate Shell Circumferential Weld 106-121 0.035 0.0582 a. The Y..T fluence was calculated using the RG 1.99, Revision 2 correlation, and the WF3 reactor vessel wall thickness of 8.625 inches. For intermediate and lower shell weld and plate locations, the maximum fluence value of 2.575 E+19 n/cm2 was applied for conservatism. For upper shell weld and plate locations (last three locations shown), the maximum fluence value of 0.035 E+19 n/cm2 was applied for conservatism. 4.0 Time-Limited Aging Analyses Page 4.2-5 ( 4.2.2 Upper-Shelf Energy Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Upper-shelf energy (USE) was evaluated for beltline materials. Fracture toughness criteria in 1 O CFR Part 50 Appendix G require that beltline materials maintain USE no less than 50 ft-lb during operation of the reactor. The 55 EFPY USE values for the beltline were determined using methods with RG 1.99 (Ref. 4-12). The value of peak %T fluence

was used. Two methods can be used to predict the decrea$e in USE with irradiation, depending on the availability of credible surveillance capsule data as defined in RG 1.99. For vessel beltline materials that are not in the surveillance program or for locations with non-credible data, the USE is assumed to decrease as a function of flu.ence and copper (Cu) content, as indicated in RG 1.99, Revision 2 (Position 1.2). When two or more credible surveillance data sets are available from the reactor, they may be used to determine the USE of the survefllance material. The surveillance are then used in conjunction with RG 1.99 to predict the change in USE of the reactor vessel material due to irradiation (Position 2.2). The 55 EFPY Position 1.2 USE values of the vessel *materials can be predicted using the corresponding %T fluence projection, the copper content of the materials, and Figure 2 in RG 1.99, Revision 2. The predicted Position 2.2 USE values are determined for the reactor vessel materials that are contained in the surveillance program by using the plant surveillance data along with the corresponding %T fluence projection. The projected USE values were calculated to determine if the WF3 beltline materials remain no less than the USE limit of 50 ft-lb at 55 EFPY. The results are summarized in Table 4.2-2. For WF3 (see Table 4.2-2), the limiting USE value at 55 EFPY is 73 ft-lb for the upper stiell longitudinal welds. The USE of all of the beltline materials in the WF3 reactor are projected to remain above the USE limit of 50. ft-lb through 55 EFPY. Therefore, the WF3 reactor vessel USE TLAA has been projected to the end of the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(ii). 4.0 Time-Limited Aging Analyses Page 4.2-6
' Table 4.2-2 Predicted USE Values at 55 EF_PY for WF3 RPV Beltline Materials ' Initial Cu %T Fluence(b) USE RPV Material(a) * --(Wt.%) (x1019 n/cm2) (ft-lb) Intermediate Shell Plate M-1003-1 0.02 2.575 108 Intermediate Shell Plate M-1003-2 0.02 2.575 132 Intermediate Shell Plate M-1003-3 '0.02 2:575 111 Lower Shell Plate M-1004-1 0.03 2.575 135 Lower Shell Plate M-1004-2 0.03 2.575 141 Lower Shell Plate M-1004-2 (using WF3 surveillance 0.03 .2.575 141 data) Lower Shell Plate M-1004-3 0.03 2.575 .118 Intermediate Shell Longitudinal Weld 101-124A 0.02 2.575 106 (Heat # BOLA & HODA) .f -. Intermediate Shell Longitudinal Welds 101-1248 & C 0.02 2.575 131 (Heat # HODA) Lower Shell Longitudinal Welds 101-142A, 8 & C ?* . 0.03 2.575 129 (Heat# 83653) " .-Intermediate to Lower Shell Circumferential Weld * ; 156 101-171(Heat#88114) 0.05 2.575 Intermediate to Lower Shell Circumferential Weld 0.05. 2.575 -156 101-171 (Heat# 88114) (using WF3 surveillance data) : 4.0 *Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Projected 55 EFPY . USE USE. . Decrease(c)(%) (ft-lb) 24 82 24 100 24 84 24 103 24 107 17(d) 117 24 90 24 81 24. 100 24 98 24 119 '* 15 (d)_. 133 Page 4.2-7 Table 4.2-2 (Continued) Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Predicted USE Values at 55 EFPY for WF3 RPV Beltline Materials (Continued) Initial Projected 55 EFPY Cu % T Fluence!b) USE USE USE RPV Material(a) (Wt.%) (x1019 n/cm2) (ft-lb) Decrease( cl(%) (ft-lb) Upper Shell Plate M-1002-1 0.13. 0.035 104 10 94 Upper Shell Plate M-1002-2 0.13 0.035 95 10 86 Upper Shell Plate M:.1002-3 0.10 0.035 120 9 109 Upper Shell Longitudinal Welds 101-122 A, B & C 0.23 0.035 88 17 73 (Heat# 606L40) Upper Shell Longitudinal Welds 101-122 A, B & C 0.02 0.035 ; 119 7 111 (Heat # FOCA) .-Upper Shell Longitudinal Welds 101-122 A, B & C 0.03 0.035 125 8 115 (Heat# JBHA) Upper Shell Longitudinal Welds 101-122 A, B & C 0.02 0.035 131 7 122 (Heat# HODA) Upper to Intermediate Shell Circumferential Weld 106-1'21 (Heat #-.3P4767)
0.16 0.035 87 14 75 ., Upper to .Intermediate Shell Weld 0.03 0.035 >87 8 > 80 106-121 (Heat# IAGA) Upper to Intermediate Shell Circumferential Weld 0.03 0.035 113 8 104 106-121 (Heat# KOHA) a. Table is derive,d from Table 5-1 of WCAP-18002-NP (Ref. 4-11 ). b. The '!l.!T'fluence was calculated using the RG 1.99, Revision 2, correlation, and the.WF3 reactor vessel wall thicknes$ of 8.625 inches. For. intermediate and lower shell weld and plate locations, the maximum fluence value of 2.575 E+19 n/cm2. was applied for conservatism. For upper shell weld and plate locations (last 10 locations shown), the maximum fluence value of 0.035 E+19 n/cm2 was applied for conservatism. 4.0 Time-Limited Aging Analyses Page 4.2-8 Waterford Steam Electric Station, Unit 3 .
License Renewal Application Technical Information c. Unless otherwise noted, percentage USE decrease values are based on Position 1.2 of RG 1.99, Revision 2, and were 9etermined by plotting the XT fluence values on Figure 2 of RG 1.99 and using _the material-speCific Cu wt. % values. For any materials with Cu wt. % less than the lowest lirie delineated in RG 1.99, Revision 2 (0.05% for welds and 0.10% for base metal), the Cu wt. % values *were conservatively rounded up to the lowest line. d. Percentage USE decrease is based on Position 2.2 of RG 1.99, Revision 2, using data from Jable 5-10 of WCAP-17969-NP, Revision 0. Credibility Criterion 3 in the Discussion section of RG 1.99, Revision 2, indicates that even if the surveillance data are not considered credible for determination of aRT NDT (reference temperature, nil-ductility transition), "they may be credible for determining decrease in upper-shelf energy if the upper-shelf can be clearly determined, following the definition given in ASTM E 185-82." Thus, the surveillance data may be used for WF3 USE projections. RG 1 :99, Revision 2, Position 2.2 indicates that an upper-bound line drawn parallel to the existing lines (in Figure 2 of . RG 1.99) through the surveillance data should be used in preference to the existing graph lines for determining the decrease in USE. , .. 4.0 Time-Limited Aging Analyses Page 4.2-9 4.2.3 Pressurized Thermal Shock Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Rules are provided in 10 CFR 50.61 for protection against pressurized thermal shock for pressurized water reactors. Licensees must assess the projected values of reference temperature whenever a significant change occurs in projected values of the adjusted reference temperature for pressurized thermal shock (RT PTS) or upon request fo'r a change in the . expiration date for the operating license of the facility. In accordance with the screening criteria of 10 CFR 50.61, acceptable RT PTS values are less than 270°F for plates, forgings, and axial welds and less than 300°F for circumferential welds. (Ref. 4-13) * . . . . two methods are provided in 10 CFR 50.61(c) for determining RT PTS* Position 1 app!ies for material that does not have surveillance data available, and Position 2 applies for material wi.th . surveilJance data. Positions 1 and 2 are described in RG 1.99, Revision 2. Adjusted reference temperatures are calculated for both Positions 1 and 2 by following the guidance in RG 1.99, Sections 1.1. cind 2.1, respectively, using copper and nickel (Ni) content of beltline end-of-license fluence projections.
The WF3 limiting RT PTS value for base metal or longitudinal weld materials at 55 EFPY is 57°F (see Table 4.2-3) at the upper shell plate M-1002-2. The WF3 limiting RT PTS value for circumferentially oriented welds at 55 EFPY is 73°F (see Table 4.2.:.3) at upper to intermediate shell circumferential weld 106-12*1 (Heat# 3P4767). All of the beltline materials in the WF3 reactor vessel are below the RT PTS screening criteria values of 270°F for plates, axial welds, and forgings and 300°F for circumferentially oriented welds through 55 EFPY. Therefore, the WF3 reactor vessel RT PTS TLAA has been projected to . .<. the end of the period of extended operation in accordance with 1 O CFR 54.21 (c)(1)(ii). 4.0 Time-Limited Aging Analyses Page 4.2-10 Table 4.2-3 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY Wt.% Wt.% CF(c) Fluence(d) RT NDT(U) (e) .6RTNDT a u(e) a ll.(f) Margin RTPTS RPV Material(a)(b) Cu (c) Ni (cl (oF) (x 1019 n/cm2) FF(d) (oF) (oF) (oF) (oF) (oF) (oF) Intermediate Shell 0.02 0.71 20 4.32 1.3726 -25.1 27.5 0 13.7 27.5 30 Plate M-1003-1 Intermediate Shell 0.02 0.67 20 4.32 1.3726 -20 27.5 0 13.7 27.5 35 Plate M-1003-2 Intermediate Shell 0.02 0.70 20 4.32 1.3726 -20 27.5 0 13.7 27.5 35 Plate M-1003-3 Lower Shell Plate 0.03 0.62 20 4.32 1.3726 -37.6 . 27.5 0 13.7 27.5 17 M-1004-1 Lower Shell Plate 0.03 0.58 20 4.32 1.3726 0 27.5 0 13.7 27.5 55 M-1004-2 Lower Shell Plate M-1004-2 (using ----13.4 4.32 1.3726 0 18.4 0 9.2 18.4 37 non-credible WF3 surveillance data)(g) Lower Shell Plate 0.03 0.62 20 4.32 1.3726 -20 27.5 0 -13.7 27.5 35 M-1004-3 Intermediate Shell Longitudinal Weld 0.02 0.96 27 4.32 1.3726 -60 37.1 0 18.5 37.1 14 101-124A (Heat# BOLA & HODA) Intermediate Shell Longitudinal Welds 0.02 0.96 27 4.32 1.3726--60 37.1 0 18.5 37.1 14 101-1248 & c (Heat# HODA) 4.0 Time-Limited Aging Analyses Page 4.2-11 Table (Continued} Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RTPTS Values Cfad/Base Metal Interface for 55 EFPY (Continued} Wt.% Wt.% CF(c) Fluence<d) RT NDT(U) (e) ARTNDT a u(e) C1 li.(f) RTPTS RPV Materia1<a)(b) (c) Ni. (c) (oF) (x 1019 n/cm2) FF(d) (oF) . (<>F) (oF) (oF) (OF) (oF) Lower Shell Longitudinal Welds 0.03 < 0.20 35 4.32 1.3726 -80 48.0 0 24.0 48.0 16 101-142A, B & C .. (Heat # 83653) ... to *-Lower Shell Circumferential Weld 0.05 0.16 44.4 4.32 1.3726 -70 . 60.9 *. 0 28.0 56.0 47 101"-171 . (Heat# 88114) Intermediate to Lower Shell Circumferential Weld 101-171 ----14.8 4.32 '1.3726 -70 20.3 0 10.2 20.3 -29 (Heat #,88114) (using credible WF3 surveillance data)(g) *. Upper Shell Plate 0.13 0.64 92 0.0582 0 .. 3174 -15.4 29.2 0 14.6 ;29.2 43 M*1002-1 ' . Upper Shell Plate 0.13 0.61 91.3 0.0582 0.3174 . -1'.4: 29.0 0 14.5 29.0 57 M-1002-2 . Upper Shell Plate 0.10 . 0.65 65.5 0.0582 0.3174 . ; :-20. 20.8 *o *. 10.4 . 20.8 22 M-1002-3 .. *. 4.0 Time-Limited Aging Analyses Page 4.2c12 Table 4.2-3 (Continued), Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY (Continued) Wt.% Wt.% CF(c) Fluence(d) RT NDT(U) (e) .6RTNDT a u(e) C1 l!J. (f) Margin RTPTS RPV Material(a)(b) Cu (c) Ni (c) (oF) (x 1019 n/cm2) FF(d) (oF) (oF) (oF) (oF) (oF) (oF) Upper Shell Longitudinal Welds 0.23 0.27 125.1 0.0582 0.3174 _55(h) 39.7 17(h) 19.9 52.3 36 101-122 A, B & C (Heat# 606L40) Upper Shell Longitudinal Welds 0.02 0.98 27 0.0582 0.3174 -30 8.6 0 4.3 8.6 -13 101-122 A, B & C (Heat # FOCA) Upper Shell Longitudinal Welds 0.03 0.97 41 0.0582 0.3174 -40 13.0 0 6.5 13.0 -14 101-122 A, B & C (Heat# JBHA) Upper Shell Longitudinal Welds 0.02 0.96 27 0.0582 0.3174 -60 8.6 0 4.3 8.6 -43 101-122A, B & C (Heat# HODA) Upper to Intermediate Shell Circumferential Weld 0.16 1.00 199 0.0582 0.3174 _55(h) 63.2 17(h) 28.0 65.5 73 106-121 (Heat# 3P4767) 4.0 Time-Limited Aging Analyses Page 4.2-13 Waterford. Steam Electric Station, Unit 3 License Renewal Application Technical Information . Table 4.2-3 (Continued) Calculation of WF3 RT PTS Values at Clad/Base Metal Interface for 55 EFPY (Continued) Wt.% Wt.% Cf(c) Fluenceld) RT NDT(U) (e) a u(e) a 11(f) Margin RTPTS RP\rMaterial(a)(b) -Cu (c) Ni (c) (Of) (x 1019 n/cm2) ff(d) (of) (of) (Of) (Of) (Of) (of) Upper to Intermediate Shell -CircumferentialWeld 0.03 0.98 41 0.0582 0.3174 -30 13.0 0 6.5 13.0 -4 106-121 (Heat # IAGA) I ---Upper to ' --Intermediate Shell *. Circumferential Weld 0.03 0.93 41 0.0582 _. 0.3174. -30 13.0 0 6.5 13.0 -4 106-121 " (Heat# KOHA) a. Table is derived from Table 4-1 of WCAP-18002-NP(Ref. 4-11). . b. Due to industry and regulatory interest in the methods of BTP 5-3, initial RT NDT and initial,1,JSE values for all of the beltline plate materials were re-evaluated. The initial RT NDT and initial USE values for the WF3 plate materials no longer utilize BTP 5-3 as their determination methodology. c. Chemical composition values and chemistry factors (CFs) provicjed in (Ref. 4-11) .. d. Clad/base metal interface fluence values taken from (Ref. 4-11). *FF= fluence factor= f(o.2a-o.1o*iog(f))_ e. Initial RT NDT values are based on measured data unless otherwise noted in WCAP-18-002-NP (Ref. 4-11 ). f. Per Appendix D of WCAP-17969-NP, Revision 0 (Ref. 4-14), and WCAP-18002-NP (Ref. 4-11), the sur\teillance data for the plate were deemed non-credible, whereas the sun/eillance data for the weld material were deemed credible. Per*the guidance of 1 O CFR 50.61, the base metal 01:;. = 17°F for Position 1.1. .and !or Position 2.1 yvith r:ion-credible surveillance data; the weld metal o /:;. = 28°F for Position 1.1 and, with credible surveillance data, 01:;. = 1_4°F for Position 2.1., However, 01:;. need not exceed NDT* g. Used RG 1.99, Rev. 2 Position 2.1; all others.used Position 1.1.
h. Initial RT NDT value is generic for Linde 0.091 flux type welds 10*CFR 50.61 as identified in WCAP-18002-NP (Ref. 4-11). Therefore, Ou= 17°F. 4.0 Time-Limited Aging Analyses Page 4.2-14 4.2.4 Pressure-Temperature Limits Waterford Steam Electric station, Unit 3 License Renewal Application Technical Information Appendix G of 1 O CFR 50 (Ref. 4-6) requires operation of the reactor pressure vessel within established pressure-ternperature (P-T) limits.* These limits are established by calculations that utilize the fluence and material property data obtained through the Reactor Vessel Surveillance Program. The P-T limits are valid for an established period of time. The provisions of 10 CFR 5Q Appendix G require the P-T limit curves be maintained and updated as necessar)f. The WF3 P-T limits for reactor coolant system are described in Technical Specifications (TS) 3.4.8.1. Technical Specification Figure 3.4-2, Reactor Coolant System Pressure-Temperature Limits,* identifies the WF3 heatup* limits for up to 32 EFPY. Technical Specification Figure 3.4-3, Reactor Coolant System Pressure-Temperature Limits, identifies the WF3 cooldown limits for up to 32 EFPY. Technical Specification 4.4.8.1.2 indicates that the reactor vessel material irradiation surveillance specimens shall be removed and examined at the intervals specified in the Reactor Vessel Material Surveillance Program withdrawal schedule in FSAR Table 5.3-10. The schedule is in accordance with 10 CFR Part 50 Appendix H. The examinations are performed to determine changes in material properties; and the results are used to update Technical Specifiqation Figures 3.4-2 and 3.4-3. Surveillance specimen capsule 83° was removed at approximately 24.7 EFPY. (Ref. 4-14) The analyses used to determine the P-T limit curves in the associated WCAP supporting documentation are considered TLAAs. The WF3 P-T limit curves included in the Technical Specifications are valid through 32 EFPY. Prior to exceeding 32 EFPY, WF3 will generate new P-T limit curves to support plant operation beyond 32 EFPY.
P-T limits will be updated as necessary through the period of extended operation in .conjunction with the Reactor Vessel Surveillance Program (Section B.1.34). Under the current license term and during the period of extended operation, the P-T limits will be updated prior to the end of their applicability period in accordance with the 10 CFR 50.90 process. Therefore, the Reactor Vessel Surveillance Program (Section B.1.34) will adequately manage the effects of aging associated with the P-T limit curves TLAAs for the period of extended operation in accordance. with 10 CFR 54.21 ( c)(1 )(iii). 4.2.5 Low-Temperature Overpressure Protection <LTOPl Setpoints The WF3 Technical Specification Bases 3/4.4.2 states that an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. This is accomplished by a low-temperature overpressure protection (LTOP) relief valve located in each shutdown cooling loop as identified in FSAR Section 5.28.3. In addition, the overpressure protection system provides a diverse means of protection against 4.0 lime-Limited Aging Analyses Page 4.2-15 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information RCS overpressurization at low temperatures. Each time the P-T limit curves are revised, the LTOP relief setpoints are reevaluated. Therefore, the LTOP limit calculations are considered part of the analyses of P-T curves for WF3. The P-T limit curves are updated prior to exceeding EFPY applicability limits. See Section 4.2.4 for further information on the P-T limit curves. Therefore, the Reactor Vessel Surveillance Program (Section B.1.34) will adequately manage the effects of aging associated with the LTOP setpoints TLAA for the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.2-16 4.3 METAL FATIGUE; Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Fatigue analyses are considered TLAAs for Class 1 and non-Class 1 mechanical components. Fatigue is an age-related degradation mechanism caused by cyclic stressing of a component by either mechanical or thermal stresses. The aging management reviews in Section 3 identify mechanical components that are within the scope of license renewal and subject to aging management review. When TLAA -metal fatigue is identified in the aging management program column of the. tables in Section 3, the associated fatigue arialyses are evaluated in this section. Evalu.13tion of TLAAs per 10 CFR 54.21(c)(1) determines whether (i) The analyses remain valid for the period of extended operation, (ii) The analyses have been projected to the end. of the period of extend operation, or (iii) The effects of aging on the intended function(s) will be adequately managed for the period of extended operation. Documentation of the evaluation of WF3 Class 1 metal fatigue analyses is provided in Section 4.3.1. Fatigue analysis of non-Class 1 mechanical components is discussed in Section 4.3.2. Evaluation of environmental fatigue effects is discussed in Section 4.3.3. 4.0 Time-Limited Aging Analyses Page 4.3-1 4.3.1 Class 1 Fatigue ' Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The major Class 1 components at WF3 include the reactor vessel, pressurizer, reactor coolant pumps, steam control rod drives, and associated piping and valves. As identified in
FSAR Section. 5.2.1,. the construction permit application for Waterford 3 was filed in December 1970. Major components for the nuclear steam supply system were ordered consistent with the application date and anticipated schedule. The reactor vessel, steam generators, pressurizer and piping were ordered in March 1971 and the reactor coolant pumps in March 1972. The construction permit was received in November 197 4. An isometric view of the reactor coolant system is shown in FSAR Figure.4.4-7. The following systems and associated LRA drawings that include Class 1* components. System (System Code) Reactor Coolant System (RC) Safety l!'ljection System (SI) Chemical and Volume Control System (CVC) LRA Drawinq(s) LRA-G172 LRA-G179
LRA-G 160 sh 4 LRA-G167 sh 2 LRA-G167 sh 4 LRA-G168 sh 1 LRA-G168 sh 2 Fatigue evaluations performed in the design of WF3 Class 1 components in accordance with ASME Section Ill requirements are documented in the equipment stress reports and associated, analyses. The fatigue evaluations calculate a cumulative usage factor (CUF) for each component or subcomponent based on a specified number of design cycles for that component. Because the design cycles may be the nu.mber of transient cycles that were assumed for a 40-year license term, these calculations of CUFs are considered TLMs. Design cy,clic loadings and thermal conditions for the Class 1 components are defined by the. applicable design specifications for each component. The original design specifications established the initial set of transients that were used in the design of the components and are included as part of each component stress report. FSAR Table 3.9-1, "Transients Used in Stress Analysis of Code Class 1 Components," lists the transients that were used for the stress analyses of the RCS components. FSAR Table 3.9-3, "Transients and Operative Conditions for Code Class 1 Non-NSSS Piping," identifies _the transients that were used as input to the piping stress analyses. Some component-specific locations such as the pressurizer and safety injection nozzles were also analyzed for design transients* beyond the original set of transients in response to thermal stratification and component-specific stresses that are identified in the individual stress analyses. . ( 4.0 Time-Limited Aging Analyses Page 4.3-2 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The WF3 Technical Requirements Manual (TRM) 5.7-1 contains the requirement to maintain the reactor coolant system components within the component cyclic or transient limits of TRM Table 5.7-1. In preparation for license renewal, an evaluation was performed to determine the cycles that required tracking. Then a review of plant operating history identified the number of cycles as of April 5; 2014. The rate of transient occurrence was utilized to estimate the number of cycles through 60 years of operation as shown in Table 4.3-1 As described in Appendix B, the WF3 Fatigue Moniforing Program will monitor transient cycles that contribute to fatigue usage.
Cycle monitoring ensures the continuing validity of fatigue TLAAs (calculations of CUFs) for various WF3 components. The Fatigue Monitoring Program (Section B.1.11) will monitor the necessary operating transients and assure action is taken prior to the analyzed riumpers of transients being exceeded. The WF3 Fatigue Monitoring Program will manage the aging effects due to fatigue of the affected components in accordance with* 10 CFR 54.21(c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.3-3

/ \ { i ,_ ' . Table 4.3-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Projected and Analyzed Transient Cycles Number of . Cycles as of 60-year Projected Analyzed Number Transient Description ' 4/5/14 Number of Cycles(a) of Cycles RCS heatup , 70 144 300 Pressurizer heatup 70 144 200 RCS cooldown

69 144 300 cooldown 69 144 :. 200 Reactor trip 91 187 400 I. Loss of reactor. coolant flow 0 4(b) 40 . Loss .of load 0 4(b) 40 Operating basis earthquake 0 1(1J) 5 8o1Uunbolt (RV head) 23 47 50 ' PZR Spray Transients: 81: Aux. spray, :> 1. pump, > 350°F . 18 37 ., 140 82: Aux. spray,*> 1 pump, s 350°F *7 14 160 ., C1 :*Aux. spray, < 2 pumps, > 350°F 151 '. 310 41Q C2: Aux. spray, < 2 pur;nps, s 350°F . 129 .. 265 240 D: Stop 3rd RCP, no aux. spray 124 254 400
E: Start 2nd RCP, s 392 psia 124 254 400 Tube leak tests (for replacement steam generators) Tube leak test (at 200 psig) 0 4q(b) 400 Tube leak. test (at 400 psig) " 2o(bl '* 0 200 ' -Tube leak test (at 600 psig), 0 12(b) " 120 Tube leak test (at 840 psig) 0 8(bl 80 Containment integrated leakage rate 1 4(b) 20 test (ILRT) Loss of charging 4 8 200 Loss of letdown 25 51 100 Extended loss *of letdown 131 .. 269 600 Safety valve release 0 4(b) 40 Safety injection at full temperature 0 4(b) 10 4.0 Time-Limited Aging Analyses Page 4.3-4 \

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information a. The original operating license term ends on 12/18/2024 and the renewed operating license term would end on 12/18/2044. The 4/5/2014 data date "is at 29.3 years of operation. Unless otherwise identified by a footnote, the projected values are determined by using a multiplier of 60/29.3 = 2.05 times the number of occurrences as* of 4/5/2014. b. Although none of these cycles have occurred, a projected value is conservatively listed. These projected values have not been used to replace the original analyzed .numbers of cycles. Cycles will continue to be tracked by th.e Fatigue Monitoring Program (Section B.1.11 ). . . 4.3.1.1 Reactor Vessel FSAR Table 5.2-.1, "Codes and Addenda Applied to Reactor Coolant Pressure Boundary," identifies the codes and addenda applied to the design of the reactor coolant pressure boundary. The reactor vessel was designed to ASME Section Ill, Class 1 through Summer 1971 Addenda .. The original .reactor vessel head has been replaced. The replacement reactor vessel head was designed to ASME Section Ill, Class 1 1998 edition through summer 2000 addenda. . . The calculated CUFs for the reactor vessel and replacement head are less than 1. The reactor vessel design transients that require tracking are included in Table 4.3-1. WF3 will monitor transient cycles using the Fatigue Monitoring Program and assure that corrective action specified in the program is taken if any of the actual cycles approach their analyzed nu.mbers. As such, the Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging due to fatigue on the reactor vessel and reactor vessel head in accordance with 1 O CFR 54.21 (c)(1)(iii). 4.3.1.2 Reactor Vessel Internals The WF3 reactor vessel internals are not pressure boundary components. As described in FSAR Section 3.9.5, in the design of critical reactor vessel internals components that are subject to fatigue, the stress analysis was performed utilizing the design fatigue cunle of Figure *1-9.2 of Section Ill of the ASME Boiler and Pressure Vessel Code. Stress reports were generated for several specific reactor vessel internals locations to support component replacement or reanalysis. The calculated CUFs for the reactor vessel internals are less than 1. The transients iqentified in Table 4.3-1 include the transients that require tracking for the reactor vessel internals. WF3 will monitor transient cycles using the Fatigue Monitoring Program and assure _that corrective action specified in the program is taken if any of the actual cycles approach their. analyzed numbers. As such, the Fatigue Monitoring Program will manage the effects of aging due to fatigue on the reactor vessel internals in accordance with 1 O CFR 54.21 (c)(1 )(iii). 4.0 Time-Limited Aging Analyses Page 4.3-5 4.3.1.3 Pressurizer Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The pressurizer is described in-FSAR Section 5.4.10 and is shown in FSAR Figure 5.4:..6. As identified in FSAR Table 5.2-1, the pressurizer was to ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, through Summer 1971 Addenda. Structural weld overlays have been installed on the pressurizer surge nozzle, the pressurizer safety valve nozzles, and the pressurizer spray nozzle. The heater sleeves that remain in service were repaired. The pressurizer side shell temperature measurement nozzle arid upper and lower head instrument nozzles were replaced.

the .calculated CUF=s for the pressurizer are less than 1. The transients identified in Table 4.3-1 include the transients that require tracking for the pressurizer. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the pressurizer in accordance with 10 CFR 54.21 (c)(1 )(iii).
4.3.1.4 Steam Generators Replacement steam generators have been installed at WF3 as identified in FSAR Section 5.4.2 and shown in FSAR Figure 5.4-5. As identified in FSAR Table 5.2-1, the replacement steam generators were designed to ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, 1998 Edition through 2000 Addenda. In addition to the RCS. transients identified.in FSAR Section \ 3.9.1.1, the replacement steam generators*fatigue analysis evaluation of c9mponent . : -specific transients such as the tube leak tests. -The calculated CUFs for the replacement steam generators are less -than 1. The transients identified in Table 4.3-1 include the transients*that require tracking for the replacement steam generators. The Fatigue Monitoring Program will manage the effects of agi_r:ig due to fatigue on . the steam generators in accordance with 10 CFR 54.21(c)(1)(iii). 1.5 Control Element Drive Mechanisms As described in FSAR Section 4.1, the control element drive mechanisms have been replaced. The control element drive mechanisms are described in FSAR Sections 3.9.4 and 4.1 and shown in FSAR Figure 3.'9-13. As described in FSAR Table 5.2-1, the replacement control element drive mechanisms are designed to.ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, 1.998 Edition and 2000 Addenda. The calculated CUFs for the control element drive mechanisms are less than 1. The transients identified in Table 4.3-1 include the transients that require tracking for the control element drive mechanisms. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the control element drive mechanisms in accordance with 10 CFR 54:21{c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.3-6 .

4.3.1.6 Reactor Coolant Pumps Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information The reactor coolant pumps are described in FSAR Sections 3.9.1 and 5.4.1 and are shown in FSAR Figures 5.4-1 and 5.4-2. As identified in _FSAR Table 5.2-1, the pump casings were de.signed to.ASME Boiler and Pressure Vessel Code, Section Ill, Class 1, through Winter 1971 Addenda.

The calculated CUFs for the reactor coolant pumps are less than 1. The transients identified _in Table 4.3-1 include the transients that require tracking for the reactor coolant pumps. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the reactor coolant pumps in accordance with 10 CFR 54.21(c)(1)(iii). 4.3.1.7 *Reactor Coolant System Class 1 Piping* The reactor coolant loop piping is in FSAR Section 5.4.3. The hot legs, cold legs and *pressurizer surge piping was supplied by the nuclear stearn system supplier (NSSS), ABB
Combustion Engineering, and controlled by project specifications. The Class 1 tributary lines
analyses include consideration of location specific transients such as loss of charging and loss of
Structural weld overlays (SWOL) have been installed on piping *for the hot leg surge nozzle,, hot leg two-inch drains;* and the hot leg shutdown cooling nozzles. The calculated piping CUFs are less than* 1. The transients identified in Table 4.3-1 include the transients that require tracking for the Class 1 piping. The Fatigue Monitoring Program will manage the effects of aging due to fatig1,.1e on the reactor coolant system Class .1 piping in accordance with 10 CFR54.21(c)(1)(iiif 4.0 Time-Limited Aging Analyses Page 4.3-7 4.3.2
Non-Class 1 Mechanical Systems Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.3.2.1 Non-Class 1 Pressure Boundary Piping Using Stress Range Reduction Factors The impact of thermal cycles on non-Class 1 piping and in-line components is reflected in the reduction of the allowable stress range if projected cycles exceed 7000. The design of ASME 111 Code Class 2 and 3 or 831.1 piping systems incorporates a stress range reduction factor for determining acceptability of piping design with respect to thermal stresses. In general, a stre§ls range reduction factor of 1.0 in the stress analyses applies for up to 7000 thermal cycles. The allowable stress range is reduced by the stress *range reduction factor if the number of thermal cycles exceeds 7000 (ASME Boiler and Pressure Vessel Code, Division 1, Subsection NC, Class 2 For the systems that are subjected to elevated temperatures above the fatigue. threshold, thermal cycles have been projected for 60 years of plant operation for the.piping and: in-line components. These projections indicate that 7000 cycles will not be exceeded during 60 years of operation. Therefore, the non-Class 1 pipe stress calculations are valid for the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(i). 4.3.2.2 Flexible Connections and.Expansion Joints As part of the review of the WF3 documentation for fatigue, a search was performed for * *of mechanical flexible connectors and expansion joints that are within the scope of license renewal. TLAAs were identified for emergency diesel generator intake air.and exhaust expansion joints ineluded in LRA tables in Section 3. The of these analyses determined. flexible connectors were qualified for at least 15,000 cycles, which are more cycles than are expected from the starting of the diesels for the period of extended operation. The design analyses were determined to.remain valid for the period of operation in accordance with 10 CFR 54.21(c)(1)(i). . . 4.3.2.3 Non-Class 1 Heat Exchangers with Fatigue Analysis. Although the letdown and regenerative heat exchangers are in the Class 2 portion of the system, a fatigue analysis was completed for the design of these components. The cycle limits are represented in Table 4.3-1. The Fatigue Monitoring Program will manage the effects of aging due to fatigue on the letdown and regenerative heat exchangers in accordance with 10 CFR 54.21(c)(1)(ii.i). * *
4.0 Time-Limited Aging Analyses Page 4.3-8 Waterford Steam Electric Station, Unit 3 . License Renewal Application Technical Information 4:3.3 Effects of Reactor Water Environment on Fatigue Life Industry test data inc:jicate that certain environmental effects (such as temperature and dissolved oxygen content) in the primary systems of light water reactors could result in greater susceptibility to fatigue than would be predicted by fatigue analyses based on the ASME Section Ill design fatigue curves. The ASME design fatigue curves were based on laboratory tests in air and at low temperatures. As reported in SECY-95-245, the NRC believes that no immediate staff or licensee-action is necessary to deal with the environmentally assisted fatigue issue. In addition, the staff concluded that it could not justify requiring a backfit of the environmental fatigue data to operating plants. However, the NRC concluded that, because metal fatigue effects increase with service life, environmentally assisted fatigue should be evaluated as aging management programs are formulated in support of license renewal. NUREG/CR-6260 (Ref. 4-18) addresses the application of-environmental factors to fatigue analyses (CUFs) and identifies locations of interest for consideration of environmental effects. NUREG/CR-6260 identified the following component locations to be.the most sensitive to environmental effects for Combustion Engineering (CE) plants. (1) Reactor vessel shell and'lower head * ; . . (2) Reactor vessel inlet and outlet nozzles '(3). Surge line . (4) Charging system nozzle (5) Safety injection system .nozzle * (6) Shutdown. cooling line Table 4.3-2 shows the results of a screening evaluation for these locations. Environmentally Assisted Fatigue (EAF) Summary NUREG-1801, Section X.M1 says the applicant addresses the effects of the coolant environment on component fatigue life by assessing the impact of the reactor coolant environment on a sample of critical components for the plant. There is no analysis of EAF under the current basis. Rather, the effect on fatigue life of the reactor water environment is a new consideration for license renewal. Applying the environmentally assisted fatigue correction factqrs <Fens) identified in Table 4.3-2 is not required during the initial 40 years of operation, consistent with the closure of Generic Safety Issue (GSI) 190. (Ref. 4-3) 4.0 Time-Limited Aging Analyses Page 4.3-9 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information As shown in Table 4.3-2, using bounding environmental correction factors, two locations have environmentally adjusted projected CUFs greater than 1.0 at the end of the period of extended operation. The WF3 Fatigue Monitoring Program (Section 8.1.11) wili manage the effects of aging due to fatigue, including EAF, for the period of extended operation iri accordance with 10 CFR 54.21(c)(1)(iii). For locations with projected CUFs greater than 1.0, refined EAF evaluations will be completed for WF3 prior to the period of extended operation as identified by the enhancement to the Fatigue Monitoring Program (Section B.1.11 ). Original design basis fatigue calculations typically include conservatism meant to simplify the analyses, such as lumping transients together and considering them to be as severe as the worst transient for a particular location. As a part of incorporating the effects on fatigue of the reactor water environment, the design basis fatigue analyses may be revised for locations that would exceed a GUF of 1.0. CUFs will be determined using an NRG-approved version of the ASME code or NRG-approved alternative_ (e:g., NRG-approved code case). WF3 will update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 whe*n. accounting for the effects of reactor water environment prior to the period of extended operation.* This includes applying the appropriate Fen factors to valid CUFs determined using an NRG-approved version of the ASME code or NRG-approved alternative (e.g., NRG-approved code case). WF3 will review design basis ASME Class 1 component fatigue evaluations to ensure the locations evaluated for the effects of the reactor coolant environment on fatigue include the most limiting components within.the reactor coolant pressure . boundary. Environmental effects on fatigue for these critical components will be evaluated using one of the following sets of formulae. Carbon and Low Alloy Steels (LAS)
Those provided in NUREG/CR-6583 (Ref. 4-19), using the applicable ASME Section Ill fatigue design curve.
Those provided in Appendix A of NUREG/CR-6909 (Ref. 4-20), using either the applicabl13 ASME Section Ill fatigue design curve or the fatigue design curve for carbon and low alloy steel provided in NUREG/CR-6909 (Figures A.1 and A.2, respectively, and Table A.1).
A staff-approved alternative. Austenitic Stainless Steels
Those provided in NUREG/CR-5704 (Ref. 4-17), using the applicable ASME Section Ill fatigue design curve. 4.0 Time-Limited Aging Analyses Page 4.3-10 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information
Those provided in NUREG/CR-6909, using the fatigue design curve for austenitic steel provided in NUREG/CR-6909 (Figure A.3 and Table A.2).
A staff-approved alternative. Nickel Allovs
Those provided in NUREG/CR-6909, using the fatigue design curve for austenitic stainless steel provided in NUREG/CR-6909 (Figure A.3 and Table A.2).
A alternative. If an acceptable CUF cannot be calculated, WF3 will repair or replace the affected locations before exceeding an environmentally adjusted CUF of 1.0. *Therefore, the WF=3 Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging due to fatigue, including EAF, for the period of extended operation in accordance with 10 CFR 54.21 (c)(1 )(iii). 4.0 Time-Limited Aging Analyses Page 4.3-11.

Table 4.3-2 EAF Screening Evaluation NUREG/CR-6260 Generic Plant-Specific M.aterial Location Location Type 1 Reactor vessel shell and Ves'sel shell LAS lower head transition 1 Reactor.vessel shell and Lower head at LAS lower head .-juncture with flow baffle 2 Reactor vessel inlet and Inlet nozzle LAS outlet nozzles 2 Reactor vessel inlet and Outlet nozzle LAs outlet nozzles ' ' 3 Pressurizer l)urge line 'Pressurizers urge LAS (including hot leg and. nozzle _, pressurizer nozzles)' 3 Pressurizer surge lihe Surge line tiot leg. SS r \ (including hot.leg and nozzle safe end pressurizer nozzles) ' 4 Charging system nozzle Charging nozzle SS 5 Safety injection systE!m Safety injection

SS nozzle nozzle loop 1A '.' 6 Shutdown cooling line SOC Line 2 SS 4.0 Time-Limited Aging Analyses Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information EAF CUF Fen CUF 0.01 2.45 0.03 0.402 2.45 0.99 " 0.218 2.45 0.53 0.401 2.45 0.98 0.550 2.45 > 1 0.6'.49 15.36 > 1 0.0191 0.293 0.0285 15.36 0.438 0.0379 ' 15.36 0.582 Page 4.3-12 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.4 ENVIRONMENTAL QUALIFICATION (EQ) OF ELECTRIC.EQUIPMENT All operating plants must meet the requirements of 10 CFR 50.49, which defines the scope of electrical components to be included in an EQ program and also provides the requirements the EQ program must meet. Qualification entails demonstrating the ability to withstand environmental and service conditions _during nornial plant operation and also those conditions postulated 'for plant accidents. A record of qualification for in-scope components must be prepared and maintained in auditable form, Equipment qualification evaluations for EQ 'components that specify a qualification of at least 40 years, but less than 60 years, are considered TLAAs for license renewal. The WF3 Environmental Qualification (EQ) of Electric.Components (WF3 EQ Program) manages the effects of aging due to component thermal, radiation, and cyclical aging, as applicable, through the use of aging evaluations t;>ased on 10 CFR S0.49(f) qualification methods. As required by 1 O CFR 50.49, EQ components are to be refurbished, replaced, or have their qualification extended prior to reaching the aging limits establ.ished in the evaluation. The WF3 1EQ Program ensures thatthe EQ components are maintainecj in accordance.with their *qualification bases. *' * . The WF3 EQ Program is.an existing program established to meet WF3 for 10 CFR 50.49. The program is consistent with NUREG-1801, Section X.E1, "Environmental Qµalification (EQ) of Electric Components." The WF3 EQ Program will man.age the effects of aging on the intended function(s) of EQ components that are the subject of EQ TLAAs for.the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iii). 4.0 Time-Limited Aging Analyses Page 4.4-1 4.5 CONCRETE CONTAINMENT TENDON PRESTRESS Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information This section is not applicable as WF3 does not have pre-stressed tendons in the containment structure, as identified in FSAR Sections 1.8.1.35 and 3.8. ) 4.0 Time-Limited Aging Analyses Page 4.5-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATIONS FATIGUE ANALYSIS As identified in, FSAR Section 3.8.2.3, the containment vessel was designed to exhibit a general elastic behavior under accident and earthquake conditions of loading. No permanent deformations due to primary stresses have been permitted in the design under any condition of loading. A fatigue evaluation was not performed for the containment vessel design. ' WF3 has penetration bellows that are reviewed as part of the structural aging management reviews. As described in FSAR Section 3.6.2.4, these bellows are designed for a minimum of 7000 thermal cycles and 200 design seismic movements (cycles). This number of cycles is more than these expansion joints will experience through the period of extended operation. The analyses remain valid in accordance with 10 CFR 54.21 (c)(1)(i). 4.0 Time-Limited Aging Analyses Page 4.6-1

4. 7 OTHER PLANT-SPECIFIC TLAAS 4.7.1 Crane Load Cycle Analysis Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information Cranes that were designed to Crane Manufacturer's Association of America Specification #70 (CMAA-70) have cycles specified as part of their design analysis. Even though crane analyses do not involve time-limited assumptions defined by the current operating term, for 40 years, crane cycle limits are nevertheless evaluated as a TLAA for cranes that were designed to CMAA-70. . CMAA-70 (1975 Edition) Table 3.3.3.1.3-1 identifies crane service classes with corresponding ranges of loading cycles .. According to CMAA-70, Service Class A 1 cranes are designed for up* to 100,000 loading cycles. A review of the cranes at WF3 determined that cranes that were . designed to CMAA-70 are the polar.crane, fuel handling building (FHB) crane, and the radwaste cask handling* bridge.crane (located in the auxiliary building). (Ref. 4-15) The* expected number of applicable crane cycles is below the top of the lowest cyclic loading range in CMAA-70of100,000 cycles, and the associated TLAAs remain valid for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(i): 4. 7.2 Leak-Before-Break An.alysis

FSAR Section 3.6.3 that a (LBB) analysis was used to eliminate from the structural design bases the dynamic effects of double-ended guillotine breaks and e,quivalent longitudinal breaks. LBB analyses consider the thermal aging of cast austenitic stainless steel (CASS) piping and fatigue transients that drive flaw growth. during plant operation. _Because these two analysis considerations could involve time-limited assumptions defined by the current term of operation, LBB analyses were further reviewed as potential TLAAs ,for W.F3. The applicable locations are the main coolant loop and the line. Thermal Aging of CASS Thermal aging results in an increase in the yield strength of CASS. and a decrease in its fracture toughness. Bounding fracture toughness values were used in the evaluation for the main coolant loop and the pressurizer surge line components (Ref. 4-5). Since LBB evaluations use saturated (fully aged) fracture toughness properties, the evah.,1ation of the thermal aging of CASS portion of the'analysis does not have a material* property and is not a TLAA. Fatigue Crack Growth The LBB analysis determined that fatigue crack growth effects will be very small when analyzing for the full set of design transients. The fatigue crack growth analysis is considered a TLAA. The basis of the evaluation of fatigue crack effects in the LBB analysis will remain unchanged 4.0 Time-Limited Aging Analyses Page 4.7-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information if the number of transient occurrences remains below the number assumed for the analysis of fatigue crack growth effects. Continued implementation of the WF3 Fatigue Monitoring Program provides reasonable assurance that the fatigue crack growth analysis will remain valid during the period of extended operation. Therefore, the Fatigue Monitoring Program (Section B.1.11) will manage the effects of aging associated with the LBB fatigue crack growth analyses for the main coolant loops and pressurizer surge line piping for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iiif 4.7.3 Postulation of High Energy Line Break <HELBl Locations As described in FSAR Section 3.6.2.1.1.2, ASME Section Ill, Code Class 1 piping (excluding RCS loop and surge piping) rupture locations have been postulated in any piping run or brarich at terminal ends and other intermediate points in accordance with Regulat_or}t Guide 1.46, Protection Against Pipe Whip Inside Containment (May 1973) and Branch Technical Position MEB 3-1 issued with Genei-ic Letter 87-11, Relaxation in Arbitrary.Intermediate Pipe Rupture Requirements. Postulated rupture locations for Class 1 piping are as follows. (1) Terminal points,* * * (2) Any intermediate points between terminal ends where the CUF exceeds 0.1 (based upon normal and upse(plant conditions and operating basis earthquake [OBE]). (3) Any intermediate points between terminal ends where the primary plus secondary "stress intensities derived on an elastic basis is greater than* 2:0 Sm in ferritic and 2.4 Sm* in austenitic piping materials (based on normal and upset plant conditions and OBE). . A fatigue analysis to determine a CUF for the intermediate points* is considered a TLAA. The Fatigue Monitoring Program (Section B.1.11) identifies when the transients affecting high-energy piping systems are approaching their analyzed number of cycles. Therefore, the CUF
calculations used to determine HELB postulated break locations are considered TLAAs that will be managed for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(iii). 4. 7 :4 Reactor Vessel Internals Evaluations (Other thari Fatigue) During service, reactor vessel internal (RVI) and core support component materials are exp-osed to a high-temperature aqueous environment, fast neutron *irradiation and applied loads. WF3
performed evaluations to assess the effect of the extended power Uprate (EPU) conditions on the potential for degradation of the RVI component materials. The evaluation addres$ed age-related
degradation mechanisms of materials that could be affected by the reactor coolant temperature and by neutron and gamma irradiation. The evaluations found that neutron and gamma flux are lower than considered in the original design: Therefore, the level of irradiation-induced enibrittlement was not expected to change significan!IY with the uprate. Also, embrittlement of 4.0 Time-Limited Aging Analyses Page4.7-2 Waterford Steam Electric Station, Unit 3 License Renewal Application -Technical Information -* CASS components as a result of thermal aging and neutron irradiation was not significantly affected by the power uprate. However, evaluations performed associated with the extended power uprate process to determine the -effects of flu'ence on RVI components are considered TLAAs as they were based on operation only until the end of the original 40-year operating term. (Ref. 4-16) -In development of MRP-227-A, the considered degradation mechanisms associated with irradiation during plant operation. The inspection and evaluation guidelines of MRP-227-A thus are designed to manage the effeets of aging of RVI. The WF3 Reactor Vessel lriternals-.Program incorporates the guidance of MRP-227-A. Therefore, the effects of aging associated with RVI TLAAs will be managed by the Vessel Internals Program for the period of extended operation in accordance with .10 CFR 54.21 (c)(1 )(iii). (Ret 4-21, 4-22). --4.0 Aging Analyses Page 4.7-3 )

4.8 REFERENCES

Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4-1 NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR 54.., The License Renewal Rule, Revision 6, June 2005. 4-2 NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 2010. 4-3 NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, December 2010. 4-4 EPRI Report TR-105090, Guidelines to Implement the License Renewal Technical Requirements of 10 CFR 54 for Integrated Plant Assessments and Time-Limited Aging

Analyses, November 1995. 4-5 CEN-367-A, Revision 000, "Leak-Before-Break" Evaluation of Primary Coolant Loop.Piping .. in Combustion Engineering Designed Nuclear Steam Supply Systems," prepared for the C-E Owners' Group, February 1991. 4-6 10 CFR 50 Appendix G, Fracture Toughness Requirements. 4-7 10 CFR 50 Appendix H, Reactor Vessel Material Surveillance Program Requirements. 4-8 NRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Vessel Neutron Fluence,'*March 2001. 4-9 non-proprietary, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," J. D. Andrachek et al., May 2004, 4-1 O WCAP:..16083-NP-A, Revision 0, "Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry," S. L. Anderson, May 2006. 4-11 WCAP-18002-NP, "Waterford Unit 3 Time-Limited Aging Analysis on Reactor Vessel Integrity," July 2015. 4-12 NRC Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2. 4-13 1 O CFR Part 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock, D.ecember 1995, 4-14 WCAP-17969-NP, Analysis of Capsule 83° from the Entergy Operations, Inc. Waterford , Unit 3 Reactor Vessel Radiation Surveillance Program, Revisio!l 0, April 2015 .. 4.0 Time-Limited Aging Analyses Page 4.8-1 Waterford Steam Electric Station, Unit 3 License Renewal Application Technical Information 4-15 CMAA-70, Crane Manufacturers Association of America Specification #70, Specifications for Electric Overhead Traveling Cranes, 1975 Edition. 4-16 W3F1-2003-0074, License Amendment Request NPF-38-249, Extended Power Uprate Waterford Steam E.lectric Station, Unit 3, November 13, 2003. 4-17 NUREG/CR-5704 (ANL-98/31), Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, April 1999. 4-18
NUREG/CR-6260 (INEL 95/0045), Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, February 1995. 19 NUREG/CR-6583 (ANL-97/18), Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, February 199.8. 4-20 NUREG/CR-6909 (ANL-06/08), Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, February 2007. 4-21 LTR-Cl-03-63*, 3716 MWt Power Uprate Waterford 3 Reactor Vessel Internals Materials Evaluation, Revision 1 (from Westinghouse Proprietary Class 2). ,* 4-22 CWTR3-15-16*, Fluence for Reactor Vessel Internals Aging Management, July 30, 2015. *Document is a proprietary document. 4.0 Time-Limited Aging Analyses Page 4.8-2}}

ML16088A332

Text

4.8 REFERENCES

4.8 REFERENCES

4.8 REFERENCES

4.8 REFERENCES

Navigation menu

Search