ML12334A650

Official Exhibit - NYS00147A-00-BD01 - NUREG-1801, Rev. 2, Generic Aging Lessons Learned (GALL) Report, Final Report (December 2010) (GALL Rev 2)

ML12334A650
Person / Time
Site:	Indian Point
Issue date:	12/31/2010
From:	Office of Nuclear Reactor Regulation
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21545, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 NUREG-1801, Rev 2
Download: ML12334A650 (189)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3)

""tP-f'REGU(.q" ASLBP #: 07-858-03-LR-BD01 NYS00147A

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Docket #: 05000247 l 05000286 Submitted: December 15, 2011

~ 0 Exhibit #: NYS00147A-00-BD01 Identified: 10/15/2012

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Admitted: 10/15/2012 Withdrawn:

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i Rejected:

0' Stricken:

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Other:

ci;U.S.NRC United States Nuclear Regulatory Commission NUREG-1801, Rev. 2 Protecting People and the Environment Generic Aging Lessons Learned (GALL) Report Final Report Office of Nuclear Reactor Regulation OAGI0001390_00001

AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at libraries include all open literature items, such as NRC's Public Electronic Reading Room at books, journal articles, and transactions, Federal bitp..:1!YY.YlilN...DIQ,.9.QY!X§.9.9.i0.9::DILbtmJ* Register notices, Federal and State legislation, and Publicly released records include, to name a few, congressional reports. Such documents as theses, NUREG-series publications; Federal Register notices; dissertations, foreign reports and translations, and applicant, licensee, and vendor documents and non-NRC conference proceedings may be purchased correspondence; NRC correspondence and internal from their sponsoring organization.

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OAGI0001390_00002

~U.S.NRC United States Nuclear Regulatory Commission NUREG-1801, Rev. 2 Protecting People and the Environment Generic Aging Lessons Learned (GALL) Report Final Report Manuscript Completed: December 2010 Date Published: December 2010 Office of Nuclear Reactor Regulation OAGI0001390_00003

ABSTRACT NUREG-1801, "The Generic Aging Lessons Learned (GALL) Report" (GALL Report), contains the staffs generic evaluation of the existing plant programs and documents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the period of extended operation. The evaluation results documented in the GALL Report indicate that many of the existing programs are adequate to manage the aging effects for structures or components for license renewal without change. The GALL Report also contains recommendations on specific areas for which existing programs should be augmented for license renewal. An applicant may reference the GALL Report in a license renewal application to demonstrate that the programs at the applicant's facility correspond to those reviewed and approved in the GALL Report. The GALL Report should be treated as an approved topical report. However, if an applicant takes credit for a program in the GALL Report, it is incumbent on the applicant to ensure that the conditions and operating experience at the plant are bounded by the conditions and operating experience for which the GALL Report program was evaluated. If these bounding conditions are not met, it is incumbent on the applicant to address the additional effects of aging and augment the GALL Report aging management program(s) as appropriate. The staff will verify that the applicant's programs are consistent with those described in the GALL Report and/or with plant conditions and operating experience during the performance of an aging management program audit and review. The focus of the balance of the staff's review of a license renewal application is on those programs that an applicant has enhanced to be consistent with the GALL Report, those programs for which the applicant has taken an exception to the program described in the GALL Report, and plant-specific programs not described in the GALL Report. The information in the GALL Report has been incorporated into the NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," as directed by the Commission, to improve the efficiency of the license renewal process.

December 201 0 iii NUREG-1801, Rev. 2 OAGI0001390_00004

TABLE OF CONTENTS Abstract ...................................................................................................................................... iii List of Contributors ................................................................................................................... xi Abbreviations ............................................................................................................................ xv Introduction ................................................................................................................................. 1 Background ................................................................................................................................. 2 Overview of the GALL Report Evaluation Process .................................................................. 5 Application of the GALL Report ................................................................................................ 8 I. Application of ASME Code ...............................................................................................I-i II. Containment Structures .................................................................................................. II-i A Pressurized Water Reactor (PWR) Containments .............................................. 11 A-i A1 Concrete Containments (Reinforced and Prestressed) .................... II A 1-1 A2 Steel Containments .......................................................................... II A2-1 A3 Common Components ...................................................................... II A3-1 B Boiling Water Reactor (BWR) Containments ...................................................... II B-i B1 Mark I Containments ......................................................................... II B1-1 B2 Mark II Containments ........................................................................ II B2-1 B3 Mark III Containments ....................................................................... II B3-1 B4 Common Components ...................................................................... II B4-1 III. Structures and Component Supports ........................................................................... III-i A Safety Related and Other Structures ................................................................. 111 A-i A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.) .............................................................. III A 1-1 A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) ................................................................................ III A2-1 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm.,

AFW Pumphouse, Utility/Piping Tunnels Yard Structures, such as AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures, such as Transmission Towers, Startup Towers Circuit Breaker Foundation, Electrical Enclosure) ........................... III A3-1 A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) .............................................................. III A4-1 AS Group S Structures (Fuel Storage Facility, Refueling Canal) .............................................................................................. III AS-1 December 201 0 v NUREG-1801, Rev. 2 OAGI0001390_0000S

A6 Group 6 Structures (Water-Control Structures) ............................... III A6-1 A7 Group 7 Structures (Concrete Tanks and Missile Barriers) ............. III A7-1 A8 Group 8 Structures (Steel Tanks and Missile Barriers) ................... III A8-1 A9 Group 9 Structures (BWR Unit Vent Stack) ..................................... III A9-1 B Component Supports ......................................................................................... 111 B-i B1 Supports for ASME Piping and Components ................................... III B1-1 B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components .................................................................................... III B2-1 B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation .................................. III B3-1 B4 Supports for Emergency Diesel Generator (EOG), HVAC System Components, and Other Miscellaneous Mechanical Equipment ................................................................... III B4-1 B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures ................................................................. III B5-1 IV. Reactor Vessel, Internals, and Reactor Coolant System ........................................... IV-i A1 Reactor Vessel (BWR) .................................................................................. IV A 1-1 A2 Reactor Vessel (PWR) ................................................................................... IV A2-1 B1 Reactor Vessel Internals (BWR) .................................................................... IV B1-1 B2 Reactor Vessel Internals (PWR) - Westinghouse .......................................... IV B2-1 B3 Reactor Vessel Internals (PWR) - Combustion Engineering .......................... IV B3-1 B4 Reactor Vessel Internals (PWR) - Babcock and Wilcox ................................. IV B4-1 C1 Reactor Coolant Pressure Boundary (BWR) .................................................. IV C1-1 C2 Reactor Coolant System and Connected Lines (PWR) .................................. IV C2-1 01 Steam Generator (Recirculating) .................................................................... IV 01-1 02 Steam Generator (Once-Through) ................................................................. IV 02-1 E Common Miscellaneous Material/Environment Combinations ......................... IV E-1 V. Engineered Safety Features ........................................................................................... V-i A Containment Spray System (PWR) ................................................................... V A-1 B Standby Gas Treatment System (BWR) .......................................................... V B-1 C Containment Isolation Components .................................................................. V C-1 01 Emergency Core Cooling System (PWR) ....................................................... V 01-1 02 Emergency Core Cooling System (BWR) ....................................................... V 02-1 E External Surfaces of Components and Miscellaneous Bolting .......................... V E-1 F Common Miscellaneous Material/Environment Combinations .......................... V F-1 VI. Electrical Components .................................................................................................. VI-i A Equipment, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements .................................... VI A-1 NUREG-1801, Rev. 2 vi December 201 0 OAG10001390_00006

B Equipment Subject to 10 CFR S0.49 Environmental Qualification Requirements ................................................................................................... VI B-1 VII. Auxiliary Systems ......................................................................................................... VII-i A1 New Fuel Storage .......................................................................................... VII A1-1 A2 Spent Fuel Storage ....................................................................................... VII A2-1 A3 Spent Fuel Pool Cooling and Cleanup (PWR) .............................................. VII A3-1 A4 Spent Fuel Pool Cooling and Cleanup (BWR) .............................................. VII A4-1 AS Suppression Pool Cleanup System (BWR) ................................................... VII AS-1 B Overhead Heavy Load and Light Load (Related to Refueling)

Handling Systems .......................................................................................... VII B-1 C1 Open-Cycle Cooling Water System (Service Water System) ........................ VII C1-1 C2 Closed-Cycle Cooling Water System ............................................................ VII C2-1 C3 Ultimate Heat Sink ........................................................................................ VII C3-1 o Compressed Air System .................................................................................. VII 0-1 E1 Chemical and Volume Control System (PWR) .............................................. VII E1-1 E2 Standby Liquid Control System (BWR) ........................................................ VII E2-1 E3 Reactor Water Cleanup System (BWR) ....................................................... VII E3-1 E4 Shutdown Cooling System (Older BWR) ....................................................... VII E4-1 ES Waste Water Systems ................................................................................... VII ES-1 F1 Control Room Area Ventilation System ........................................................ VII F1-1 F2 Auxiliary and Radwaste Area Ventilation System ........................................ VII F2-1 F3 Primary Containment Heating and Ventilation System ................................. VII F3-1 F4 Diesel Generator Building Ventilation System .............................................. VII F4-1 G Fire Protection ............................................................................................... .vll G-1 H1 Diesel Fuel Oil System .................................................................................. VII H1-1 H2 Emergency Diesel Generator System .......................................................... VII H2-1 I External Surfaces of Components and Miscellaneous Bolting ......................... VII 1-1 J Common Miscellaneous Material/Environment Combinations ......................... VII J-1 VIII. Steam and Power Conversion System ...................................................................... VIII-i A Steam Turbine System ................................................................................... VIII A-1 B1 Main Steam System (PWR) ......................................................................... VIII B1-1 B2 Main Steam System (BWR) ......................................................................... VIII B2-1 C Extraction Steam System .............................................................................. VIII C-1 01 Feedwater System (PWR) ............................................................................ VIII 01-1 02 Feedwater System (BWR) ............................................................................ VIII 02-1 E Condensate System ....................................................................................... VIII E-1 F Steam Generator Blowdown System (PWR) .................................................. VIII F-1 G Auxiliary Feedwater System (PWR) ............................................................... VIII G-1 H External Surfaces of Components and Miscellaneous Bolting ....................... VIII H-1 Common Miscellaneous Material/Environment Combinations ........................ VIII 1-1 December 201 0 vii NUREG-1801, Rev. 2 OAG10001390_00007

IX. Selected Definitions and Use of Terms for Structures, Components, Materials, Environments, Aging Effects, and Aging Mechanisms ............................ IX-i A Introduction .......................................................................................................... IX-1 B Structures and Components ................................................................................ IX-2 C Materials .............................................................................................................. IX-7 o Environment ...................................................................................................... IX-14 E Aging Effects ..................................................................................................... IX-22 F Significant Aging Mechanisms .......................................................................... IX-27 G References ........................................................................................................ IX-41 X. Time-Limited Aging Analyses [Evaluation of Aging Management Programs under 10 CFR S4.21(c)(1)(iii)] ......................................................................................... X-i X.M1 Fatigue Monitoring .......................................................................................... X M1-1 X.S1 Concrete Containment Tendon Prestress ...................................................... X S1-1 X.E1 Environmental Qualification (EQ) of Electric Components ............................. X E1-1 XI. Aging Management Programs (AMPs) ......................................................................... XI-i XI.M1 ASME Section Xllnservice Inspection, Subsections IWB, IWC, and IWO ........................................................................................................... XI M1-1 XI.M2 Water Chemistry ....................................................................................... XI M2-1 XI.M3 Reactor Head Closure Stud Bolting .......................................................... XI M3-1 XI.M4 BWR Vessel 10 Attachment Welds ........................................................... XI M4-1 XI.MS BWR Feedwater Nozzle ............................................................................ XI MS-1 XI.M6 BWR Control Rod Drive Return Line Nozzle ............................................ XI M6-1 XI.M7 BWR Stress Corrosion Cracking ............................................................... XI M7-1 XI.MS BWR Penetrations .................................................................................... XI MS-1 XI.M9 BWR Vessel Internals ............................................................................... XI M9-1 XI.M10 Boric Acid Corrosion ............................................................................... XI M10-1 XI.M11 B Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components (PWRs only) .................................................................... XI M 11 B-1 XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) ........................................................................... XI M12-1 XI.M16A PWR Vessel Internals ........................................................................... XI M16A-1 XI.M17 Flow-Accelerated Corrosion .................................................................... XI M17-1 XI.M1S Bolting Integrity ....................................................................................... XI M1S-1 XI. M 19 Steam Generators ................................................................................... XI M 19-1 XI.M20 Open-Cycle Cooling Water System ........................................................ XI M20-1 XI.M21A Closed Treated Water Systems ............................................................ XI M21A-1 XI.M22 Boraflex Monitoring ................................................................................. XI M22-1 XI.M23 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems .................................................................. XI M23-1 XI.M24 Compressed Air Monitoring .................................................................... XI M24-1 NUREG-1801, Rev. 2 viii December 201 0 OAGI0001390_0000S

XI.M2S BWR Reactor Water Cleanup System .................................................... XI M2S-1 XI.M26 Fire Protection ......................................................................................... XI M26-1 XI.M27 Fire Water System .................................................................................. XI M27-1 XI.M29 Aboveground Metallic Tanks ................................................................... XI M29-1 XI.M30 Fuel Oil Chemistry .................................................................................. XI M30-1 XI.M31 Reactor Vessel Surveillance ................................................................... XI M31-1 XI.M32 One-Time Inspection ............................................................................... XI M32-1 XI.M33 Selective Leaching .................................................................................. XI M33-1 XI.M3S One-time Inspection of ASME Code Class 1 Small Bore-Piping ............ XI M3S-1 XI.M36 External Surfaces Monitoring of Mechanical Components ..................... XI M36-1 XI.M37 Flux Thimble Tube Inspection ................................................................. XI M37-1 XI.M38 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components ............................................................................................ XI M38-1 XI.M39 Lubricating Oil Analysis ........................................................................... XI M39-1 XI.M40 Monitoring of Neutron-Absorbing Materials Other than Boraflex ............ XI M40-1 XI.M41 Buried and Underground Piping and Tanks ............................................ XI M41-1 XI.S1 ASME Section XI, Subsection IWE ................................................................ XI S1-1 XI.S2 ASME Section XI, Subsection IWL ................................................................. XI S2-1 XI.S3 ASME Section XI, Subsection IWF ................................................................ XI S3-1 XI.S4 10 CFR Part SO, Appendix J ........................................................................... XI S4-1 XI.SS Masonry Walls ................................................................................................ XI SS-1 XI.S6 Structures Monitoring ..................................................................................... XI S6-1 XI.S7 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants ............................................................................... XI S7-1 XI.S8 Protective Coating Monitoring and Maintenance Program ............................ XI S8-1 XI.E1 Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR S0.49 Environmental Qualification Requirements ........................ XI E1-1 XI.E2 Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR S0.49 Environmental Qualification Requirements Used in Instrumentation Circuits ............................................................................. XI E2-1 XI.E3 Inaccessible Power Cables Not Subject to 10 CFR S0.49 Environmental Qualification Requirements ........................................................................ XI E3-1 XI.E4 Metal Enclosed Bus ........................................................................................ XI E4-1 XI.ES Fuse Holders .................................................................................................. XI ES-1 XI.E6 Electrical Cable Connections Not Subject to 10 CFR S0.49 Environmental Qualification Requirements ........................................................................ XI E6-1 Appendix: Quality Assurance for Aging Management Programs ....................................... A-i December 201 0 ix NUREG-1801, Rev. 2 OAG10001390_00009

LIST OF CONTRIBUTORS Division of License Renewal, Office of Nuclear Reactor Regulation B. Holian Division Director M. Galloway Deputy Division Director S. Lee Deputy Division Director L. Lund Deputy Division Director R. Auluck Branch Chief J. Dozier Branch Chief D. Pelton Branch Chief A. Hiser Senior Level R. Gramm Team Leader H. Ashar Structural Engineering M. Banic Mechanical Engineering A. Buford Structural Engineer C.Cho Administrative Assistant J. Davis Materials Engineering C. Doutt Electrical Engineering B. Elliot Materials Engineering A. Erickson General Engineer S. Figueroa Licensing Assistant B. Fu Materials Engineering J. Gavula Mechanical Engineering W. Holston Mechanical Engineering E. Keegan Project Manager I. King Licensing Assistant R.Li Electrical Engineering J. Medoff Mechanical Engineering S. Min Materials Engineering D. Nguyen Electrical Engineering V. Perin Mechanical Engineering A. Prinaris Mechanical Engineering L. Regner Project Manager S. Sakai Project Manager B. Rogers Reactor Engineer A. Sheikh Structural Engineering W. Smith Mechanical Engineering R. Sun Mechanical Engineering R. Vaucher Mechanical Engineering A. Wong Mechanical Engineering December 201 0 xi NUREG-1801, Rev. 2 OAGI0001390_00010

C.Y. Yang Materials Engineering L. Yee Administrative Assistant O.Yee Mechanical Engineering Office of Nuclear Reactor Regulation G. Casto Branch Chief T. Chan Branch Chief M. Khanna Branch Chief A. Klein Branch Chief T. Lupoid Branch Chief M. Mitchell Branch Chief R. Taylor Branch Chief G. Wilson Branch Chief R. Hardies Senior Level - Materials Engineering K. Karwoski Senior Level - Steam Generators K. Manoly Senior Level - Structural Engineering D. Alley Materials Engineering J. Bettie Mechanical Engineering T. Cheng Structural Engineering G. Cheruvenki Materials Engineering J. Collins Mechanical Engineering R. Davis Materials Engineering S. Gardocki Mechanical Engineering M. Hartzman Materials Engineering K. Hoffman Mechanical Engineering N. Iqbal Fire Protection Engineering A. Johnson Mechanical Engineering S.Jones Mechanical Engineering B. Lee Mechanical Engineering R. Mathew Electrical Engineering P. Patniak Mechanical Engineering G. Purciarello Mechanical Engineering A. Tsirigotis Mechanical Engineering M. Yoder Chemical Engineering E. Wong Chemical Engineering NUREG-1801, Rev. 2 xii December 201 0 OAGI0001390_00011

Region I G. Meyer Mechanical Engineering M. Modes Mechanical Engineering Office of Nuclear Regulatory Research A. Csontos Branch Chief M. Gavrilas Branch Chief R. Hogan Branch Chief T. Koshy Branch Chief M. Salley Branch Chief R. Tregoning Senior Level - Materials Engineering S. Aggarwal Electrical Engineering J. Burke Mechanical Engineering G. Carpenter Materials Engineering H. Graves Structural Engineering A. Hull Materials Engineering B.Lin Structural Engineering L. Ramadan Electrical Engineering G. Stevens Materials Engineering D. Stroup Fire Protection Engineering G. Wang Mechanical Engineering Advanced Technologies and Laboratories International, Inc. (A TL)

K. Makeig Project Manager K. Chang Mechanical Engineering O. Chopra Materials Engineering W. Jackson Mechanical Engineering D. Jones Programming (Project Enhancement Corp.)

M. May Mechanical Engineering A. Ouaou Structural Engineering E. Patel Mechanical Engineering J. Davis Materials Engineering R. Royal Electrical Engineering T. Brake Technical Editing December 201 0 xiii NUREG-1801, Rev. 2 OAGI0001390_00012

ABBREVIA TIONS ACAR aluminum conductor aluminum alloy reinforced ACRS aluminum conductor steel reinforced ACI American Concrete Institute ADS automatic depressurization system AFW auxiliary feedwater ALARA as low as reasonably achievable AMP aging management program AMR aging management review ANSI American National Standards Institute ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials B&PV boiler and pressure vessel B&W Babcock & Wilcox BWR boiling water reactor BWRVIP Boiling Water Reactor Vessel and Internals Project CASS cast austenitic stainless steel CB core barrel CCCW closed-cycle cooling water CE Combustion Engineering CEA control element assembly CFR Code of Federal Regulations CFS core flood system CLB current licensing basis CRD control rod drive CRDM control rod drive mechanism CRDRL control rod drive return line CRGT control rod guide tube CVCS chemical and volume control system DC direct current DHR decay heat removal DSCSS drywell and suppression chamber spray system EDG emergency diesel generator EPDM ethylene propylene diene monosomer EPR ethylene-propylene rubber EPRI Electric Power Research Institute December 201 0 xv NUREG-1801, Rev. 2 OAGI0001390_00013

EQ environmental qualification FAC flow-accelerated corrosion FERC Federal Energy Regulatory Commission FRN Federal Register Notice FSAR Final Safety Analysis Report FW feedwater GALL Generic Aging Lessons Learned GE General Electric GL generic letter HOPE high density polyethylene HELBs high-energy line breaks HP high pressure HPCI high-pressure coolant injection HPCS high-pressure core spray HPSI high-pressure safety injection HVAC heating, ventilation, and air conditioning I&C instrumentation and control IASCC irradiation assisted stress corrosion cracking IC isolation condenser 10 inside diameter IEB inspection and enforcement bulletin IEEE Institute of Electrical and Electronics Engineers IGA intergranular attack IGSCC intergranular stress corrosion cracking IN information notice INPO Institute of Nuclear Power Operations IPA integrated plant assessment IR insulation resistance IRM intermediate range monitor lSI inservice inspection LER licensee event report LG lower grid LOCA loss of coolant accident LP low pressure LPCI low-pressure coolant injection LPCS low-pressure core spray NUREG-1801, Rev. 2 xvi December 201 0 OAGI0001390_00014

LPM loose part monitoring LPRM low-power range monitor LPSI low-pressure safety injection LRAAI license renewal applicant action items LRT leak rate test LWR light water reactor MFW main feedwater MIC microbiologically influenced corrosion MS main steam MSR moisture separatorireheater MT magnetic particle testing NOE nondestructive examination NEI Nuclear Energy Institute NFPA National Fire Protection Association NPAR nuclear plant aging research NPS nominal pipe size NRC Nuclear Regulatory Commission NRMS normalized root mean square NSAC Nuclear Safety Analysis Center NSSS nuclear steam supply system NUMARC Nuclear Management and Resources Council OCCW open-cycle cooling water 00 outside diameter OOSCC outside diameter stress corrosion cracking OM operation and maintenance PT penetrant testing PVC polyvinyl chloride PWR pressurized water reactor PWSCC primary water stress corrosion cracking QA quality assurance RCCA rod control cluster assemblies RCIC reactor core isolation cooling RCP reactor coolant pump RCPB reactor coolant pressure boundary RCS reactor coolant system December 201 0 xvii NUREG-1801, Rev. 2 OAGI0001390_00015

RG Regulatory Guide RHR residual heat removal RMS root mean square RWC reactor water cleanup RWST refueling water storage tank RWT refueling water tank SAW submerged arc weld SCC stress corrosion cracking SOC shutdown cooling SFP spent fuel pool SG steam generator S/G standards and guides SIL services information letter SIT safety injection tank SLC standby liquid control SOER significant operating experience report SR silicon rubber SRM source range monitor SRM staff requirements memorandum SRP-LR standard review plan for license renewal SS stainless steel SSC systems, structures, and components TGSCC transgranular stress corrosion cracking TLAA time-limited aging analysis UCS Union of Concerned Scientists UHS ultimate heat sink USI unresolved safety issue UT ultrasonic testing UV ultraviolet XPLE cross-linked polyethylene NUREG-1801, Rev. 2 xviii December 201 0 OAGI0001390_00016

INTRODUCTION NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is referenced as a technical basis document in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR). The GALL Report lists generic aging management reviews (AMRs) of systems, structures, and components (SSCs) that may be in the scope of license renewal applications (LRAs) and identifies aging management programs (AMPs) that are determined to be acceptable to manage aging effects of SSCs in the scope of license renewal, as required by 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants." If an applicant takes credit for a program in the GALL Report, it is incumbent on the applicant to ensure that the conditions and operating experience at the plant are bounded by the conditions and operating experience for which the GALL Report was evaluated. If these bounding conditions are not met, it is incumbent on the applicant to address the additional effects of aging and augment the GALL report AMPs as appropriate.

If an LRA references the GALL Report as the approach used to manage aging effect(s), the NRC staff will use the GALL Report as a basis for the LRA assessment consistent with guidance specified in the SRP-LR.

December 201 0 NUREG-1801, Rev. 2 OAGI0001390_00017

BACKGROUND Revision 0 of the GALL Report By letter dated March 3, 1999, the Nuclear Energy Institute (NEI) documented the industry's views on how existing plant programs and activities should be credited for license renewal. The issue can be summarized as follows:

To what extent should the staff review existing programs relied on for license renewal to determine whether an applicant has demonstrated reasonable assurance that such programs will be effective in managing the effects of aging on the functionality of structures and components during the period of extended operation?

In a staff paper (SECY-99-148, "Credit for Existing Programs for License Renewal") dated June 3, 1999, the staff described options for crediting existing programs and recommended one option that the staff believed would improve the efficiency of the license renewal process.

Bya staff requirements memorandum (SRM), dated August 27, 1999, the Commission approved the staff's recommendation and directed the staff to focus the staff review guidance in the SRP-LR on areas where existing programs should be augmented for license renewal. The staff would develop a GALL Report to document the staff's evaluation of generic existing programs. The GALL Report would document the staff's basis for determining which existing programs are adequate without modification and which existing programs should be augmented for license renewal. The GALL Report would be referenced in the SRP-LR as a basis for determining the adequacy of existing programs.

The GALL Report (Revision 0) is built on a previous report, NUREG/CR-6490, "Nuclear Power Plant Generic Aging Lessons Learned (GALL)," which is a systematic compilation of plant aging information. The GALL Report (Revision 0) extended the information in NUREG/CR-6490 to provide an evaluation of the adequacy of AMPs for license renewal. The NUREG/CR-6490 report was based on information in over 500 documents: Nuclear Plant Aging Research (NPAR) program reports sponsored by the Office of Nuclear Regulatory Research, Nuclear Management and Resources Council (NUMARC, now NEI) industry reports addressing license renewal for major structures and components, licensee event reports (LERs), information notices, generic letters, and bulletins. The staff also considered information contained in the reports provided by the Union of Concerned Scientists (UCS) in a letter dated May 5, 2000.

Following the general format of NUREG-0800 for major plant sections, except for refueling water, chilled water, residual heat removal, condenser circulating water, and condensate storage system in pressurized water reactor (PWR) and boiling water reactor (BWR) power plants, the staff reviewed the aging effects on components and structures, identified the relevant existing programs, and evaluated program attributes to manage aging effects for license renewal. The GALL Report (Revision 0) was prepared with the technical assistance of Argonne National Laboratory and Brookhaven National Laboratory. As directed in the SRM, the GALL Report (Revision 0) had the benefit of the experience of the staff members who conducted the review of the initial LRAs. Also, as directed in the SRM, the staff sought stakeholders' participation in the development of this report. The staff held many public meetings and workshops to solicit input from the public. The staff also requested comments from the public on the draft improved license renewal guidance documents, including the GALL Report, in the Federal Register Notice, Vol. 65, No. 170, August 31, 2000. The staff's analysis of stakeholder NUREG-1801, Rev. 2 2 December 201 0 OAG10001390_00018

comments is documented in NUREG-1739. These documents can be found online at http://www.nrc.gov/reading-rm/doc-collections/.

Revision 1 of the GALL Report Based on lessons learned from the reviews of LRAs and other public input including industry comments, the NRC staff proposed changes to the GALL Report (Revision 0) to make the GALL Report (Revision 1) more efficient. A preliminary version of Revision 1 of the GALL Report was posted on the NRC public web page on September 30,2004. The draft revisions of the GALL Report (Vol. 1 and Vol. 2) were further refined and issued for public comment on January 31, 2005. The staff also held public meetings with stakeholders to facilitate dialogue and to discuss comments. The staff subsequently took into consideration comments received (see NUREG-1832) and incorporated its dispositions into the September 2005 version of the GALL Report (Revision 1).

Revision 2 of the GALL Report Based on further lessons learned from the reviews of LRAs, operating experience obtained after Revision 1 was issued, and other public input including industry comments, the NRC staff proposed changes to the GALL Report (Revision 1). A preliminary version of Revision 2 of the GALL Report was posted on the NRC public web page on December 23,2009. The draft revision of the GALL Report was further refined and issued for public comment on May 18, 2010. The staff held public meetings with stakeholders to facilitate dialogue and to discuss comments. The staff subsequently took into consideration comments received (see NUREG-1950) and incorporated their dispositions into the December 2010, Revision 2 of the GALL Report.

Revision 2 - Operating Experience Evaluation The extended operation of nuclear reactors necessitates a thorough analysis of existing experience. An operating experience review was performed by NRC staff to identify necessary additions or modifications to the GALL Report based on this experience. Both domestic and foreign operating experience was reviewed.

The staff from the Division of License Renewal (DLR) analyzed operating experience information during a screening review of domestic operating experience, foreign operating experience from the international Incident Reporting System (IRS) database, and NRC generic communications. The information reviewed included operating experience from January 2004 to approximately April 2009.

Domestic Operating Experience: The NRC, Office of Research (RES) provided a listing of Licensee Event Reports (LERs) related to failures, cracking, degradation, etc. of passive components. These results were reviewed by NRC staff. The operating experience elements of numerous AMPs were updated to reflect relevant operating experience identified by the review.

In addition, the operating experience review identified a number of examples where vibration-induced fatigue caused cracking of plant components. The staff subsequently modified GALL AMP XI.M35, "One-time Inspection of ASME Code Class 1 Small-bore Piping," to address these concerns.

Foreign Operating Experience: The international IRS, jointly operated by the International Atomic Energy Agency (lAEA) and the Nuclear Energy Agency (NEA), is used to compile and December 201 0 3 NUREG-1801, Rev. 2 OAG10001390_00019

analyze information on NPP events and also promotes a systematic approach to collecting and disseminating the lessons learned from international operating experience. Events of safety significance and events from which lessons can be learned are reported to the IRS. The main objective of the IRS is to enhance the safety of NPPs by reducing the frequency and severity of safety significant unusual events at NPPs. NRC staff also reviewed international operating experience from: (a) the Organization for Economic Co-operation and Development (OECD)

OECD/NEA Piping Failure Data Exchange database (including the data from 1970 to 2009) and (b) the OECD/NEA Stress Corrosion Cracking and Cable Aging database.

The foreign operating experience databases were queried for reports relating to aging effects in passive components. The identified reports were analyzed to determine if there were any revisions necessary for either AMR items or AMP content. Many of the reports identified MEAP combinations that were already addressed by the GALL Report. Some of the items were specific to foreign plants and not generically applicable to U.S. pressurized water reactors (PWRs) and boiling water reactors (BWRs). In addition, the IRS identified that stainless steel components are subject to chloride-induced stress corrosion cracking when they are exposed to the air-outdoor environment that involves a salt-laden atmospheric condition or salt water spray.

Based on this review result, relevant SRP-LR sections were added and further evaluation is now recommended for those environmental conditions.

NUREG-1801, Rev. 2 4 December 201 0 OAG10001390_00020

OVERVIEW OF THE GALL REPORT EVALUATION PROCESS The GALL Report contains 11 chapters and an appendix. The majority of the chapters contain summary descriptions and tabulations of evaluations of AMPs for a large number of structures and components in major plant systems found in light-water reactor nuclear power plants. The major plant systems include the containment structures (Chapter II), structures and component supports (Chapter III), reactor vessel, internals and reactor coolant system (Chapter IV),

engineered safety features (Chapter V), electrical components (Chapter VI), auxiliary systems (Chapter VII), and steam and power conversion system (Chapter VIII).

Chapter I of the GALL Report addresses the application of the ASME Code for license renewal.

Chapter IX contains definitions of a selection of standard terms used within the GALL Report.

Chapter X contains the time-limited aging analysis evaluation of AMPs under 10 CFR 54.21 (c)(1)(iii). Chapter XI contains the AMPs for the structures and mechanical and electrical components. The Appendix of the GALL Report addresses quality assurance (QA) for AMPs.

The evaluation process for the AMPs and the application of the GALL Report is described in this document. The results of the GALL effort are presented in tabular format in the GALL Report.

Table Column Headings The following describes the information presented in each column of the tables in Chapters II through VIII contained in this report.

Column Description Heading Item Identifies a unique number for the item (i.e., VII.G.A-91). The first part of the number indicates the chapter and AMR system (e.g., VII.G is in the auxiliary systems, fire protection system), and the second part is a unique chapter-specific identifier within a chapter (e.g., A-91 for auxiliary systems).

Link For each row in the subsystem tables, this item identifies the corresponding row identifier from GALL Volume 2, Rev. 1, if the row was derived from the earlier version of this report. Otherwise, blanks indicate a new row in this revision of the GALL Report.

Structure and/ Identifies the structure or components to which the row applies.

or Component Material Identifies the material of construction. See Chapter IX of this report for further information.

Environment Identifies the environment applicable to this row. See Chapter IX of this report for further information.

Aging Effect! Identifies the applicable aging effect and mechanism(s). See Chapter IX of the Mechanism GALL Report for more information.

Aging Identifies the time-limited aging analysis or AMP found acceptable for Management adequately managing the effects of aging. See Chapters X and XI of the GALL Programs Report.

Further Identifies whether further evaluation is needed.

Evaluation December 201 0 5 NUREG-1801, Rev. 2 OAG10001390_00021

The staff's evaluation of the adequacy of each generic AMP to manage certain aging effects for particular structures and components is based on its review of the following 10 program elements in each AMP.

AMP Element Description

1. Scope of the Program The scope of the program should include the specific structures and components subject to an AMR.

2. Preventive Actions Preventive actions should mitigate or prevent the applicable aging effects.

3. Parameters Monitored or Parameters monitored or inspected should be linked to the Inspected effects of aging on the intended functions of the particular structure and component.

4. Detection of Aging Effects Detection of aging effects should occur before there is a loss of any structure and component intended function. This includes aspects such as method or technique (i.e., visual, volumetric, surface inspection), frequency, sample size, data collection, and timing of new/one-time inspections to ensure timely detection of aging effects.

5. Monitoring and Trending Monitoring and trending should provide for prediction of the extent of the effects of aging and timely corrective or mitigative actions.

6. Acceptance Criteria Acceptance criteria, against which the need for corrective action will be evaluated, should ensure that the particular structure and component's intended functions are maintained under all current licensing basis (CLB) design conditions during the period of extended operation.

7. Corrective Actions Corrective actions, including root cause determination and prevention of recurrence, should be timely.

8. Confirmation Process The confirmation process should ensure that preventive actions are adequate and that appropriate corrective actions have been completed and are effective.

9. Administrative Controls Administrative controls should provide a formal review and approval process.

10. Operating Experience Operating experience involving the AMP, including past corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the period of extended operation.

On the basis of its evaluation, if the staff determined that a program is adequate to manage certain aging effects for a particular structure or component without change, the "Further Evaluation" entry will indicate that no further evaluation is recommended for license renewal.

NUREG-1801, Rev. 2 6 December 201 0 OAG10001390_00022

Chapter XI of the GALL Report contains the staff's evaluation of generic aging management programs that are relied on in the GALL Report, such as the ASME Section XI inservice inspection, water chemistry, or structures monitoring program.

December 201 0 7 NUREG-1801, Rev. 2 OAGI0001390_00023

APPLICATION OF THE GALL REPORT The GALL Report is a technical basis document to the SRP-LR, which provides the staff with guidance in reviewing an LRA. The GALL Report should be treated in the same manner as an approved topical report that is generically applicable. An applicant may reference the GALL Report in an LRA to demonstrate that the programs at the applicant's facility correspond to those reviewed and approved in the GALL Report.

If an applicant takes credit for a program in GALL, it is incumbent on the applicant to ensure that the plant program contains all the elements of the referenced GALL program. In addition, the conditions and operating experience at the plant must be bound by the conditions and operating experience for which the GALL program was evaluated, otherwise it is incumbent on the applicant to augment the GALL program as appropriate to address the additional aging effects.

The above verifications must be documented on-site in an auditable form. The applicant must include a certification in the LRA that the verifications have been completed.

The GALL Report contains one acceptable way to manage aging effects for license renewal. An applicant may propose alternatives for staff review in its plant-specific LRA. Use of the GALL Report is not required, but its use should facilitate both preparation of an LRA by an applicant and timely, uniform review by the NRC staff.

In addition, the GALL Report does not address scoping of structures and components for license renewal. Scoping is plant-specific, and the results depend on the plant design and CLB.

The inclusion of a certain structure or component in the GALL Report does not mean that this particular structure or component is within the scope of license renewal for all plants.

Conversely, the omission of a certain structure or component in the GALL Report does not mean that this particular structure or component is not within the scope of license renewal for any plants.

The GALL Report contains an evaluation of a large number of structures and components that may be in the scope of a typical LRA. The evaluation results documented in the GALL Report indicate that many existing, typical generic aging management programs are adequate to manage aging effects for particular structures or components for license renewal without change. The GALL Report also contains recommendations on specific areas for which existing generic programs should be augmented (require further evaluation) for license renewal and documents the technical basis for each such determination. In addition, the GALL Report identifies certain SSCs that mayor may not be subject to particular aging effects, and those for which industry groups are developing generic aging management programs or investigating whether aging management is warranted.

The Appendix of the GALL Report addresses quality assurance (QA) for aging management programs. Those aspects of the aging management review process that affect the quality of safety-related structures, systems, and components are subject to the QA requirements of Appendix B to 10 CFR Part 50. For nonsafety-related structures and components subject to an AMR, the existing 10 CFR Part 50, Appendix B, QA program may be used by an applicant to address the elements of the corrective actions, confirmation process, and administrative controls for an aging management program for license renewal.

The GALL Report provides a technical basis for crediting existing plant programs and recommending areas for program augmentation and further evaluation. The incorporation of the NUREG-1801, Rev. 2 8 December 201 0 OAG10001390_00024

GALL Report information into the SRP-LR, as directed by the Commission, should improve the efficiency of the license renewal process and better focus staff resources.

December 201 0 9 NUREG-1801, Rev. 2 OAGI0001390_00025

CHAPTER I APPLICATION OF THE ASME CODE December 201 0 I-i NUREG-1801, Rev. 2 OAGI0001390_00026

The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1, Sections III (design) and XI (inservice inspection requirements) were developed and are revised periodically by industry code committees composed of representatives of utilities, reactor designers, architect-engineers, component manufacturers, insurance companies, the U.S. Nuclear Regulatory Commission (NRC), and others. In 1971, the Atomic Energy Commission (AEC), the predecessor of the NRC, incorporated the ASME Boiler and Pressure Vessel Code into the regulations in 10 CFR 50.55a through issuance of the Federal Register Notice (FRN) for the final rule (36 FR 11423 [June 12, 1971]).

The Statements of Consideration (SOCs) for the initial issuance of 10 CFR 50.55a provide the bases for AEC's endorsement and use of the ASME Code:

"It has been generally recognized that, for boiling and pressurized water-cooled reactors, pressure vessels, piping, pumps, and valves which are part of the reactor coolant pressure boundary should, as a minimum, be designed, fabricated, inspected, and tested in accordance with the requirements of the applicable American Society of Mechanical Engineers (ASME) codes in effect at the time the equipment is purchased[.]"

"Because of the safety significance of uniform early compliance by the nuclear industry with the requirements of these ASME codes and published code revisions, the Commission has adopted the following amendments to Part 50 and 115, which require that certain components and systems of water-cooled reactors important to safety comply with these codes and appropriate revisions to the codes at the earliest feasible time."

"Compliance with the provisions of the amendments and the referenced codes is intended to insure a basic, sound quality level."

These ASME Code sections are based on the collective engineering judgment of the code committees and document the conditions that must be monitored, the inspection techniques to identify those conditions, the frequency of the inspections, and the acceptance criteria that the inspections' results must meet in order to assure the integrity of the structures and components considered in the code. The NRC has accepted this engineering judgment by endorsing the use of selected sections of the ASME Code, as incorporated in 10 CFR 50.55a.

In addition, the NRC periodically amends 10 CFR 50.55a and issues FRNs about this rule in order to endorse, by reference, newer editions and ASME Code Addenda subject to the modifications and limitations identified in 10 CFR 50.55a. At the time of this Standard Review Plan for License Renewal (SRP-LR) (NUREG-1S00) and Generic Aging Lessons Learned (GALL) Report (NUREG-1S01) update, the most recent editions of the ASME Code Sections III and XI were endorsed in 73 FR 52730-52750 (September 10, 200S). As stated in 65 FR 53050 (August 31, 2000):

"To ensure that the GALL report conclusions will remain valid when future editions of the ASME Code are incorporated into the NRC regulations by the 10 CFR 50.55a rulemaking, the staff will perform an evaluation of these later editions for their adequacy for license renewal using the 10-element program evaluation described in the GALL Report as part of the 10 CFR 50.55a rulemaking."

December 201 0 1-1 NUREG-1801, Rev. 2 OAG10001390_00027

The staff will document this evaluation in the SOC accompanying future 10 CFR 50.55a amendments, which will be published in a FRN.

To aid applicants in the development of their license renewal applications, the staff has developed a list of aging management programs (AMPs) in the GALL Report that are based on conformance with the 10-program element criteria defined in Section A.1.2.3 of the SRP-LR.

Some of the AMPs referenced in the GALL Report are based entirely or in part on compliance with the requirements of ASME Section XI, as endorsed for use through reference in 10 CFR 50.55a., The staff has determined that the referenced ASME Section XI programs or requirements provide an acceptable basis for managing the effects of aging during the period of extended operation for these AMPs, except where noted and augmented in the GALL Report.

For aging management purposes, consideration of the acceptability for license renewal of ASME Section XI editions and addenda from the 1995 edition through the 2004 Addenda are discussed in FRNs 67 FR 60520 (September 26,2002); 69 FR 58804 (October 1,2004); and 73 FR 52730 (September 10,2008) (via update of 10 CFR 50.55a). These FRNs provide that ASME Section XI editions and addenda from the 1995 edition through the 2004 edition, as modified and limited in the final rule, are acceptable and the conclusions in the current GALL Report at the time of the FRN issuance remain valid. Future FRNs that amend 10 CFR 50.55a will discuss the acceptability of editions and addenda more recent than the 2004 edition for their applicability for aging management for license renewal. Therefore, except where noted and augmented in the GALL Report, the following ASME Section XI editions and addenda are acceptable and should be treated as consistent with the GALL Report: (1) from the 1995 edition to the 2004 edition, as modified and limited in 10 CFR 50.55a, and (2) more recent editions, as evaluated for their adequacy for license renewal and discussed in the accompanying FRN for 10 CFR 50.55a rulemaking endorsing those specific editions. Hence, applicants for renewal should justify any exception to use an ASME Section XI edition or addenda that is (1) earlier than the 1995 edition, (2) not endorsed in 10 CFR 50.55a, or (3) not adequate for license renewal as discussed in the FRN issuing the 10 CFR 50.55a amendment.

In some cases, the staff has determined that specific requirements in ASME Section XI need to be augmented to ensure adequate aging management consistent with the license renewal rule.

Thus, some of the AMPs in the GALL Report provide for additional augmented actions. For these situations, applicants for renewal should review the recommendations in the GALL Report and discuss proposed enhancements in their LRAs.

Pursuant to 10 CFR 50.55a(g)(4), a nuclear licensee is required to amend its current licensing basis (CLB) by updating its ASME Section XI edition and addenda of record to the most recently endorsed edition and addenda referenced in 10 CFR 50.55a one year prior to entering the next 10-year internal inservice inspection (lSI) for its unit. Pursuant to 10 CFR 54.21(b), an applicant for license renewal is required to periodically submit updates of its LRA to identify any changes in its CLB that materially affect the contents of the LRA. The rule requires an update of the LRA each year following the submittal of the application and an additional update 3 months prior to the completion of the NRC's review of the LRA. If an applicant's ASME Section XI edition of record is updated under the requirements of 10 CFR 50.55a(g)(4) during the NRC's review of the LRA, the applicant should update those AMPs in the LRA that are impacted by this change in the CLB when the applicant submits the next update of the LRA required by 10 CFR 54.21 (b).

The current regulatory process, including 10 CFR 50.55a, continues into the period of extended operation. The NRC Director of the Office of Nuclear Reactor Regulation (NRR) may approve a licensee-proposed alternative to ASME Section XI if it is submitted as a relief request in NUREG-1801, Rev. 2 1-2 December 201 0 OAG10001390_00028

accordance with 10 CFR 50.55a(a)(3). The staff's approval of an alternative program/relief request typically does not extend beyond the current 10-year interval for which the alternative was proposed. For cases in which this interval extends beyond the initial 40-year license period into the renewed license period, the approved relief remains in effect until the end of that interval, consistent with the specific approval (60 FR 22461, 22483).

Pursuant to 10 CFR 50.55a(b)(5), licensees may apply ASME Code cases listed in NRC Regulatory Guide (RG) 1.147, through the most recent endorsed revision, without NRC approval, subject to the limitations contained in the rule. The rule permits licensees to continue to apply the Code case, or a most recent version that is incorporated by the RG, until the end of the 1O-year interval. For cases in which this interval extends beyond the initial 40-year license period into the renewal period, the Code case, or a more recent endorsed version, remains in effect until the end of that interval, consistent with 10 CFR 50.55a(b)(5) and the statements of consideration for the final license renewal rule 60 FR 22461.

December 201 0 1-3 NUREG-1801, Rev. 2 OAG10001390_00029

CHAPTER II CONTAINMENT STRUCTURES December 201 0 II-i NUREG-1801, Rev. 2 OAGI0001390_00030

CONTAINMENT STRUCTURES A. Pressurized Water Reactor (PWR) Containments B. Boiling Water Reactor (BWR) Containments December 201 0 II-iii NUREG-1801, Rev. 2 OAGI0001390_00031

PRESSURIZED WATER REACTOR (PWR) CONTAINMENTS A 1. Concrete Containments (Reinforced and Prestressed)

A2. Steel Containments A3. Common Components December 201 0 II A-i NUREG-1801, Rev. 2 OAGI0001390_00032

A1. CONCRETE CONTAINMENTS (REINFORCED AND PRESTRESSED)

Systems, Structures, and Components This section addresses the elements of pressurized water reactor (PWR) concrete containment structures. Concrete containment structures are divided into three elements: concrete, steel, and prestressing systems.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (VIII.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

December 201 0 II A1-1 NUREG-1801, Rev. 2 OAGI0001390_00033

z II CONTAINMENT STRUCTURES c

U A1 Concrete Containments (Reinforced and Prestressed) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< II.A1.CP- II.A 1-4(C- Concrete Concrete Air - indoor, Increase in porosity Chapter XI.S2, "ASME Section XI, No I\)

87 03) (accessible uncontrolled or and permeability; Subsection IWL" areas): dome; Air - outdoor cracking; loss of wall; basemat; material (spalling, ring girders; scaling) buttresses due to aggressive chemical attack II.A1.CP- II.A1-2(C- Concrete Concrete Air - outdoor Loss of material Chapter XI.S2, "ASME Section XI, No 31 01 ) (accessible (spalling, scaling) Subsection IWL" areas): dome; and cracking wall; basemat; due to freeze-thaw ring girders; buttresses

...... II.A1.CP- II.A1-3(C- Concrete Concrete Any environment Cracking Chapter XI.S2, "ASME Section XI, No I

I\)

33 04) (accessible due to expansion Subsection IWL" areas): dome; from reaction with wall; basemat; aggregates ring girders; buttresses II.A1.CP- II.A 1-6(C- Concrete Concrete Water - flowing Increase in porosity Chapter XI.S2, "ASME Section XI, No 32 02) (accessible and permeability; Subsection IWL" areas): dome; loss of strength wall; basemat; due to leaching of ring girders; calcium hydroxide buttresses and carbonation II.A1.CP- II.A 1-7(C- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 68 05) (accessible steel uncontrolled or bond; and loss of Subsection IWL" 0 areas): dome; Air - outdoor material (spalling, CD C')

CD wall; basemat; scaling) 0 3 ring girders; due to corrosion of G) 0-buttresses; embedded steel CD 0 I\) reinforcing 0 a 0 steel

--" a 0)

CD 0

I 0

0 0

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oCD II CONTAINMENT STRUCTURES C')

CD A1 Concrete Containments (Reinforced and Prestressed) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component II.A1.CP- II.A 1-4(C- Concrete Concrete Air - indoor, Increase in porosity Chapter XI.S2, "ASME Section XI, No 100 03) (inaccessible uncontrolled or and permeability; Subsection IWL," or areas): dome; Air - outdoor or cracking; loss of Chapter XI.S6, " Structures Monitoring" wall; basemat; Ground material (spalling, ring girders; water/soil scaling) buttresses due to aggressive chemical attack II.A1.CP- II.A1-2(C- Concrete Concrete Air - outdoor or Loss of material Further evaluation is required for plants Yes, for plants 147 01 ) (inaccessible Ground (spalling, scaling) that are located in moderate to severe located in areas): dome; water/soil and cracking weathering conditions (weathering index moderate to wall; basemat; due to freeze-thaw >100 day-inch/yr) (NUREG-1557) to severe ring girders; determine if a plant-specific aging weathering buttresses management program is needed. A conditions

...... plant-specific aging management I

CJ.) program is not required if documented evidence confirms that the existing concrete had air entrainment content (as per Table CC-2231-2 of the ASME Section III Division 2), and subsequent inspections of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management z program is required to manage loss of c material (spalling, scaling) and cracking

u m due to freeze-thaw of concrete in G) inaccessible areas.

I 0 00 The weathering index for the continental

>> a US is shown in ASTM C33-90, Fig. 1.

G)

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z II CONTAINMENT STRUCTURES c

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I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< II.A1.CP- II.A1-3(C- Concrete Concrete Any environment Cracking Further evaluation is required to Yes, if I\)

67 04) (inaccessible due to expansion determine if a plant-specific aging concrete is not areas): dome; from reaction with management program is needed to constructed as wall; basemat; aggregates manage cracking and expansion due to stated ring girders; reaction with aggregate of concrete in buttresses Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can

...... demonstrate that those aggregates do I

.j:>. not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

II.A1.CP- II.A 1-6(C- Concrete Concrete Water - flowing Increase in porosity Further evaluation is required to Yes, if 102 02) (inaccessible and permeability; determine if a plant-specific aging leaching is areas): dome; loss of strength management program is needed to observed in wall; basemat; due to leaching of manage increase in porosity, and accessible ring girders; calcium hydroxide permeability due to leaching of calcium areas that buttresses and carbonation hydroxide and carbonation of concrete in impact Inaccessible Areas. A plant-specific intended 0 aging management program is not function CD required if (1) There is evidence in the C')

CD 0 accessible areas that the flowing water

>> 3 0- has not caused leaching and G) ...,

CD 0 I\)

carbonation, or (2) Evaluation 0 a determined that the observed leaching 0

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CD 0

I 0

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oCD II CONTAINMENT STRUCTURES C')

CD A1 Concrete Containments (Reinforced and Prestressed) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

II.A1.CP- II.A 1-7(C- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 97 05) (inaccessible steel uncontrolled or bond; and loss of Subsection IWL," or areas): dome; Air - outdoor material (spalling, Chapter XI.S6, " Structures Monitoring" wall; basemat; scaling) ring girders; due to corrosion of buttresses; embedded steel reinforcing steel II.A1.CP- II.A1-1(C- Concrete: Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if

...... 34 08) dome; wall; uncontrolled or strength and program temperature I

0"1 basemat; ring Air - outdoor modulus limits are girders; due to elevated The implementation of 10 CFR SO.SSa exceeded buttresses temperature and ASME Section XI, Subsection IWL

(>1S0°F general; would not be able to identify the

>200°F local) reduction of strength and modulus of elasticity due to elevated temperature.

Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted. Subsection CC-3400 of ASME Section III, Division 2, specifies z the concrete temperature limits for c normal operation or any other long-term

u m period. The temperatures shall not G)

I exceed 150°F except for local areas, 0 a 00 such as around penetrations, which are G) not allowed to exceed 200°F. If 0

U significant equipment loads are CD 0 supported by concrete at temperatures 0

<

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CD 0

I 0

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z II CONTAINMENT STRUCTURES c

U A1 Concrete Containments (Reinforced and Prestressed) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< exceeding 150°F, an evaluation of the I\)

ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

II.A1.CP- II.A1-5(C- Concrete: Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-101 37) dome; wall; distortion Subsection IWL," or watering

...... basemat; ring due to increased Chapter XI.S6, " Structures Monitoring" system is I

(J) girders; stress levels from If a de-watering system is relied upon for relied upon to buttresses settlement control of settlement, then the licensee control is to ensure proper functioning of the de- settlement watering system through the period of extended operation.

II.A1.C-07 II.A1-8(C- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-

07) foundation; porous foundation strength If a de-watering system is relied upon for watering subfoundation concrete and cracking control of erosion of cement from porous system is due to differential concrete subfoundations, then the relied upon to settlement and licensee is to ensure proper functioning control erosion of porous of the de-watering system through the settlement concrete period of extended operation.

subfoundation 0 II.A 1.C-11 II.A1-9(C- Prestressing Steel Air - indoor, Loss of prestress Loss of tendon prestress is a time- Yes, TLAA CD C') 11 ) system: uncontrolled or due to relaxation; limited aging analysis (TLAA) to be CD 0 3 tendons Air - outdoor shrinkage; creep; evaluated for the period of extended G) 0-elevated operation.

CD 0 I\) temperature See the SRP, Section 4.5, "Concrete 0 a Containment Tendon Prestress" for 0

--" a 0)

CD 0

I 0

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oCD II CONTAINMENT STRUCTURES C')

CD A1 Concrete Containments (Reinforced and Prestressed) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component acceptable methods for meeting the requirements of 10 CFR 54.21 (c) (1 )(i) and (ii). See Chapter X.S1 of this report for meeting the requirements of 10 CFR 54.21 (c)(1)(iii).

For periodic monitoring of prestress, see Chapter XI.S2.

II.A1.C-10 II.A1- Prestressing Steel Air - indoor, Loss of material Chapter XI.S2, "ASME Section XI, No 10(C-1 0) system: uncontrolled or due to corrosion Subsection IWL" tendons; Air - outdoor anchorage components II.A1.CP- II.A1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No

...... 35 11 (C-09) (accessible uncontrolled due to general, Subsection IWE," and I

-J areas): liner; pitting, and crevice Chapter XI.S4, "10 CFR Part 50, liner anchors; corrosion AppendixJ" integral attachments II.A1.CP- II.A1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 98 11 (C-09) (inaccessible uncontrolled due to general, Subsection IWE" and corrosion is areas): liner; pitting, and crevice indicated from liner anchors; corrosion Chapter XI.S4, "10 CFR Part 50, the IWE integral AppendixJ" examinations attachments Additional plant-specific activities are z warranted if loss of material due to c corrosion is significant for inaccessible

u m areas (embedded containment steel G)

I shell or liner).

0 a 00 G) Loss of material due to corrosion is not

U significant if the following conditions are 0 CD 0

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z II CONTAINMENT STRUCTURES c

U A1 Concrete Containments (Reinforced and Prestressed) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< 1. Concrete meeting the requirements of I\)

ACI 318 or 349 and the guidance of 201.2R was used for the containment concrete in contact with the embedded containment shell or liner.

2. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.

3. The concrete is monitored to ensure that it is free of penetrating cracks that

...... provide a path for water seepage to the I

00 surface of the containment shell or liner.

4. Borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified significant corrosion in some plants.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

0 CD C')

CD 0 3 G) 0-CD 0 I\)

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A2. STEEL CONTAINMENTS Systems, Structures, and Components This section addresses the elements of pressurized water reactor (PWR) steel containment structures. Steel containment structures are divided into two elements: steel and concrete.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (VIII.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

December 201 0 II A2-1 NUREG-1801, Rev. 2 OAGI0001390_00041

z c II CONTAINMENT STRUCTURES

U m A2 Steel Containments G)

I 00 a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

u Mechanism Evaluation Component CD

< II.A2.CP-51 II.A2-2(C- Concrete Concrete Air - outdoor Loss of material Chapter XI.S2, "ASME Section XI, No I\)

28) (accessible (spalling, scaling) Subsection IWL" areas): and cracking basemat due to freeze-thaw II.A2.CP-58 II.A2-3(C- Concrete Concrete Any Cracking Chapter XI.S2, "ASME Section XI, No

38) (accessible environment due to expansion Subsection IWL" areas): from reaction with basemat aggregates II.A2.CP-72 II.A2-4(C- Concrete Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, No

25) (accessible water/soil porosity and Subsection IWL," or areas): permeability; Chapter XI.S6, " Structures

>> basemat cracking; loss of Monitoring" I\)

I material (spalling, I\)

scaling) due to aggressive chemical attack II.A2.CP-155 II.A2-6(C- Concrete Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, No

30) (accessible porosity and Subsection IWL" areas): permeability; loss basemat of strength due to leaching of calcium hydroxide and carbonation II.A2.CP-74 II.A2-7(C- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No

43) (accessible steel uncontrolled or bond; and loss of Subsection IWL" areas): Air - outdoor material (spalling, 0 basemat; scaling)

CD C')

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CD A2 Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component II.A2.CP-70 II.A2-2(C- Concrete Concrete Air - outdoor or Loss of material Further evaluation is required for Yes, for plants

28) (inaccessible Ground (spalling, scaling) plants that are located in moderate to located in areas): water/soil and cracking severe weathering conditions moderate to basemat due to freeze- (weathering index >100 day-inch/yr) severe thaw (NUREG-1557) to determine if a weathering plant-specific aging management conditions program is needed. A plant-specific aging management program is not required if documented evidence confirms that the existing concrete had air entrainment content (as per Table CC-2231-2 of the ASME Section III Division 2), and I\) subsequent inspections of accessible I

CJ.) areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the z continental US is shown in ASTM c C33-90, Fig. 1.

u m II.A2.CP-104 II.A2-3(C- Concrete Concrete Any Cracking Further evaluation is required to Yes, if G)

38) (inaccessible environment due to expansion determine if a plant-specific aging concrete is I

0 00 areas): from reaction with management program is needed to not

>> a basemat aggregates manage cracking and expansion due constructed G) 0

U to reaction with aggregate of concrete as stated CD 0

< in Inaccessible Areas. A plant-specific 0

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U A2 Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< aging management program is not I\)

required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place I\) concrete can perform its intended I

.j:>. function .

II.A2.CP-71 II.A2-4(C- Concrete Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, No

25) (inaccessible water/soil porosity and Subsection IWL," or areas): permeability; Chapter XI.S6, Structures II basemat cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack II.A2.CP-53 II.A2-6(C- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

30) (inaccessible porosity and determine if a plant-specific aging leaching is areas): permeability; loss management program is needed to observed in basemat of strength manage increase in porosity, and accessible 0 due to leaching of permeability due to leaching of areas that CD C')

calcium hydroxide calcium hydroxide and carbonation of impact CD and carbonation concrete in Inaccessible Areas. A intended 0

G) 3 0- plant-specific aging management function CD program is not required if 0 I\)

0 a (1) There is evidence in the 0

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CD A2 Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component accessible areas of adjacent structures that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

II.A2.CP-75 II.A2-7(C- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No

43) (inaccessible steel uncontrolled or bond; and loss of Subsection IWL," or areas): Air - outdoor material (spalling, Chapter XI.S6, " Structures I\) basemat; scaling) Monitoring" I

0"1 reinforcing due to corrosion steel of embedded steel II.A2.CP-69 II.A2-5(C- Concrete: Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-

36) basemat distortion Subsection IWL," or watering due to increased Chapter XI.S6, " Structures system is stress levels from Monitoring" relied upon to settlement If a de-watering system is relied upon control for control of settlement, then the settlement licensee is to ensure proper functioning of the de-watering system z through the period of extended c operation.

u m II.A2.C-07 II.A2-8(C- Concrete

Concrete; Water - flowing Reduction of Chapter XI.S6, " Structures Yes, if a de-G)

I

07) foundation; porous foundation Monitoring" watering 0 a 00 subfoundation concrete strength and If a de-watering system is relied upon system is G) cracking for control of erosion of cement from relied upon to

U due to differential porous concrete subfoundations, then control 0 CD 0

0  :< settlement and the licensee is to ensure proper settlement

--" I\)

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z II CONTAINMENT STRUCTURES c

U A2 Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< erosion of porous functioning of the de-watering system I\)

concrete through the period of extended su bfou ndation operation.

II.A2.CP-35 II.A2-9(C- Steel Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No

09) elements uncontrolled due to general, Subsection IWE," and (accessible pitting, and Chapter XI.S4, "10 CFR Part 50, areas): liner; crevice corrosion AppendixJ" liner anchors; integral attachments II.A2.CP-98 II.A2-9(C- Steel Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if

09) elements uncontrolled due to general, Subsection IWE" and corrosion is

>> (inaccessible pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from I\)

I (J) areas): liner; crevice corrosion Appendix J" the IWE liner anchors; Additional plant-specific activities are examinations integral warranted if loss of material due to attachments corrosion is significant for inaccessible areas (embedded containment steel shell or liner).

Loss of material due to corrosion is not significant if the following conditions are satisfied:

1. Concrete meeting the requirements of ACI 318 or 349 and the guidance of 201.2R was used for the containment concrete in contact with the embedded containment shell or liner.

0 2. The moisture barrier, at the junction CD C')

CD where the shell or liner becomes 0 embedded, is subject to aging G) 3 0-management activities in accordance CD 0 I\) with ASME Section XI, Subsection 0 a 0 IWE requirements.

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CD 0

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oCD II CONTAINMENT STRUCTURES C')

CD A2 Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component

3. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

4. Borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified significant corrosion in some plants.

If any of the above conditions cannot I\) be satisfied, then a plant-specific I

-J aging management program for corrosion is necessary.

z c

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A3. COMMON COMPONENTS Systems, Structures, and Components This section addresses the common components of pressurized water reactor (PWR) containment structures. The common components include penetration sleeves and bellows; dissimilar metal welds; personnel airlock; equipment hatch; seals, gaskets, and moisture barriers.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (VIII.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

December 201 0 II A3-1 NUREG-1801, Rev. 2 OAGI0001390_00048

z II CONTAINMENT STRUCTURES c

U A3 Common Components m

G)

I 00 Structure a Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< II.A3.CP-40 II.A3-7(C- Moisture Elastomers, Air - indoor, Loss of sealing Chapter XI.S1, "ASME Section XI, No i\J

18) barriers rubber and uncontrolled due to wear, Subsection IWE" (caulking, other similar damage, flashing, and materials erosion, tear, other surface cracks, sealants) or other defects II.A3.CP-36 II.A3-1 (C- Penetration Steel; Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No

12) sleeves dissimilar uncontrolled or due to general, Subsection IWE," and metal welds Air - outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice Appendix J" corrosion II.A3.CP-38 II.A3-2(C- Penetration Stainless Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, Yes, detection

15) sleeves; steel; uncontrolled or due to stress Subsection IWE," and of aging CJ.) penetration dissimilar Air - outdoor corrosion Chapter XI.S4, "10 CFR Part 50, effects is to be I

I\)

bellows metal welds cracking AppendixJ" evaluated II.A3.CP-37 II.A3-3(C- penetration Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No

14) sleeves; stainless uncontrolled or due to cyclic Subsection IWE," and penetration steel; Air - outdoor loading Chapter XI.S4, "10 CFR Part 50, bellows dissimilar (CLB fatigue Appendix J" metal welds analysis does not exist)

II.A3.C-13 II.A3-4(C- Penetration Steel; Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA

13) sleeves; stainless uncontrolled or fatigue damage (TLAA) to be evaluated for the period penetration steel; Air - outdoor due to fatigue of extended operation. See the SRP, bellows dissimilar (Only ifCLB Section 4.6, "Containment Liner Plate metal welds fatigue analysis and Penetration Fatigue Analysis" for exists) acceptable methods for meeting the 0 requirements of 10 CFR 54.21 (c)(1).

CD C')

CD II.A3.C-16 II.A3-6(C- Personnel Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 0 16) airlock, uncontrolled or due to general, Subsection IWE," and

>> 3 0-G) ...,

CD equipment Air - outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, 0 I\) hatch, CRD crevice Appendix J" 0 a 0 hatch corrosion

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CD A3 Common Components 3

0-CD Structure I\) Aging Effect! Further a Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component II.A3.CP-39 II.A3-5(C- Personnel Steel Air - indoor, Loss of leak Chapter XI.S1, "ASME Section XI, No

17) airlock, uncontrolled or tightness Subsection IWE," and equipment Air - outdoor due to Chapter XI.S4, "10 CFR Part 50, hatch, CRD mechanical wear Appendix J" hatch: locks, of locks, hinges hinges, and and closure closure mechanisms mechanisms II.A3.CP-150 Pressure- Any Any Loss of preload Chapter XI.S1, "ASME Section XI, No retaining environment due to self- Subsection IWE," and bolting loosening Chapter XI.S4, "10 CFR Part 50, AppendixJ" II.A3.CP-148 Pressure- Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No

>>CJ.) retaining uncontrolled or due to general, Subsection IWE" I

CJ.)

bolting Air - outdoor pitting, and crevice corrosion II.A3.CP-41 II.A3-7(C- Seals and Elastomers, Air - indoor, Loss of sealing Chapter XI.S4, "10 CFR Part 50, No

18) gaskets rubber and uncontrolled or due to wear, AppendixJ" other similar Air - outdoor damage, materials erosion, tear, surface cracks, or other defects II.A3.CP-152 Service Level Coatings Air - indoor, Loss of coating Chapter XI.S8, "Protective Coating No I coatings uncontrolled integrity Monitoring and Maintenance" z due to blistering, c cracking, flaking,

u m peeling, or G)

I physical damage 0 00 G) a 0 ;U 0 CD 0 <

--" i\J 0)

CD 0

I 0

0 0

(J1 0

BOILING WATER REACTOR (BWR) CONTAINMENTS

81. Mark I Containments

82. Mark II Containments

83. Mark III Containments

84. Common Components December 201 0 DRAFT II B1-i NUREG-1801, Rev. 2 OAGI0001390_00051

81. MARK I CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark I containment structures. Steel containments are discussed in II.B1.1 and concrete containments are discussed in II.B1.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

December 201 0 II 81-1 NUREG-1801, Rev. 2 OAGI0001390_00052

z II CONTAINMENT STRUCTURES c B1.1 Mark I Steel Containments

U m

G)

I Structure 00 a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD II.B1.1.CP-43 II.B1.1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No I\) 2(C-19) (accessible uncontrolled due to general, Subsection IWE," and areas)

drywell pitting, and Chapter XI.S4, "10 CFR Part 50, shell; drywell crevice Appendix J" head; drywell corrosion shell in sand pocket regions; II.B1.1.C-23 II.B1.1- Steel elements: Steel Air - indoor, Fretting or Chapter XI.S1, "ASME Section XI, No 1 (C-23) drywell head; uncontrolled lockup Subsection IWE" downcomers due to mechanical wear II.B1.1.CP-44 Steel elements: Steel Concrete None None No drywell support I

I\) skirt II.B1.1.CP-109 II.B1.1- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 2(C-19) torus ring uncontrolled or due to general, Subsection IWE" corrosion is girders; Treated water pitting, and significant downcomers; crevice Plant specific aging management corrosion program is required if plant operating experience identified significant corrosion of the torus ring girders and downcomers. If protective coating is credited for preventing corrosion of the torus shell, the coating should be included in scope of license renewal and subject to aging management 0 review.

CD C') II.B1.1.CP-48 II.B1.1- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 0 CD G) 3 0-2(C-19) torus shell uncontrolled or due to general, Subsection IWE," and corrosion is Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, significant 0

CD 0 I\) crevice Appendix J" Recoating of 0 a corrosion Significant corrosion of the torus shell the torus is

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I 0

0 0

(J1 0)

oCD II CONTAINMENT STRUCTURES C')

CD B1.1 Mark I Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component and degradation of its protective recommended.

coating are identified in IN 88-82. Other industrywide operating indicates a number of incidences of torus corrosion. License renewal applicants are advised to address their plant specific operating experience related to the torus shell corrosion. If the identified corrosion is significant, a plant specific aging management is required. If protective coating is credited for preventing corrosion of the torus shell, the coating should be included in scope of license renewal I

CJ.) and subject to aging management review.

II.B1.1.CP-49 II.B1.1- Steel elements: Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No 3(C-20) torus; vent line; stainless uncontrolled due to cyclic Subsection IWE," and vent header; steel loading Chapter XI.S4, "10 CFR Part 50, vent line (CLB fatigue Appendix J" bellows; analysis does downcomers not exist)

II.B1.1.C-21 II.B1.1- Steel elements: Steel; Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA 4(C-21) torus; vent line; stainless uncontrolled fatigue damage (TLAA) to be evaluated for the period of vent header; steel due to fatigue extended operation. See the SRP, z vent line (Only ifCLB Section 4.6, "Containment Liner Plate c bellows; fatigue analysis and Penetration Fatigue Analysis" for

u m downcomers exists) acceptable methods for meeting the G)

I requirements of 10 CFR 54.21 (c)(1).

0 a 00 II.B1.1.CP-50 II.B1.1- Steel elements: Stainless Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No G) 5(C-22) vent line steel uncontrolled due to stress Subsection IWE," and 0

U bellows corrosion Chapter XI.S4, "10 CFR Part 50, CD 0 cracking AppendixJ" 0

<

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U II CONTAINMENT STRUCTURES m B1.2 Mark I Concrete Containments G)

I 00 a Structure Aging Effect/ Further

u Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation CD Component I\) II.B1.2.CP-79 II.B1.2- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 2(C-41) (accessible steel uncontrolled or bond; and loss of Subsection IWL" areas): Air - outdoor material (spalling, basemat; scaling) reinforcing steel due to corrosion of embedded steel II.B1.2.CP-S9 II.B1.2- Concrete Concrete Any Cracking Chapter XI.S2, "ASME Section XI, No 4(C-39) (accessible environment due to expansion Subsection IWL" areas): from reaction with containment; aggregates wall; basemat II.B1.2.CP-S4 II.B1.2- Concrete Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, No I

.j:>. 6(C-31) (accessible porosity and Subsection IWL" areas): permeability; loss containment; of strength wall; basemat due to leaching of calcium hydroxide and carbonation II.B1.2.CP-80 II.B1.2(C- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S6, "Structures No

41) (inaccessible steel uncontrolled or bond; and loss of Monitoring" areas): Air - outdoor material (spalling, basemat; scaling) reinforcing steel due to corrosion of embedded steel 0

II.B1.2.CP-99 II.B1.2- Concrete Concrete Any Cracking Further evaluation is required to Yes, if CD C')

4(C-39) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not 0 CD areas): from reaction with management program is needed to constructed as G) 3 0- containment; aggregates manage cracking and expansion due stated 0

CD wall; basemat to reaction with aggregate of concrete 0 I\)

0 a in Inaccessible Areas. A plant-specific

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oCD II CONTAINMENT STRUCTURES C')

CD B1.2 Mark I Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended I

0"1 function.

II.B1.2.CP-110 II.B1.2- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if 6(C-31) (inaccessible porosity and determine if a plant-specific aging leaching is areas): permeability; loss management program is needed to observed in containment; of strength manage increase in porosity, and accessible wall; basemat due to leaching of permeability due to leaching of areas that calcium hydroxide calcium hydroxide and carbonation of impact and carbonation concrete in Inaccessible Areas. A intended plant-specific aging management function program is not required if (1) There is evidence in the accessible areas that z the flowing water has not caused c leaching and carbonation, or (2)

u m Evaluation determined that the G) observed leaching of calcium I

0 00 hydroxide and carbonation in

>> a accessible areas has no impact on G)

U the intended function of the concrete 0 CD 0

< structure.

0

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I 0

0 0

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z II CONTAINMENT STRUCTURES c B1.2 Mark I Concrete Containments

U m

G)

I Structure 00 a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD II.B1.2.CP-10S II.B1.2- Concrete Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-I\) 1(C-06) elements, all distortion Subsection IWL," or watering due to increased Chapter XI.S6, " Structures system is stress levels from Monitoring" relied upon to settlement If a de-watering system is relied upon control for control of settlement, then the settlement licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

II.B1.2.CP-106 II.B1.2- Concrete: Concrete Air - indoor, Increase in Chapter XI.S2, "ASME Section XI, No S(C-26) containment; uncontrolled or porosity and Subsection IWL," or wall; basemat Air - outdoor permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" I

(J) material (spalling, scaling) due to aggressive chemical attack II.B1.2.CP-S7 II.B1.2- Concrete: Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if 3(C-3S) containment; uncontrolled or strength and program temperature wall; basemat Air - outdoor modulus limits are due to elevated The implementation of exceeded temperature 10 CFR SO.SSa and ASME Code,

(>1S0°F general; Section XI, Subsection IWL would not

>200°F local) be able to identify the reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed 0 specified temperature limits, further CD C')

0 CD evaluations are warranted.

G) 3 0-Subsection CC-3400 of ASME 0

CD Section III, Division 2, specifies the I\)

0 a concrete temperature limits for normal 0

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oCD II CONTAINMENT STRUCTURES C')

CD B1.2 Mark I Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200°F. If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete

-J I

if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity, and these reductions are applied to the design calculations.

II.B1.2.C-07 II.B1.2- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Yes, if a de-7(C-07) foundation; porous foundation Monitoring" watering subfoundation concrete strength and If a de-watering system is relied upon system is cracking for control of erosion of cement from relied upon to due to differential porous concrete subfoundations, then control settlement and the licensee is to ensure proper settlement z erosion of porous functioning of the de-watering system c concrete through the period of extended

u m subfoundation operation.

G)

I II.B1.2.CP-46 II.B1.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 0 00 8(C-46) (accessible uncontrolled or due to general, Subsection IWE," and

>> a areas): Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, G) 0

U suppression crevice corrosion AppendixJ" CD 0

< chamber; 0

--" I\)

0)

CD 0

I 0

0 0

(J1 CD

z II CONTAINMENT STRUCTURES c B1.2 Mark I Concrete Containments

U m

G)

I Structure 00 a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD drywell; drywell I\) head; embedded shell; region shielded by diaphragm floor (as applicable)

II.B1.2.CP-114 Steel elements Steel Concrete None None No (inaccessible areas): support skirt II.B1.2.CP-63 II.B1.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 8(C-46) (inaccessible uncontrolled or due to general, Subsection IWE" and corrosion is areas): Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from 00 I

suppression crevice corrosion AppendixJ" the IWE chamber; Additional plant-specific activities are examinations drywell; drywell warranted if loss of material due to head; corrosion is significant for embedded inaccessible areas (embedded shell; region containment steel shell or liner).

shielded by Loss of material due to corrosion is diaphragm floor not significant if the following (as applicable) conditions are satisfied:

1. Concrete meeting the requirements of ACI 318 or 349 and the guidance of 201 .2R was used for the concrete in contact with the embedded containment shell or liner.

0 2. The moisture barrier, at the CD C')

0 CD unction where the shell or liner G) 3 0-becomes embedded, is subject to 0

CD aging management activities in I\)

0 a accordance with ASME Section XI, 0

--" a 0)

CD 0

I 0

0 0

(J1 CD

oCD II CONTAINMENT STRUCTURES C')

CD B1.2 Mark I Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component Subsection IWE requirements.

3. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

4. Borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified significant corrosion in some plants.

I CD If any of the above cond itions can not be satisfied, then a plant-specific aging management program for corrosion is necessary.

II.B1.2.CP-117 II.B1.2- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 8(C-46) downcomer uncontrolled or due to general, Subsection IWE" pipes Treated water pitting, and crevice corrosion II.B1.2.C-23 II.B1.2- Steel elements: Steel Air - indoor, Fretting or lockup Chapter XI.S1, "ASME Section XI, No 9(C-23) drywell head; uncontrolled due to mechanical Subsection IWE" downcomers wear z II.B1.2.C-49 II.B1.2- Steel elements: Steel; Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No c

u 10(C-49) suppression stainless uncontrolled or due to general Subsection IWE," and m chamber (torus) steel Treated water (steel only), Chapter XI.S4, "10 CFR Part 50, G)

I liner (interior pitting, and AppendixJ" 0 a 00 surface) crevice corrosion G)

U 0 CD 0

0  :<

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0)

CD 0

I 0

0 0

(J) 0

82. MARK II CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark II containment structures. Mark II steel containments are discussed in II. B2.1. Mark II concrete containments are discussed in II.B2.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

December 201 0 II 82-1 NUREG-1801, Rev. 2 OAGI0001390_00061

z II CONTAINMENT STRUCTURES c

U B2.1 Mark II Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< II.B2.1.CP-46 II.B2.1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No I\)

1(C-46) (accessible uncontrolled or due to general, Subsection IWE," and areas): Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, suppression crevice AppendixJ" chamber; corrosion drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

II.B2.1.CP-114 Steel elements Steel Concrete None None No III (inaccessible I\)

I I\) areas): support skirt II.B2.1.CP-63 II.B2.1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 1(C-46) (inaccessible uncontrolled or due to general, Subsection IWE" and corrosion is areas): Treated water pitting, and indicated from suppression crevice Chapter XI.S4, "10 CFR Part 50, the IWE chamber; corrosion AppendixJ" examinations drywell; drywell head; Additional plant-specific activities are embedded warranted if loss of material due to shell; region corrosion is significant for inaccessible shielded by areas (embedded containment steel diaphragm floor shell or liner).

(as applicable) 0 CD C')

Loss of material due to corrosion is not 0 CD significant if the following conditions are G) 3 0- satisfied:

CD

1. Concrete meeting the requirements 0 I\)

0 a of ACI 318 or 349 and the guidance of 0

--" a 0)

CD 0

I 0

0 0

(J)

N

oCD II CONTAINMENT STRUCTURES C')

CD B2.1 Mark II Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component 201.2R was used for the concrete in contact with the embedded containment shell or liner.

2. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.

3. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

III I\)

4. Borated water spills and water I

CJ.) ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified significant corrosion in some plants.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

z II.B2.1.CP-117 II.B2.1- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No c 1(C-46) downcomer uncontrolled or due to general, Subsection IWE"

u m pipes Treated water pitting, and G) crevice I

0 00 corrosion

>> a II.B2.1.C-23 II.B2.1- Steel elements: Steel Air - indoor, Fretting or Chapter XI.S1, "ASME Section XI, No G) 0

U 2(C-23) drywell head; uncontrolled lockup Subsection IWE" CD 0

< downcomers due to 0

--" I\)

0)

CD 0

I 0

0 0

(J) 0)

z II CONTAINMENT STRUCTURES c

U B2.1 Mark II Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< mechanical I\)

wear II.B2.1.CP-107 II.B2.1- Suppression Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No 3(C-44) pool shell stainless uncontrolled or due to cyclic Subsection IWE," and steel; Treated Water loading Chapter XI.S4, "10 CFR Part 50, dissimilar (CLB fatigue AppendixJ" metal analysis does welds not exist)

II.B2.1.C-45 II.B2.1- Suppression Steel; Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA 4(C-45) pool shell; stainless uncontrolled fatigue damage (TLAA) to be evaluated for the period of unbraced steel; due to fatigue extended operation. See the SRP, III downcomers dissimilar (Only ifCLB Section 4.6, "Containment Liner Plate I\)

I metal fatigue analysis and Penetration Fatigue Analysis" for

.j:>.

welds exists) acceptable methods for meeting the requirements of 10 CFR 54.21 (c) (1 ).

II.B2.1.CP-142 II.B2.1- Unbraced Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No 3(C-44) downcomers stainless uncontrolled or due to cyclic Subsection IWE" steel; Treated water loading dissimilar (CLB fatigue metal analysis does welds not exist) 0 CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 0

(J)

.j::>.

oCD II CONTAINMENT STRUCTURES C')

CD B2.2 Mark II Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component II.B2.2.CP-79 II.B2.2- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 2(C-41) (accessible steel uncontrolled or bond; and loss of Subsection IWL" areas): Air - outdoor material (spalling, basemat; scaling) reinforcing steel due to corrosion of embedded steel II.B2.2.CP-S9 II.B2.2- Concrete Concrete Any Cracking Chapter XI.S2, "ASME Section XI, No 4(C-39) (accessible environment due to expansion Subsection IWL" areas): from reaction with containment; aggregates wall; base mat II.B2.2.CP-S4 II.B2.2- Concrete Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, No III I\) 6(C-31) (accessible porosity and Subsection IWL" I

0"1 areas): permeability; loss containment; of strength wall; base mat due to leaching of calcium hydroxide and carbonation II.B2.2.CP-80 II.B2.2- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No 2(C-41) (inaccessible steel uncontrolled or bond; and loss of areas): Air - outdoor material (spalling, basemat; scaling) reinforcing steel due to corrosion of embedded z steel c II.B2.2.CP-99 II.B2.2- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

u m 4(C-39) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not G)

I areas): from reaction with management program is needed to constructed as 0 a 00 containment; aggregates manage cracking and expansion due stated G) wall; base mat to reaction with aggregate of concrete

U in Inaccessible Areas. A plant-specific 0 CD 0

0  :< aging management program is not

--" I\)

0)

CD 0

I 0

0 0

(J)

(J1

z II CONTAINMENT STRUCTURES c

U B2.2 Mark II Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< required if (1) as described in NUREG-I\)

1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III II.B2.2.CP-110 II.B2.2- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if I\)

I (J) 6(C-31) (inaccessible porosity and determine if a plant-specific aging leaching is areas): permeability; loss management program is needed to observed in containment; of strength manage increase in porosity, and accessible wall; base mat due to leaching of permeability due to leaching of calcium areas that calcium hydroxide hydroxide and carbonation of concrete impact and carbonation in Inaccessible Areas. A plant-specific intended aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on 0

CD the intended function of the concrete C')

0 CD structure.

G) 3 0- II.B2.2.CP-105 II.B2.2- Concrete Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-CD 1(C-06) elements, all distortion Subsection IWL," or watering 0 I\)

0 a due to increased Chapter XI.S6, " Structures Monitoring" system is 0

--" a 0)

CD 0

I 0

0 0

(J)

(J)

oCD II CONTAINMENT STRUCTURES C')

CD B2.2 Mark II Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component stress levels from If a de-watering system is relied upon relied upon to settlement for control of settlement, then the control licensee is to ensure proper settlement functioning of the de-watering system through the period of extended operation.

II.B2.2.CP-106 II.B2.2- Concrete: Concrete Air - indoor, Increase in Chapter XI.S2, "ASME Section XI, No S(C-26) containment; uncontrolled or porosity and Subsection IWL," or wall; base mat Air - outdoor permeability; Chapter XI.S6, " Structures Monitoring" cracking; loss of material (spalling, scaling) due to aggressive III chemical attack I\)

I

-J II.B2.2.CP-S7 II.B2.2- Concrete: Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if 3(C-3S) containment; uncontrolled or strength and program temperature wall; base mat Air - outdoor modulus limits are due to elevated The implementation of 10 CFR SO.SSa exceeded temperature and ASME Section XI, Subsection IWL

(>1S0°F general; would not be able to identify the

>200°F local) reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

z Subsection CC-3400 of ASME c Section III, Division 2, specifies the

u m concrete temperature limits for normal G)

I operation or any other long-term 0 00 period. The temperatures shall not

>> a exceed 150°F except for local areas, G) 0

U such as around penetrations, which CD 0

< are not allowed to exceed 200°F. If 0

--" I\)

0)

CD 0

I 0

0 0

(J)

-....J

z II CONTAINMENT STRUCTURES c

U B2.2 Mark II Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< significant equipment loads are I\)

supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity, and these reductions are applied to the design calculations.

III II.B2.2.C-07 II.B2.2- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-I\)

I 00 7(C-07) foundation; porous foundation If a de-watering system is relied upon watering su bfou ndation concrete strength and for control of erosion of cement from system is cracking porous concrete subfoundations, then relied upon to due to differential the licensee is to ensure proper control settlement and functioning of the de-watering system settlement erosion of porous through the period of extended concrete operation.

subfoundation II.B2.2.C-11 II.B2.2- Prestressing Steel Air - indoor, Loss of prestress Loss of tendon prestress is a time- Yes, TLAA 8(C-11) system: uncontrolled or due to relaxation; limited aging analysis (TLAA) to be tendons Air - outdoor shrinkage; creep; evaluated for the period of extended elevated operation.

temperature See the SRP, Section 4.5, "Concrete Containment Tendon Prestress" for 0

CD C')

acceptable methods for meeting the 0 CD requirements of 10 CFR 54.21 (c)(1)(i)

G) 3 0- and (ii). See Chapter X.S1 of this CD report for meeting the requirements of 0 I\)

0 a 10 CFR 54.21 (c)(1)(iii).

0

--" a 0)

CD 0

I 0

0 0

(J)

CD

oCD II CONTAINMENT STRUCTURES C')

CD B2.2 Mark II Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component For periodic monitoring of prestress, see Chapter XI.S2.

II.B2.2.C-10 II.B2.2- Prestressing Steel Air - indoor, Loss of material Chapter XI.S2, "ASME Section XI, No 9(C-10) system: uncontrolled or due to corrosion Subsection IWL" tendons; Air - outdoor anchorage components II.B2.2.CP-46 II.B2.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 10(C-46) (accessible uncontrolled or due to general, Subsection IWE," and areas): Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, suppression crevice corrosion AppendixJ" III chamber; I\)

I drywell; drywell CD head; embedded shell; region shielded by diaphragm floor I(as applicable)

II.B2.2.CP-114 Steel elements Steel Concrete None None No (inaccessible areas): support skirt II.B2.2.CP-63 II.B2.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if z 10(C-46) (inaccessible uncontrolled or due to general, Subsection IWE" and corrosion is c

u areas)

Treated water pitting, and indicated from m

G) suppression crevice corrosion Chapter XI.S4, "10 CFR Part 50, the IWE I

chamber; AppendixJ" examinations 0 a 00 drywell; drywell G) head; Additional plant-specific activities are

U 0 CD embedded warranted if loss of material due to 0

0  :< shell; region corrosion is significant for inaccessible

--" I\)

0)

CD 0

I 0

0 0

(J)

CD

z II CONTAINMENT STRUCTURES c

U B2.2 Mark II Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< shielded by areas (embedded containment steel I\)

diaphragm floor shell or liner).

(as applicable)

Loss of material due to corrosion is not significant if the following conditions are satisfied:

1. Concrete meeting the requirements of ACI 318 or 349 and the guidance of 201 .2R was used for the concrete in contact with the embedded containment shell or liner.

2. The moisture barrier, at the junction where the shell or liner becomes III I\) embedded, is subject to aging I

management activities in accordance a

with ASME Section XI, Subsection IWE requirements.

3. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

4. Borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified 0

CD significant corrosion in some plants.

C')

CD 0

G) 3 0-If any of the above cond itions can not CD be satisfied, then a plant-specific aging 0 I\)

0 a management program for corrosion is 0

--" a necessary.

0)

CD 0

I 0

0 0

-....J 0

oCD II CONTAINMENT STRUCTURES C')

CD B2.2 Mark II Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component II.B2.2.CP-117 II.B2.2- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 10(C-46) downcomer uncontrolled or due to general, Subsection IWE" pipes Treated water pitting, and crevice corrosion II.B2.2.C-23 II.B2.2- Steel elements: Steel Air - indoor, Fretting or lockup Chapter XI.S1, "ASME Section XI, No 11 (C-23) drywell head; uncontrolled due to mechanical Subsection IWE" downcomers wear II.B2.2.C-49 II.B2.2- Steel elements: Steel; Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 12(C-49) suppression stainless uncontrolled or due to general Subsection IWE," and chamber (torus) steel Treated water (steel only), Chapter XI.S4, "10 CFR Part 50, liner (interior pitting, and AppendixJ" surface) crevice corrosion III I\)

II.B2.2.CP-64 II.B2.2- Steel elements: Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No I

13(C-47) vent header; stainless uncontrolled or due to cyclic Subsection IWE" downcomers steel Treated water loading (CLB fatigue analysis does not exist)

II.B2.2.C-48 II.B2.2- Steel elements: Steel; Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA 14(C-48) vent header; stainless uncontrolled or fatigue damage (TLAA) to be evaluated for the period downcomers steel Treated water due to fatigue of extended operation. See the SRP, (Only ifCLB Section 4.6, "Containment Liner Plate fatigue analysis and Penetration Fatigue Analysis" for exists) acceptable methods for meeting the requirements of 10 CFR 54.21 (c)(1).

z c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

-....J

83. MARK III CONTAINMENTS 83.1 Steel Containments 83.2 Concrete Containments December 201 0 II 83-i NUREG-1801, Rev. 2 OAGI0001390_00072

83. MARK III CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark III containment structures. Mark III steel containments are discussed in II.B3.1. Mark III concrete containments are discussed in II.B3.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

December 201 0 II 83-1 NUREG-1801, Rev. 2 OAGI0001390_00073

z II CONTAINMENT STRUCTURES c

U 83.1 Mark III Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< 11.83.1.CP-72 11.83.1- Concrete Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, No I\)

1 (C-2S) (accessible water/soil porosity and Subsection IWL," or areas): permeability; Chapter XI.S6, " Structures basemat cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack 11.83.1.CP-1S6 11.83.1- Concrete Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, No 3(C-30) (accessible porosity and Subsection IWL" areas): permeability; loss basemat of strength due to leaching of III calcium hydroxide CJ.)

I I\) and carbonation 11.83.1.CP-66 11.83.1- Concrete Concrete Any Cracking Chapter XI.S2, "ASME Section XI, No S(C-S1) (accessible environment due to expansion Subsection IWL" areas): from reaction with basemat, aggregates concrete fill-in annulus 11.83.1.CP-74 11.83.1- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 6(C-43) (accessible steel uncontrolled or bond; and loss of Subsection IWL" areas): Air - outdoor material (spalling, basemat; scaling) reinforcing steel due to corrosion of embedded 0 steel CD C') 11.83.1.CP-71 11.83.1- Concrete Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, No CD 0 1 (C-2S) (inaccessible water/soil porosity and Subsection IWL," or G) 3 0- areas): permeability; Chapter XI.S6, " Structures CD Monitoring" 0 I\)

basemat cracking; loss of 0 a material (spalling, 0

--" a 0)

CD 0

I 0

0 0

-....J

.j::>.

oCD II CONTAINMENT STRUCTURES C')

CD 83.1 Mark III Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component scaling) due to aggressive chemical attack 11.83.1.CP-53 11.83.1- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if 3(C-30) (inaccessible porosity and determine if a plant-specific aging leaching is areas): permeability; loss management program is needed to observed in basemat of strength manage increase in porosity, and accessible due to leaching of permeability due to leaching of areas that calcium hydroxide calcium hydroxide and carbonation of impact and carbonation concrete in Inaccessible Areas. A intended plant-specific aging management function program is not required if (1) There is evidence in the III CJ.)

I accessible areas of adjacent CJ.)

structures that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

11.83.1.CP-83 11.83.1- Concrete Concrete Any Cracking Further evaluation is required to Yes, if 5(C-51) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not z areas): from reaction with management program is needed to constructed as c basemat, aggregates manage cracking and expansion due stated

u m concrete fill-in to reaction with aggregate of concrete G)

I annulus in Inaccessible Areas. A plant-specific 0 a 00 aging management program is not G) required if (1) as described in

U 0 CD NUREG-1557, investigations, tests, 0

0  :< and petrographic examinations of

--" I\)

0)

CD 0

I 0

0 0

-....J (J1

z II CONTAINMENT STRUCTURES c

U 83.1 Mark III Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< aggregates performed in accordance I\)

with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

11.83.1.CP-75 11.83.1- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 6(C-43) (inaccessible steel uncontrolled or bond; and loss of Subsection IWL," or areas): Air - outdoor material (spalling, Chapter XI.S6, " Structures basemat; scaling) Monitoring" reinforcing steel due to corrosion of embedded steel 11.83.1.CP-69 11.83.1- Concrete: Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-2(C-36) basemat distortion Subsection IWL," or watering due to increased Chapter XI.S6, " Structures system is stress levels from Monitoring" relied upon to settlement If a de-watering system is relied upon control for control of settlement, then the settlement licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

0 CD C')

11.83.1.CP-65 11.83.1- Concrete: Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if CD 4(C-50) basemat, uncontrolled or strength and program temperature 0

G) 3 0- concrete fill-in Air - outdoor modulus limits are CD annulus due to elevated The implementation of exceeded 0 I\)

0 a temperature 10 CFR 50.55a and ASME Section 0

--" a 0)

CD 0

I 0

0 0

-....J (J)

oCD II CONTAINMENT STRUCTURES C')

CD 83.1 Mark III Steel Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component

(>150°F general; XI, Subsection IWL would not be able

>200°F local) to identify the reduction of strength and modulus of elasticity due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, III CJ.)

such as around penetrations, which I

0"1 are not allowed to exceed 200°F. If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in z

c strength and modulus of elasticity and

u these reductions are applied to the m

G) design calculations.

I 0 00 11.83.1.C-07 11.83.1- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Yes, if a de-

>> a 7(C-07) foundation; porous foundation Monitoring" watering G)

U subfoundation concrete strength and If a de-watering system is relied upon system is 0 CD 0

< cracking for control of erosion of cement from relied upon to 0

--" I\)

0)

CD 0

I 0

0 0

-....J

-....J

z II CONTAINMENT STRUCTURES c

U 83.1 Mark III Steel Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< due to differential porous concrete subfoundations, then control I\)

settlement and the licensee is to ensure proper settlement erosion of porous functioning of the de-watering system concrete through the period of extended subfoundation operation.

11.83.1.CP-43 11.83.1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No 8(C-19) (accessible uncontrolled due to general, Subsection IWE," and areas): drywell pitting, and Chapter XI.S4, "10 CFR Part 50, shell; drywell crevice corrosion AppendixJ" head 11.83.1.CP-113 11.83.1- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 8(C-19) (inaccessible uncontrolled or due to general, Subsection IWE," and corrosion is areas): drywell Concrete pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from III CJ.) shell; drywell crevice corrosion AppendixJ" the IWE I

(J) head; and examinations drywell shell 11.83.1.C-24 11.83.1- Steel elements: Stainless Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No 9(C-24) suppression steel uncontrolled due to stress Subsection IWE," and chamber shell corrosion cracking Chapter XI.S4, "10 CFR Part 50, (interior AppendixJ" surface) 11.83.1.CP-158 11.83.1- Steel elements: Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 8(C-19) suppression uncontrolled or due to general, Subsection IWE" corrosion is chamber shell Treated water pitting, and Plant-specific aging management significant (interior crevice corrosion program is required if plant operating surface) experience identified significant corrosion. If protective coating is 0 credited for preventing corrosion, the CD C') coating should be included in scope CD 0 of license renewal and subject to G) 3 0- aging management review.

CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 0

-....J CD

oCD C')

CD II CONTAINMENT STRUCTURES 3 83.2 Mark III Concrete Containments 0-CD I\)

a Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component 11.83.2.CP-84 11.83.2- Concrete Concrete Air - indoor, Increase in Chapter XI.S2, "ASME Section XI, No 5(C-27) (accessible uncontrolled or porosity and Subsection IWL," or areas): dome; Air - outdoor or permeability; Chapter XI.S6, " Structures wall; base mat Ground cracking; loss of Monitoring" water/soil material (spalling, scaling) due to aggressive chemical attack 11.83.2.CP-52 11.83.2- Concrete Concrete Air - outdoor or Loss of material Chapter XI.S2, "ASME Section XI, No 3(C-29) (accessible Ground (spalling, scaling) Subsection IWL" areas): dome; water/soil and cracking wall; base mat due to freeze-thaw 11.83.2.CP-60 11.83.2- Concrete Concrete Any Cracking Chapter XI.S2, "ASME Section XI, No 4(C-40) (accessible environment due to expansion Subsection IWL" areas): dome; from reaction with wall; base mat aggregates 11.83.2.CP-55 11.83.2- Concrete Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, No 6(C-32) (accessible porosity and Subsection IWL" areas): dome; permeability; loss wall; base mat of strength due to leaching of calcium hydroxide and carbonation z 11.83.2.CP-88 11.83.2- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No c 7(C-42) (accessible steel uncontrolled or bond; and loss of Subsection IWL"

u m areas)

dome; Air - outdoor material (spalling, G)

I wall; base mat; scaling) 0 a 00 reinforcing due to corrosion G) steel of embedded

U steel 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

-....J CD

z II CONTAINMENT STRUCTURES c

U 83.2 Mark III Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< 11.83.2.CP-73 11.83.2- Concrete Concrete Air - indoor, Increase in Chapter XI.S2, "ASME Section XI, No I\)

5(C-27) (inaccessible uncontrolled or porosity and Subsection IWL," or areas): dome; Air - outdoor or permeability; Chapter XI.S6, " Structures wall; base mat Ground cracking; loss of Monitoring" water/soil material (spalling, scaling) due to aggressive chemical attack 11.83.2.CP-135 11.83.2- Concrete Concrete Air - outdoor or Loss of material Further evaluation is required for Yes, for plants 3(C-29) (inaccessible Ground (spalling, scaling) plants that are located in moderate to located in areas): dome; water/soil and cracking severe weathering conditions moderate to wall; base mat due to freeze- (weathering index >100 day-inch/yr) severe thaw (NUREG-1557) to determine if a weathering III plant-specific aging management conditions CJ.)

I 00 program is needed. A plant-specific aging management program is not required if documented evidence confirms that the existing concrete had air entrainment content (as per Table CC-2231-2 of the ASME Section III Division 2), and subsequent inspections of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is 0

CD required to manage loss of material C')

0 CD (spalling, scaling) and cracking due to G) 3 0- freeze-thaw of concrete in CD inaccessible areas .

0 I\)

0 a The weathering index for the 0

--" a 0)

CD 0

I 0

0 0

CD 0

oCD II CONTAINMENT STRUCTURES C')

CD 83.2 Mark III Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component continental US is shown in ASTM C33-90, Fig. 1.

11.83.2.CP-121 11.83.2- Concrete Concrete Any Cracking Further evaluation is required to Yes, if 4(C-40) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not areas): dome; from reaction with management program is needed to constructed as wall; base mat aggregates manage cracking and expansion due stated to reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of III CJ.)

I aggregates performed in accordance CD with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

11.83.2.CP-122 11.83.2- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if z 6(C-32) (inaccessible porosity and determine if a plant-specific aging leaching is c areas): dome; permeability; loss management program is needed to observed in

u m wall; base mat of strength manage increase in porosity, and accessible G)

I due to leaching of permeability due to leaching of areas that 0 a 00 calcium hydroxide calcium hydroxide and carbonation of impact G) and carbonation concrete in Inaccessible Areas. A intended

U 0 CD plant-specific aging management function 0

0  :< program is not required if (1) There is

--" I\)

0)

CD 0

I 0

0 0

CD

z II CONTAINMENT STRUCTURES c

U 83.2 Mark III Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< evidence in the accessible areas that I\)

the flowing water has not caused leaching and carbonation, or (2)

Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

11.83.2.CP-89 11.83.2- Concrete Concrete; Air - indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No 7(C-42) (inaccessible steel uncontrolled or bond; and loss of Subsection IWL," or areas): dome; Air - outdoor material (spalling, Chapter XI.S6, " Structures wall; base mat; scaling) Monitoring" III CJ.) reinforcing due to corrosion I

steel of embedded a

steel 11.83.2.CP-10S 11.83.2- Concrete Concrete Soil Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-1(C-06) elements, all distortion Subsection IWL," or watering due to increased Chapter XI.S6, " Structures system is stress levels from Monitoring" relied upon to settlement If a de-watering system is relied upon control for control of settlement, then the settlement licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

11.83.2.CP-108 11.83.2- Concrete: Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if 0 2(C-33) dome; wall; uncontrolled or strength and program temperature CD C') basemat Air - outdoor modulus The implementation of 10 CFR SO.SSa limits are CD due to elevated and ASME Section XI, Subsection exceeded 0

G) 3 0- temperature IWL would not be able to identify the CD

(>1S0°F general; reduction of strength and modulus of 0 I\)

0 a >200°F local) elasticity due to elevated temperature.

0

--" a 0)

CD 0

I 0

0 0

CD N

oCD II CONTAINMENT STRUCTURES C')

CD 83.2 Mark III Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted. Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200°F. If significant equipment loads are supported by concrete at III CJ.) temperatures exceeding 150°F, an I

evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

11.83.2.C-07 11.83.2- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-z 8(C-07) foundation; porous foundation If a de-watering system is relied upon watering c su bfou ndation concrete strength and for control of erosion of cement from system is

u m cracking porous concrete subfoundations, then relied upon to G) due to differential the licensee is to ensure proper control I

0 00 settlement and functioning of the de-watering system settlement

>> a erosion of porous through the period of extended G)

U concrete operation.

0 CD 0

< subfoundation 0

--" I\)

0)

CD 0

I 0

0 0

CD 0)

z II CONTAINMENT STRUCTURES c

U 83.2 Mark III Concrete Containments m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< 11.83.2.CP-35 11.83.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No I\)

9(C-09) (accessible uncontrolled due to general, Subsection IWE," and areas): liner; pitting, and Chapter XI.S4, "10 CFR Part 50, liner anchors; crevice corrosion AppendixJ" integral attachments 11.83.2.CP-98 11.83.2- Steel elements Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if 9(C-09) (inaccessible uncontrolled due to general, Subsection IWE" and corrosion is areas): liner; pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from liner anchors; crevice corrosion AppendixJ" the IWE integral Additional plant-specific activities are examinations attachments warranted if loss of material due to corrosion is significant for inaccessible III CJ.) areas (embedded containment steel I

shell or liner) .

I\)

Loss of material due to corrosion is not significant if the following conditions are satisfied:

1. Concrete meeting the requirements of ACI 318 or 349 and the guidance of 201.2R was used for the containment concrete in contact with the embedded containment shell or liner.

2. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection 0

CD IWE requirements.

C')

0 CD 3. The concrete is monitored to G) 3 0- ensure that it is free of penetrating CD cracks that provide a path for water 0 I\)

0 a seepage to the surface of the 0

--" a 0)

CD 0

I 0

0 0

CD

.j::>.

oCD II CONTAINMENT STRUCTURES C')

CD B3.2 Mark III Concrete Containments 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component containment shell or liner.

4. Borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner.

Operating experience has identified significant corrosion in some plants.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

II.B3.2.C-24 II.B3.2- Steel Stainless Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No 10(C-24) elements: steel uncontrolled due to stress Subsection IWE," and suppression corrosion cracking Chapter XI.S4, "10 CFR Part 50, chamber shell AppendixJ" (interior surface) z c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

CD (J1

84. COMMON COMPONENTS Systems, Structures, and Components This section addresses the common components of boiling water reactor (BWR) containments.

The common components include penetration sleeves and bellows; dissimilar metal welds; personnel airlock; equipment hatch; CRD hatch; seals, gaskets, and moisture barriers.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation components (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

December 201 0 II 84-1 NUREG-1801, Rev. 2 OAGI0001390_00086

z II CONTAINMENT STRUCTURES c

U B4 Common Components m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< II.B4.CP-40 II.B4-7(C- Moisture Elastomers, Air - indoor, Loss of sealing Chapter XI.S1, "ASME Section XI, No I\)

18) barriers rubber and uncontrolled due to wear, Subsection IWE" (caulking, other similar damage, flashing, and materials erosion, tear, other surface cracks, sealants) or other defects II.B4.CP-36 II.B4-1 (C- Penetration Steel; Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No

12) sleeves dissimilar uncontrolled or due to general, Subsection IWE," and metal welds Air - outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice AppendixJ" corrosion II.B4.CP-38 II.B4-2(C- Penetration Stainless Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, Yes, detection

15) sleeves; steel; uncontrolled or due to stress Subsection IWE," and of aging III

.j:>. penetration dissimilar Air - outdoor corrosion Chapter XI.S4, "10 CFR Part 50, effects is to I

I\) bellows metal welds cracking AppendixJ" be evaluated II.B4.CP-37 II.B4-3(C- penetration Steel; Air - indoor, Cracking Chapter XI.S1, "ASME Section XI, No

14) sleeves; stainless uncontrolled or due to cyclic Subsection IWE," and penetration steel; Air - outdoor loading Chapter XI.S4, "10 CFR Part 50, bellows dissimilar (CLB fatigue AppendixJ" metal welds analysis does not exist)

II.B4.C-13 II.B4-4(C- Penetration Steel; Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA

13) sleeves; stainless uncontrolled or fatigue damage (TLAA) to be evaluated for the period of penetration steel; Air - outdoor due to fatigue extended operation. See the SRP, bellows dissimilar (Only ifCLB Section 4.6, "Containment Liner Plate metal welds fatigue analysis and Penetration Fatigue Analysis" for exists) acceptable methods for meeting the 0 requirements of 10 CFR 54.21 (c) (1 ).

CD C') II.B4.C-16 II.B4-6(C- Personnel Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No CD 0 16) airlock, uncontrolled or due to general, Subsection IWE," and G) 3 0- equipment Air - outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, CD 0 I\) hatch, CRD crevice AppendixJ" 0 a hatch corrosion 0

--" a 0)

CD 0

I 0

0 0

CD

-....J

oCD II CONTAINMENT STRUCTURES C')

CD B4 Common Components 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component II.B4.CP-39 II.B4-5(C- Personnel Steel Air - indoor, Loss of leak Chapter XI.S1, "ASME Section XI, No

17) airlock, uncontrolled or tightness Subsection IWE," and equipment Air - outdoor due to Chapter XI.S4, "10 CFR Part 50, hatch, CRD mechanical wear AppendixJ" hatch: locks, of locks, hinges hinges, and and closure closure mechanisms mechanisms II.B4.CP-150 Pressure- Any Any Loss of preload Chapter XI.S1, "ASME Section XI, No retaining environment due to self- Subsection IWE," and bolting loosening Chapter XI.S4, "10 CFR Part 50, AppendixJ" II.B4.CP-148 Pressure- Steel Air - indoor, Loss of material Chapter XI.S1, "ASME Section XI, No retaining uncontrolled or due to general, Subsection IWE" bolting Air - outdoor pitting, and crevice corrosion II.B4.CP-41 II.B4-7(C- Seals and Elastomers, Air - indoor, Loss of sealing Chapter XI.S4, "10 CFR Part 50, No

18) gaskets rubber and uncontrolled or due to wear, AppendixJ" other similar Air - outdoor damage, materials erosion, tear, surface cracks, or other defects II.B4.CP-152 Service Level Coatings Air - indoor, Loss of coating Chapter XI.S8, "Protective Coating No I coatings uncontrolled integrity Monitoring and Maintenance" z due to blistering, c cracking, flaking,

u m peeling, or G)

I physical damage 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

CD CD

CHAPTER III STRUCTURES AND COMPONENT SUPPORTS December 201 0 III-i NUREG-1801, Rev. 2 OAGI0001390_00089

STRUCTURES AND COMPONENT SUPPORTS Chapter III A: Safety Related and Other Structures Safety-related structures are those defined pursuant to 10 CFR 54.4(a)(1), and the other structures are those defined pursuant to 10 CFR 54.4(a)(2) and 10 CFR 54.4(a)(3).

Structures in this section are organized into nine groups and are discussed separately under subheadings A 1 through A9.

Chapter III B: Component Supports Component supports include supports for ASME piping and components; supports for cable trays, conduit, HVAC ducts, TubeTrack, instrument tubing, non-ASME piping and components; anchorage of racks, panels, cabinets, and enclosures for electrical equipment and instrumentation; supports for emergency diesel generator (EOG) and HVAC system components; and supports for platforms, pipe whip restraints, jet impingement shields, masonry walls, and other miscellaneous structures.

December 201 0 III-iii NUREG-1801, Rev. 2 OAG10001390_00090

III.A SAFETY RELATED AND OTHER STRUCTURES A 1. Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

A2. Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

A3. Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm.,Yard Structures, such as AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures, such as Transmission Towers, Startup Towers Circuit Breaker Foundation, Electrical Enclosure)

A4. Group 4 Structures (Containment Internal Structures, excluding Refueling Canal)

AS. Group S Structures (Fuel Storage Facility, Refueling Canal)

A6. Group 6 Structures (Water-Control Structures)

A7. Group 7 Structures (Concrete Tanks and Missile Barriers)

A8. Group 8 Structures (Steel Tanks and Missile Barriers)

A9. Group 9 Structures (BWR Unit Vent Stack)

December 201 0 III A-i NUREG-1801, Rev. 2 OAGI0001390_00091

A 1. GROUP 1 STRUCTURES (BWR REACTOR BLDG., PWR SHIELD BLDG., CONTROL ROOM/BLDG.)

Systems, Structures, and Components This section addresses the elements of the boiling water reactor (8WR) reactor building, pressurized water reactor (PWR) shield building, and control room/building. For this group, the applicable structural elements are concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems or components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A1-1 NUREG-1801, Rev. 2 OAGI0001390_00092

z III STRUCTURES AND COMPONENT SUPPORTS c

U A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< IILA1.TP- IILA1-2(T- Concrete Concrete Any environment Cracking Chapter XLS6, "Structures Monitoring" No I\)

25 03) (accessible due to expansion areas): all from reaction with aggregates IILA1.TP- liLA 1-4(T- Concrete Concrete Ground Cracking; loss of Chapter XLS6, "Structures Monitoring" No 27 05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel IILA1.TP- liLA 1-6(T- Concrete Concrete Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring" No 23 01 ) (accessible (spalling, scaling) areas): exterior and cracking

...... above- and due to freeze-thaw I

I\) below-grade; foundation IILA1.TP- liLA 1-7(T- Concrete Concrete Water - flowing Increase in Chapter XLS6, "Structures Monitoring" No 24 02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation IILA1.TP- IILA1-9(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XLS6, "Structures Monitoring" No 26 04) (accessible uncontrolled or bond; and loss of areas): interior Air - outdoor material (spalling, and above- scaling) 0 grade exterior due to corrosion of CD C') embedded steel CD 0 IILA1.TP- IILA1-2(T- Concrete Concrete Any environment Cracking Further evaluation is required to Yes, if G) 3 0- 204 03) (inaccessible due to expansion determine if a plant-specific aging concrete is not CD 0 I\) areas): all from reaction with management program is needed to constructed as 0 a aggregates manage cracking and expansion due to stated 0

--" a 0)

CD 0

I 0

0 0

CD 0)

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not

...... significant if it is demonstrated that the I

CJ.) in-place concrete can perform its intended function.

IILA1.TP- liLA 1-4(T- Concrete Concrete Ground Cracking; loss of Chapter XLS6, "Structures Monitoring" No 212 05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel IILA1.TP- IILA1-5(T- Concrete Concrete Ground Increase in Chapter XLS6, "Structures Monitoring" No 29 07) (inaccessible water/soil porosity and areas): below- permeability; z grade exterior; cracking; loss of c foundation material (spalling,

u m scaling)

G) due to aggressive I

0 00 chemical attack

>> a G) IILA1.TP- liLA 1-7(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if 0

U 67 02) (inaccessible porosity and determine if a plant-specific aging leaching is CD 0 areas)

exterior permeability; loss management program is needed to observed in 0  :<

--" I\)

0)

CD 0

I 0

0 0

CD

.j::>.

z III STRUCTURES AND COMPONENT SUPPORTS c

U A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< above- and of strength manage increase in porosity, and accessible I\)

below-grade; due to leaching of permeability due to leaching of calcium areas that foundation calcium hydroxide hydroxide and carbonation of concrete in impact and carbonation Inaccessible Areas. A plant-specific intended aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete

...... structure.

I

.j:>. III.A1.TP- III.A 1-6(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants 108 01) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering index moderate to foundation due to freeze-thaw >100 day-inch/yr) (NUREG-1557) to severe determine if a plant-specific aging weathering management program is needed. A conditions plant-specific aging management program is not required if documented evidence confirms that the existing concrete had air entrainment content (as per Table CC-2231-2 of the ASME Section III Division 2), and subsequent inspections of accessible areas did not exhibit degradation related to freeze-0 CD thaw. Such inspections should be C')

0 CD considered a part of the evaluation. If G) 3 0- this condition is not satisfied, then a CD plant-specific aging management 0 I\)

0 a program is required to manage loss of 0

--" a 0)

CD 0

I 0

0 0

CD (J1

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A1.TP- III.A1-1 (T- Concrete: all Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if 114 10) uncontrolled strength and program temperature modulus limits are due to elevated Subsection CC-3400 of ASME exceeded temperature Section III, Division 2, and Appendix A of

(>150°F general; ACI 349 specifies the concrete

>200°F local) temperature limits for normal operation or any other long-term period. The

...... temperatures shall not exceed 150°F I

0"1 except for local areas, such as around penetrations, where the temperatures are not allowed to exceed 200°F. If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than those given above may be allowed in the concrete if z tests and/or calculations are provided to c evaluate the reduction in strength and

u m modulus of elasticity and these G) reductions are applied to the design I

0 00 calculations.

>> a III.A1.TP- III.A1-3(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-G) 0

U 30 08) distortion If a de-watering system is relied upon for watering CD 0

< due to increased control of settlement, then the licensee system is 0

--" I\)

0)

CD 0

I 0

0 0

CD (J)

z III STRUCTURES AND COMPONENT SUPPORTS c

U A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< stress levels from is to ensure proper functioning of the de- relied upon to I\)

settlement watering system through the period of control extended operation. settlement III.A1.TP- III.A1-8(T- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-31 09) foundation; porous under foundation foundation strength If a de-watering system is relied upon for watering subfoundation concrete and cracking control of settlement, then the licensee system is due to differential is to ensure proper functioning of the de- relied upon to settlement and watering system through the period of control erosion of porous extended operation. settlement concrete subfoundation III.A1.TP- III.A1- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No 28 10(T-06) interior; above- uncontrolled or porosity and

...... grade exterior Air - outdoor permeability; I

(J) cracking; loss of material (spalling, scaling) due to aggressive chemical attack III.A1.TP- High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No 300 structural steel, actual uncontrolled or due to stress bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM yield strength A 490 bolts used in civil structures have

150 ksi not shown to be prone to SCC. SCC (1,034 MPa) potential need not be evaluated for these bolts.

III.A1.T-12 III.A1- Masonry walls: Concrete Air - indoor, Cracking Chapter XI.S5, "Masonry Walls" No 0 11(T-12) all block uncontrolled or due to restraint CD C')

CD Air - outdoor shrinkage, creep, 0 and aggressive

>> 3 0-G) ...,

CD environment 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 0

CD

-....J

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.A1.TP- III.A1- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No 302 12(T-11) components: all uncontrolled or due to corrosion If protective coatings are relied upon to structural steel Air - outdoor manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

III.A1.TP- Structural Any Any environment Loss of preload Chapter XI.S6, "Structures Monitoring" No 261 bolting due to self-loosening III.A1.TP- Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No 248 bolting uncontrolled due to general, pitting and crevice corrosion

...... III.A1.TP- Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No I

-J 274 bolting galvanized due to general, steel pitting, and crevice corrosion z

c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

CD CD

A2. GROUP 2 STRUCTURES (BWR REACTOR BLDG. WITH STEEL SUPERSTRUCTURE)

Systems, Structures, and Components This section addresses the elements of the boiling water reactor (8WR) reactor building with steel superstructure. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A2-1 NUREG-1801, Rev. 2 OAGI0001390_00099

z III STRUCTURES AND COMPONENT SUPPORTS c

U A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.A2.TP-25 III.A2-2(T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No I\)

03) (accessible environment due to expansion areas): all from reaction with aggregates III.A2.TP-27 III.A2-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A2.TP-23 III.A2-6(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No

01) (accessible (spalling, scaling)

I\) areas): exterior and cracking I

I\) above- and due to freeze-below-grade; thaw foundation III.A2.TP-24 III.A2-7(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A2.TP-26 III.A2-9(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

04) (accessible uncontrolled or bond; and loss of areas): interior Air - outdoor material (spalling, 0 and above- scaling)

CD C') grade exterior due to corrosion CD 0 3 of embedded G) 0- steel CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 0

0

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.A2.TP-204 III.A2-2(T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not areas): all from reaction with management program is needed to constructed as aggregates manage cracking and expansion due to stated reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can I\)

demonstrate that those aggregates do I

CJ.) not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III.A2.TP-212 III.A2-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion z of embedded c steel

u m III.A2.TP-29 III.A2-5(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures Monitoring" No G)

I 07) (inaccessible water/soil porosity and 0 00 areas): below- permeability;

>> a grade exterior; cracking; loss of G) 0

U foundation material (spalling, CD 0

< scaling) 0

--" I\)

0)

CD 0

I 0

0 0

z III STRUCTURES AND COMPONENT SUPPORTS c

U A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< due to aggressive I\)

chemical attack III.A2.TP-67 III.A2-7(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

02) (inaccessible porosity and determine if a plant-specific aging leaching is areas): exterior permeability; loss management program is needed to observed in above- and of strength manage increase in porosity, and accessible below-grade; due to leaching of permeability due to leaching of calcium areas that foundation calcium hydroxide hydroxide and carbonation of concrete impact and carbonation in Inaccessible Areas. A plant-specific intended aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water I\) has not caused leaching and I

.j:>.

carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

III.A2 .TP-1 08 III.A2-6(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants

01) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering moderate to foundation due to freeze- index >100 day-inch/yr) (NUREG- severe thaw 1557) to determine if a plant-specific weathering aging management program is needed. conditions A plant-specific aging management 0 program is not required if documented CD C')

CD evidence confirms that the existing 0 3 concrete had air entrainment content G) 0-(as per Table CC-2231-2 of the ASME CD 0 I\) Section III Division 2), and subsequent 0 a 0 inspections of accessible areas did not

--" a 0)

CD 0

I 0

0 0

N

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A2.TP-114 III.A2-1 (T- Concrete: all Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if I\)

10) uncontrolled strength and program temperature I

0"1 modulus limits are due to elevated Subsection CC-3400 of ASME exceeded temperature Section III, Division 2, and Appendix A

(>150°F general; of ACI 349 specifies the concrete

>200°F local) temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, where the temperatures are not allowed to exceed 200°F. If significant equipment loads are z supported by concrete at temperatures c exceeding 150°F, an evaluation of the

u m ability to withstand the postulated G) design loads is to be made.

I 0 a 00 G)

Higher temperatures than those given

U above may be allowed in the concrete 0 CD 0

< if tests and/or calculations are provided 0

--" I\)

0)

CD 0

I 0

0 0

0)

z III STRUCTURES AND COMPONENT SUPPORTS c

U A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< to evaluate the reduction in strength I\)

and modulus of elasticity and these reductions are applied to the design calculations.

111.A2.TP-30 III.A2-3(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-

08) distortion If a de-watering system is relied upon watering due to increased for control of settlement, then the system is stress levels from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation. settlement III.A2.TP-31 III.A2-8(T- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-

09) foundation; porous under foundation If a de-watering system is relied upon watering su bfou ndation concrete foundation strength and for control of settlement, then the system is I\) cracking licensee is to ensure proper functioning relied upon to I

(J) due to differential of the de-watering system through the control settlement and period of extended operation. settlement erosion of porous concrete subfoundation III.A2.TP-28 III.A2- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No 10(T-06) interior; above- uncontrolled or porosity and grade exterior Air - outdoor permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack 0 111.A2. TP-300 H ig h-stre ngth Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No CD C') structural steel, actual uncontrolled or due to stress CD 0 3 bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM G) 0-yield A 490 bolts used in civil structures CD 0 I\) strength ;:: have not shown to be prone to SCC.

0 a 150 ksi SCC potential need not be evaluated 0

--" a 0)

CD 0

I 0

0 0

.j::>.

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component (1,034 MPa) for these bolts.

III.A2.T-12 III.A2- Masonry walls: Concrete Air - indoor, Cracking Chapter XI.SS, "Masonry Walls" No 11(T-12) all block uncontrolled or due to restraint Air - outdoor shrinkage, creep, and aggressive environment 111.A2. TP-302 III.A2- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No 12(T-11) components: uncontrolled or due to corrosion If protective coatings are relied upon to all structural Air - outdoor manage the effects of aging, the steel structures monitoring program is to include provisions to address protective I\) coating monitoring and maintenance.

I

-J III.A2.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No bolting environment due to self-loosening III.A2.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No bolting uncontrolled due to general, pitting and crevice corrosion III.A2.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and z crevice corrosion c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 0

(J1

A3. GROUP 3 STRUCTURES (AUXILIARY BLDG., DIESEL GENERATOR BLDG.,

RADWASTE BLDG., TURBINE BLDG., SWITCHGEAR RM., YARD STRUCTURES, SUCH AS AFW PUMPHOUSE, UTILITY/PIPING TUNNELS, SECURITY/LIGHTING POLES, MANHOLES, DUCT BANKS; SBO STRUCTURES, SUCH AS TRANSMISSION TOWERS, STARTUP TOWERS CIRCUIT BREAKER FOUNDATION, ELECTRICAL ENCLOSURE)

Systems, Structures, and Components This section addresses the elements of the auxiliary building, diesel generator building, radwaste building, turbine building, switchgear room, yard structures, and station blackout (S80) structures. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A3-1 NUREG-1801, Rev. 2 OAG10001390_00106

z III STRUCTURES AND COMPONENT SUPPORTS c

U A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

G) AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, I

Startup Towers Circuit Breaker foundation, Electrical Enclosure) 00 a

u Structure CD Aging Effect/ Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation I\) Component III.A3.TP-25 III.A3-2(T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No

03) (accessible environment due to expansion areas): all from reaction with aggregates III.A3.TP-27 III.A3-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel CJ.) III.A3.TP-23 III.A3-6(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No I

I\) 01 ) (accessible (spalling, scaling) areas): exterior and cracking above- and due to freeze-below-grade; thaw foundation III.A3.TP-24 III.A3-7(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A3.TP-26 III.A3-9(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No 0 04) (accessible uncontrolled or bond; and loss of CD C') areas): interior Air - outdoor material (spalling, CD 0 and above- scaling)

G) 3 0- grade exterior due to corrosion CD 0 I\)

of embedded 0 a steel 0

--" a 0)

CD 0

I 0

0 0

-....J

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-CD Startup Towers Circuit Breaker foundation, Electrical Enclosure)

I\)

a a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component III.A3.TP-204 III.A3-2(T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is areas): all from reaction with management program is needed to not aggregates manage cracking and expansion due constructed to reaction with aggregate of concrete as stated in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance

>>CJ.)

with ASTM C295 and other ASTM I

CJ.) reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III.A3.TP-212 III.A3-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, z grade exterior; scaling) c foundation due to corrosion

u m of embedded G) steel I

0 00 III.A3.TP-29 III.A3-5(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures Monitoring" No

>> a

07) (inaccessible water/soil porosity and G) 0

U areas)

below- permeability; CD 0

< grade exterior; cracking; loss of 0

--" I\)

0)

CD 0

I 0

0 0

CD

z III STRUCTURES AND COMPONENT SUPPORTS c

U A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

G) AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, I

Startup Towers Circuit Breaker foundation, Electrical Enclosure) 00 a

u Structure CD Aging Effect/ Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation I\) Component foundation material (spalling, scaling) due to aggressive chemical attack III.A3.TP-67 III.A3-7(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

02) (inaccessible porosity and determine if a plant-specific aging leaching is areas): exterior permeability; loss management program is needed to observed in above- and of strength manage increase in porosity, and accessible below-grade; due to leaching of permeability due to leaching of calcium areas that foundation calcium hydroxide hydroxide and carbonation of concrete impact and carbonation in Inaccessible Areas. A plant-specific intended CJ.)

aging management program is not function I

.j:>. required if (1) There is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

III.A3 .TP-1 08 III.A3-6(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants 01 ) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering moderate to foundation due to freeze- index >100 day-inch/yr) (NUREG- severe thaw 1557) to determine if a plant-specific weathering 0

CD C')

aging management program is conditions 0 CD needed. A plant-specific aging G) 3 0- management program is not required if CD documented evidence confirms that 0 I\)

0 a the existing concrete had air 0

--" a 0)

CD 0

I 0

0 0

CD

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-CD Startup Towers Circuit Breaker foundation, Electrical Enclosure)

I\)

a a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component entrainment content (as per Table CC-2231-2 of the ASME Section III Division 2), and subsequent inspections of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and

>>CJ.)

cracking due to freeze-thaw of I

0"1 concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A3.TP-114 III.A3-1 (T- Concrete: all Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if

10) uncontrolled strength and program temperature modulus limits are due to elevated Subsection CC-3400 of ASME exceeded temperature Section III, Division 2, and Appendix A

(>150°F general; of ACI 349 specifies the concrete

>200°F local) temperature limits for normal operation z or any other long-term period. The c temperatures shall not exceed 150°F

u m except for local areas, such as around G) penetrations, where the temperatures I

0 00 are not allowed to exceed 200°F. If

>> a significant equipment loads are G)

U supported by concrete at temperatures 0 CD 0

< exceeding 150°F, an evaluation of the 0

--" I\)

0)

CD 0

I 0

0 0

z III STRUCTURES AND COMPONENT SUPPORTS c

U A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

G) AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, I

Startup Towers Circuit Breaker foundation, Electrical Enclosure) 00 a

u Structure CD Aging Effect/ Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation I\) Component ability to withstand the postulated design loads is to be made.

Higher temperatures than those given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

111.A3.TP-30 III.A3-3(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-CJ.)

08) distortion If a de-watering system is relied upon watering I

(J) due to increased for control of settlement, then the system is stress levels from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation. settlement III.A3.TP-31 III.A3-8(T- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-

09) foundation; porous under foundation If a de-watering system is relied upon watering subfoundation concrete foundation strength and for control of settlement, then the system is cracking licensee is to ensure proper functioning relied upon to due to differential of the de-watering system through the control settlement and period of extended operation. settlement erosion of porous concrete su bfou ndation 0 III.A3.TP-28 III.A3- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No CD C')

10(T-06) interior; above- uncontrolled or porosity and CD grade exterior Air - outdoor permeability; 0

G) 3 0- cracking; loss of CD material (spalling, 0 I\)

0 a scaling) 0

--" a 0)

CD 0

I 0

0

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-CD Startup Towers Circuit Breaker foundation, Electrical Enclosure)

I\)

a a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component due to aggressive chemical attack 111.A3. TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No structural steel, actual uncontrolled or due to stress bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM yield A 490 bolts used in civil structures strength ;::: have not shown to be prone to SCC.

150 ksi SCC potential need not be evaluated (1,034 MPa) for these bolts.

III.A3.T-12 III.A3- Masonry walls: Concrete Air - indoor, Cracking Chapter XI.S5, "Masonry Walls" No

>>CJ.) 11(T-12) all block uncontrolled or due to restraint I

-J Air - outdoor shrinkage, creep, and aggressive environment 111.A3. TP-302 III.A3- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No 12(T-11) components: uncontrolled or due to corrosion If protective coatings are relied upon to all structural Air - outdoor manage the effects of aging, the steel structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

III.A3.TP-219 Steel Steel Ground Loss of material Chapter XI.S6, "Structures Monitoring" No z components: water/soil due to corrosion c

u piles m

G)

III.A3.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No I

0 00 bolting environment due to self-

>> a loosening G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 N

z III STRUCTURES AND COMPONENT SUPPORTS c

U A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

G) AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, I

Startup Towers Circuit Breaker foundation, Electrical Enclosure) 00 a

u Structure CD Aging Effect/ Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation I\) Component III.A3.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No bolting uncontrolled due to general, pitting and crevice corrosion III.A3.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and crevice corrosion CJ.)

I 00 0

CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 0)

A4. GROUP 4 STRUCTURES (CONTAINMENT INTERNAL STRUCTURES, EXCLUDING REFUELING CANAL)

Systems, Structures, and Components This section addresses the elements of the containment internal structures, excluding refueling canal. For this group, the applicable structural elements are identified: concrete and steel elements. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A4-1 NUREG-1801, Rev. 2 OAGI0001390_00114

z III STRUCTURES AND COMPONENT SUPPORTS c

U A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.A4.TP-25 III.A4-2(T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No I\)

03) (accessible environment due to areas): all expansion from reaction with aggregates III.A4.TP-26 III.A4-3(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

04) (accessible uncontrolled or bond; and loss areas): Air - outdoor of material interior and (spalling, above-grade scaling) exterior due to corrosion of embedded steel

.j:>. III.A4.TP-204 III.A4-2(T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if I

I\) 03) (inaccessible environment due to determine if a plant-specific aging concrete is not areas): all expansion from management program is needed to constructed as reaction with manage cracking and expansion due to stated aggregates reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do 0 not adversely react within concrete, or CD C') (2) For potentially reactive aggregates, CD 0 aggregate concrete reaction is not

>> 3 0- significant if it is demonstrated that the G) ...,

CD 0 I\)

in-place concrete can perform its 0 a intended function.

0

--" a 0)

CD 0

I 0

0 (J1

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component 111.A4. TP-30S Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if (inaccessible porosity and determine if a plant-specific aging leaching is areas): permeability; management program is needed to observed in exterior loss of strength manage increase in porosity, and accessible above- and due to leaching permeability due to leaching of calcium areas that below-grade; of calcium hydroxide and carbonation of concrete impact foundation hydroxide and in Inaccessible Areas. A plant-specific intended carbonation aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching

.j:>.

of calcium hydroxide and carbonation in I

CJ.) accessible areas has no impact on the intended function of the concrete structure.

III.A4.TP-114 III.A4-1 (T- Concrete: all Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if

10) uncontrolled strength and program temperature modulus limits are due to elevated Subsection CC-3400 of ASME exceeded temperature Section III, Division 2, and Appendix A

(>1S0°F general; of ACI 349 specifies the concrete

>200°F local) temperature limits for normal operation or any other long-term period. The z temperatures shall not exceed 150°F c except for local areas, such as around

u m penetrations, where the temperatures G) are not allowed to exceed 200°F. If I

0 00 significant equipment loads are

>> a supported by concrete at temperatures G)

U exceeding 150°F, an evaluation of the 0 CD 0

< ability to withstand the postulated design 0

--" I\)

0)

CD 0

I 0

0 (J)

z III STRUCTURES AND COMPONENT SUPPORTS c

U A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< loads is to be made.

I\)

Higher temperatures than those given above may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

111.A4. TP-304 Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-distortion If a de-watering system is relied upon watering due to increased for control of settlement, then the system is stress levels licensee is to ensure proper functioning relied upon to

.j:>. from settlement of the de-watering system through the control I

.j:>. period of extended operation. settlement III.A4.TP-28 III.A4-4(T- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No

06) interior; uncontrolled or porosity and above-grade Air - outdoor permeability; exterior cracking; loss of material (spalling, scaling) due to aggressive chemical attack 111.A4. TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No structural steel, actual uncontrolled or due to stress 0 bolting measured Air - outdoor corrosion Note: ASTM A 325, F 1852, and ASTM CD C') yield cracking A 490 bolts used in civil structures have CD 0 3 strength ;::: not shown to be prone to SCC. SCC G) 0- 150 ksi potential need not be evaluated for CD 0 I\)

(1,034 MPa) these bolts .

0 a 0

--" a 0)

CD 0

I 0

0

-....J

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.A4.TP-301 Service Level Coatings Air - indoor, Loss of coating Chapter XI.S8, "Protective Coating No I coatings uncontrolled integrity Monitoring and Maintenance" due to blistering, cracking, flaking, peeling, physical damage 111.A4.TP-35 III.A4-6(T- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S6, "Structures Monitoring" No

13) surfaces: Fluorogold; uncontrolled mechanical radial beam Lubrofluor function seats in BWR due to corrosion, drywell distortion, dirt, overload, wear 111.A4. TP-302 III.A4-5(T- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No

.j:>. 11 ) components: uncontrolled or due to corrosion If protective coatings are relied upon to I

0"1 all structural Air - outdoor manage the effects of aging, the steel structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

III.A4.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No bolting environment due to self-loosening III.A4.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No bolting uncontrolled due to general, pitting and crevice corrosion z III.A4.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No c

u bolting galvanized due to general, m

G) steel pitting, and I

crevice corrosion 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 CD

AS. GROUP S STRUCTURES (FUEL STORAGE FACILITY, REFUELING CANAL)

Systems, Structures, and Components This section addresses the elements of the fuel storage facility and refueling canal. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III AS-1 NUREG-1801, Rev. 2 OAGI0001390_00119

z c III STRUCTURES AND COMPONENT SUPPORTS

U m AS Group 5 Structures (Fuel Storage Facility, Refueling Canal)

G)

I 00 a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

u Mechanism Evaluation Component CD

< III.A5.TP-25 III.A5-2(T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No I\)

03) (accessible environment due to expansion areas): all from reaction with aggregates III.A5.TP-27 III.A5-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A5.TP-23 III.A5-6(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No

01) (accessible (spalling, scaling) 0'1 areas): exterior and cracking I

I\)

above- and due to freeze-below-grade; thaw foundation III.A5.TP-24 III.A5-7(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A5.TP-26 III.A5-9(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

04) (accessible uncontrolled or bond; and loss of areas): interior Air - outdoor material (spalling, 0

CD and above- scaling)

C')

CD grade exterior due to corrosion 0 of embedded

>> 3 0-G) ...,

CD steel 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 N

0

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.A5.TP-204 III.A5-2(T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not areas): all from reaction with management program is needed to constructed as aggregates manage cracking and expansion due to stated reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can

>>0"1 demonstrate that those aggregates do I

CJ.) not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III.A5.TP-212 III.A5-4(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion z of embedded c steel

u m III.A5.TP-29 III.A5-5(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures Monitoring" No G)

I 07) (inaccessible water/soil porosity and 0 00 areas): below- permeability;

>> a grade exterior; cracking; loss of G) 0

U foundation material (spalling, CD 0

< scaling) 0

--" I\)

0)

CD 0

I 0

0 N

z III STRUCTURES AND COMPONENT SUPPORTS c

U AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< due to aggressive I\)

chemical attack III.A5.TP-67 III.A5-7(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

02) (inaccessible porosity and determine if a plant-specific aging leaching is areas): exterior permeability; loss management program is needed to observed in above- and of strength manage increase in porosity, and accessible below-grade; due to leaching of permeability due to leaching of calcium areas that foundation calcium hydroxide hydroxide and carbonation of concrete impact and carbonation in Inaccessible Areas. A plant-specific intended aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water 0"1 has not caused leaching and I

.j:>.

carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

III.A5 .TP-1 08 III.A5-6(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants 01 ) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering moderate to foundation due to freeze- index >100 day-inch/yr) (NUREG- severe thaw 1557) to determine if a plant-specific weathering aging management program is needed. conditions A plant-specific aging management 0 program is not required if documented CD C') evidence confirms that the existing CD 0 concrete had air entrainment content G) 3 0- (as per Table CC-2231-2 of the ASME CD 0 I\) Section III Division 2), and subsequent 0 a inspections of accessible areas did not 0

--" a 0)

CD 0

I 0

0 N

N

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD AS Group S Structures (Fuel Storage Facility, Refueling Canal) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.AS.TP-114 III.AS-1 (T- Concrete: all Concrete Air - indoor, Reduction of Plant-specific aging management Yes, if

>>0"1

10) uncontrolled strength and program temperature I

0"1 modulus limits are due to elevated Subsection CC-3400 of ASME exceeded temperature Section III, Division 2, and Appendix A

(>1S0°F general; of ACI 349 specifies the concrete

>200°F local) temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 1S0°F except for local areas, such as around penetrations, where the temperatures are not allowed to exceed 200°F. If significant equipment loads are z supported by concrete at temperatures c exceeding 1S0°F, an evaluation of the

u m ability to withstand the postulated G) design loads is to be made.

I 0 a 00 G)

Higher temperatures than those given

U above may be allowed in the concrete 0 CD 0

< if tests and/or calculations are provided 0

--" I\)

0)

CD 0

I 0

0 N

0)

z III STRUCTURES AND COMPONENT SUPPORTS c

U AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< to evaluate the reduction in strength I\)

and modulus of elasticity and these reductions are applied to the design calculations.

111.A5.TP-30 III.A5-3(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-

08) distortion If a de-watering system is relied upon watering due to increased for control of settlement, then the system is stress levels from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control Iperiod of extended operation. settlement III.A5.TP-31 III.A5-8(T- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-

09) foundation; porous under foundation If a de-watering system is relied upon watering subfoundation concrete foundation strength and for control of settlement, then the system is 0"1 cracking licensee is to ensure proper functioning relied upon to I

(J) due to differential of the de-watering system through the control settlement and period of extended operation. settlement erosion of porous concrete subfoundation III.A5.TP-28 III.A5- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No 10(T-06) interior; above- uncontrolled or porosity and grade exterior Air - outdoor permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack 0 111.A5. TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No CD C') structural steel, actual uncontrolled or due to stress CD 0 bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM G) 3 0- yield A 490 bolts used in civil structures CD strength ;:::

0 I\)

have not shown to be prone to SCC .

0 a 150 ksi SCC potential need not be evaluated 0

--" a 0)

CD 0

I 0

0 N

.j::>.

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD AS Group S Structures (Fuel Storage Facility, Refueling Canal) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component (1,034 MPa) for these bolts.

III.AS.T-12 III.AS- Masonry walls: Concrete Air - indoor, Cracking Chapter XI.SS, "Masonry Walls" No 11(T-12) all block uncontrolled or due to restraint Air - outdoor shrinkage, creep, and aggressive environment 111.AS.TP-34 Masonry walls: Concrete Air - outdoor Loss of material Chapter XI.SS, "Masonry Walls" No all block (spalling, scaling) and cracking due to freeze-thaw

>>0"1 III.AS. TP-302 III.AS- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No I

-J 12(T-11) components: uncontrolled or due to corrosion If protective coatings are relied upon to all structural Air - outdoor manage the effects of aging, the steel structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

III.AS.T-14 III.AS- Steel Stainless Treated water Cracking Chapter XI.M2, "Water Chemistry," and No, unless 13(T-14) components: steel or Treated due to stress monitoring of the spent fuel pool water leakages have fuel pool liner borated water corrosion level in accordance with technical been detected cracking; specifications and leakage from the through the Loss of material leak chase channels. SFP liner that due to pitting and cannot be z crevice corrosion accounted for c

u from the leak m

G) chase I

channels 0 a 00 G)

III.AS.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No

U bolting environment due to self-0 CD loosening 0

0  :<

--" I\)

0)

CD 0

I 0

0 N

(J1

z III STRUCTURES AND COMPONENT SUPPORTS c

U AS Group S Structures (Fuel Storage Facility, Refueling Canal) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.AS.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No I\)

bolting uncontrolled due to general, pitting and crevice corrosion III.AS.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and crevice corrosion 0'1 I

00 0

CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 N

(J)

AG. GROUP G STRUCTURES (WATER-CONTROL STRUCTURES)

Systems, Structures, and Components This section addresses the elements of water-control structures. For this group, the applicable structural elements are identified: concrete, steel, masonry walls, and earthen water-control structures. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 2010 III A6-1 NUREG-1801, Rev. 2 OAGI0001390_00127

z III STRUCTURES AND COMPONENT SUPPORTS c

U A6 Group 6 Structures (Water-Control Structures) m G)

I 00 a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

u CD

< 111.A6.TP-38 III.A6-1 (T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S7, "Regulatory Guide No I\)

18) (accessible uncontrolled or bond; and loss of 1.127, Inspection of Water-Control areas): all Air - outdoor material (spalling, Structures Associated with Nuclear or Ground scaling) Power Plants" or the FERC/US Army water/soil due to corrosion Corp of Engineers dam inspections of embedded and maintenance programs.

steel 111.A6.TP-36 III.A6-5(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S7, "Regulatory Guide No

15) (accessible (spalling, scaling) 1.127, Inspection of Water-Control areas): exterior and cracking Structures Associated with Nuclear above- and due to freeze- Power Plants" or the FERC/US Army below-grade; thaw Corp of Engineers dam inspections foundation and maintenance programs.

(J) III.A6.TP-37 III.A6-6(T- Concrete Concrete Water- Increase in Chapter XI.S7, "Regulatory Guide No I

I\) 16) (accessible flowing porosity and 1.127, Inspection of Water-Control areas): exterior permeability; loss Structures Associated with Nuclear above- and of strength Power Plants" or the FERC/US Army below-grade; due to leaching of Corp of Engineers dam inspections foundation; calcium hydroxide and maintenance programs.

interior slab and carbonation III.A6 .TP-1 04 III.A6-1 (T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures No

18) (inaccessible uncontrolled or bond; and loss of Monitoring" areas): all Air - outdoor material (spalling, or Ground scaling) water/soil due to corrosion of embedded steel 0 III.A6.TP-220 III.A6-2(T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if CD C') 17) (inaccessible environment due to expansion determine if a plant-specific aging concrete is CD 0 areas): all from reaction with management program is needed to not G) 3 0- aggregates manage cracking and expansion due constructed CD 0 I\)

to reaction with aggregate of concrete as stated 0 a in Inaccessible Areas. A plant-specific 0

--" a 0)

CD 0

I 0

0 N

CD

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A6 Group 6 Structures (Water-Control Structures) 3 0-CD I\)

a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP) a Component Mechanism Evaluation aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place

>>(J) concrete can perform its intended I

CJ.) function.

III.A6.TP-107 III.A6-3(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures No

19) (inaccessible water/soil porosity and Monitoring" areas): all permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack III.A6.TP-110 III.A6-5(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for Yes, for plants

15) (inaccessible (spalling, scaling) plants that are located in moderate to located in z areas): exterior and cracking severe weathering conditions moderate to c above- and due to freeze- (weathering index >100 day-inch/yr) severe

u m below-grade; thaw (NUREG-1557) to determine if a weathering G)

I foundation; plant-specific aging management conditions 0 00 interior slab program is needed. A plant-specific

>> a aging management program is not G) 0

U required if documented evidence CD 0

< confirms that the existing concrete 0

--" I\)

0)

CD 0

I 0

0 N

CD

z III STRUCTURES AND COMPONENT SUPPORTS c

U A6 Group 6 Structures (Water-Control Structures) m G)

I 00 a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

u CD

< had air entrainment content (as per I\)

Table CC-2231-2 of the ASME Section III Division 2), and subsequent inspections of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in (J) inaccessible areas.

I

.j:>. The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A6 .TP-1 09 III.A6-6(T- Concrete Concrete Water- Increase in Further evaluation is required to Yes, if

16) (inaccessible flowing porosity and determine if a plant-specific aging leaching is areas): exterior permeability; loss management program is needed to observed in above- and of strength manage increase in porosity, and accessible below-grade; due to leaching of permeability due to leaching of areas that foundation; calcium hydroxide calcium hydroxide and carbonation of impact interior slab and carbonation concrete in Inaccessible Areas. A intended plant-specific aging management function program is not required if (1) There is evidence in the accessible areas that the flowing water has not caused 0

CD leaching and carbonation, or (2)

C')

0 CD Evaluation determined that the G) 3 0- observed leaching of calcium CD hydroxide and carbonation in 0 I\)

0 a accessible areas has no impact on 0

--" a 0)

CD 0

I 0

0 0) 0

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD A6 Group 6 Structures (Water-Control Structures) 3 0-CD I\)

a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP) a Component Mechanism Evaluation the intended function of the concrete structure.

111.A6.TP-30 III.A6-4(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Yes, if a de-

08) distortion Monitoring" watering due to increased If a de-watering system is relied upon system is stress levels from for control of settlement, then the relied upon to settlement licensee is to ensure proper control functioning of the de-watering system settlement through the period of extended operation.

III.A6.T-20 III.A6-7(T- Concrete: Concrete Water- Loss of material Chapter XI.S7, "Regulatory Guide No

20) exterior above- flowing due to abrasion; 1.127, Inspection of Water-Control

>>(J) and below-grade; cavitation Structures Associated with Nuclear I

0"1 foundation; Power Plants" or the FERC/US Army interior slab Corp of Engineers dam inspections and maintenance programs.

III.A6.TP-31 III.A6-8(T- Concrete: Concrete; Water- Reduction of Chapter XI.S6, "Structures Yes, if a de-

09) foundation; porous flowing under foundation Monitoring" watering subfoundation concrete foundation strength and If a de-watering system is relied upon system is cracking for control of settlement, then the relied upon to due to differential licensee is to ensure proper control settlement and functioning of the de-watering system settlement erosion of porous through the period of extended concrete operation.

z su bfou ndation c

u III.A6.T-22 III.A6-9(T- Earthen water- Various Water- Loss of material; Chapter XI.S7, "Regulatory Guide No m

G) 22) control flowing or loss of form 1.127, Inspection of Water-Control I

structures: dams; standing due to erosion, Structures Associated with Nuclear 0 a 00 embankments; settlement, Power Plants" or the FERC/US Army G)

U reservoirs; sedimentation, Corp of Engineers dam inspections 0 CD channels; canals frost action, and maintenance programs.

0  :<

0 I\)

and ponds waves, currents, 0)

CD 0

I 0

0 0)

z III STRUCTURES AND COMPONENT SUPPORTS c

U A6 Group 6 Structures (Water-Control Structures) m G)

I 00 a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

u CD

< surface runoff, I\)

seepage III.A6.TP-223 Group 6: Wood Air - outdoor Loss of material; Chapter XI.S7, "Regulatory Guide No Wooden Piles; or Water- change in material 1.127, Inspection of Water-Control sheeting flowing or properties Structures Associated with Nuclear standing or due to Power Plants" or the FERC/US Army Ground weathering, Corp of Engineers dam inspections water/soil chemical and maintenance programs.

degradation, and insect infestation repeated wetting and drying, fungal (J) decay I

(J)

III.A6.T-12 III.A6- Masonry walls: Concrete Air - indoor, Cracking Chapter XI.SS, "Masonry Walls" No 10(T-12) all block uncontrolled or due to restraint Air - outdoor shrinkage, creep, and aggressive environment III.A6.TP-7 III.A6- Seals; gasket; Elastomers Various Loss of sealing Chapter XI.S6, "Structures No 12(TP-7) moisture barriers (such as due to Monitoring" (caulking, EPDM deterioration of flashing, and rubber) seals, gaskets, other sealants) and moisture barriers (caulking, flashing, and other sealants) 0 III.A6.TP-261 Structural bolting Any Any Loss of preload Chapter XI.S6, "Structures No CD C')

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a Structure and/or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP) a Component Mechanism Evaluation III.A6.TP-248 Structural bolting Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No uncontrolled due to general, Monitoring" pitting and crevice corrosion III.A6.TP-221 Structural bolting Steel Air - indoor, Loss of material Chapter XI.S7, "Regulatory Guide No uncontrolled or due to general, 1.127, Inspection of Water-Control Air - outdoor pitting, and Structures Associated with Nuclear or Water- crevice corrosion Power Plants" or the FERC/US Army flowing or Corp of Engineers dam inspections standing and maintenance programs.

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A7. GROUP 7 STRUCTURES (CONCRETE TANKS AND MISSILE BARRIERS)

Systems, Structures, and Components This section addresses the elements of concrete tanks and missile barriers. For this group, the applicable structural elements are identified: concrete and steel. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A7-1 NUREG-1801, Rev. 2 OAGI0001390_00134

z c

U III STRUCTURES AND COMPONENT SUPPORTS m

G) A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

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Structure Aging Effect! Further

u Item Link and/or Material Environment Aging Management Program (AMP)

CD Mechanism Evaluation

< Component I\)

III.A7.TP-25 III.A7-1 (T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No

03) (accessible environment due to expansion areas): all from reaction with aggregates III.A7.TP-27 III.A7-3(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A7.TP-23 III.A7-5(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No

-J 01) (accessible (spalling, scaling)

I I\) areas): exterior and cracking above- and due to freeze-below-grade; thaw foundation III.A7.TP-24 III.A7-6(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A7.TP-26 III.A7-8(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

04) (accessible uncontrolled or bond; and loss of 0 areas): interior Air - outdoor material (spalling, CD C') and above- scaling)

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Mechanism Evaluation a Component liLA 7 .TP-204 IILA7-1 (T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not areas): all from reaction with management program is needed to constructed as aggregates manage cracking and expansion due to stated reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can

-J demonstrate that those aggregates do I

CJ.) not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

liLA 7 .TP-212 IILA7-3(T- Concrete Concrete Ground Cracking; loss of Chapter XLS6, "Structures Monitoring" No

05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion z of embedded c steel

u m IILA7.TP-29 IILA7-4(T- Concrete Concrete Ground Increase in Chapter XLS6, "Structures Monitoring" No G)

I 07) (inaccessible water/soil porosity and 0 00 areas): below- permeability;

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Mechanism Evaluation

u Component CD

< due to aggressive I\)

chemical attack III.A7.TP-67 III.A7-6(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

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III.A7.TP-108 III.A7-5(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants

01) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering moderate to foundation due to freeze- index >100 day-inch/yr) (NUREG- severe thaw 1557) to determine if a plant-specific weathering aging management program is needed. conditions A plant-specific aging management 0 program is not required if documented CD C') evidence confirms that the existing CD 0 concrete had air entrainment content G) 3 0- (as per Table CC-2231-2 of the ASME CD 0 I\) Section III Division 2), and subsequent 0 a inspections of accessible areas did not 0

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Mechanism Evaluation a Component exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A7.TP-30 III.A7-2(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-

-J

08) distortion If a de-watering system is relied upon watering I

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09) foundation; porous under foundation If a de-watering system is relied upon watering subfoundation concrete foundation strength and for control of settlement, then the system is cracking licensee is to ensure proper functioning relied upon to due to differential of the de-watering system through the control settlement and period of extended operation. settlement erosion of porous z concrete c subfoundation

u m III.A7.TP-28 III.A7-9(T- Concrete

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Mechanism Evaluation

u Component CD

< due to aggressive I\)

chemical attack liLA 7 .TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XLS6, "Structures Monitoring" No structural steel, actual uncontrolled or due to stress bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM yield A 490 bolts used in civil structures strength ;::: have not shown to be prone to SCC.

150 ksi SCC potential need not be evaluated (1,034 MPa) for these bolts.

liLA 7 .TP-302 IILA7- Steel Steel Air - indoor, Loss of material Chapter XLS6, "Structures Monitoring" No 10(T-11) components: uncontrolled or due to corrosion If protective coatings are relied upon to all structural Air - outdoor manage the effects of aging, the

-J steel structures monitoring program is to I

(J) include provisions to address protective coating monitoring and maintenance.

IILA7.T-23 IILA7- Steel Stainless Water- Cracking A plant-specific aging management Yes, plant-11 (T-23) components: steel standing due to stress program is to be evaluated. specific tank liner corrosion cracking; Loss of material due to pitting and crevice corrosion IILA7.TP-261 Structural Any Any Loss of preload Chapter XLS6, "Structures Monitoring" No bolting environment due to self-loosening liLA 7 .TP-248 Structural Steel Air - indoor, Loss of material Chapter XLS6, "Structures Monitoring" No 0

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Mechanism Evaluation a Component III.A7 .TP-27 4 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and crevice corrosion

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A8. GROUP 8 STRUCTURES (STEEL TANKS AND MISSILE BARRIERS)

Systems, Structures, and Components This section addresses the elements of steel tanks and missile barriers. For this group, the applicable structural elements are identified: concrete and steel. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A8-1 NUREG-1801, Rev. 2 OAGI0001390_00141

z c

U III STRUCTURES AND COMPONENT SUPPORTS m

G) A8 Group 8 Structures (Steel Tanks and Missile Barriers)

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Structure Aging Effect! Further

u Item Link and/or Material Environment Aging Management Program (AMP)

CD Mechanism Evaluation

< Component I\)

III.A8.TP-25 III.A8-1 (T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No

03) (accessible environment due to expansion areas): all from reaction with aggregates III.A8.TP-27 III.A8-3(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A8.TP-23 III.A8-5(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No 00 01) (accessible (spalling, scaling)

I I\) areas): exterior and cracking above- and due to freeze-below-grade; thaw foundation III.A8.TP-24 III.A8-6(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A8.TP-204 III.A8-1 (T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not 0 areas): all from reaction with management program is needed to constructed as CD C') aggregates manage cracking and expansion due to stated CD 0 reaction with aggregate of concrete in G) 3 0- Inaccessible Areas. A plant-specific CD 0 I\) aging management program is not 0 a required if (1) as described in NUREG-0

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Mechanism Evaluation a Component 1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can demonstrate that those aggregates do not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III.A8.TP-212 III.A8-3(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

>>00

05) (inaccessible water/soil bond; and loss of I

CJ.) areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A8.TP-29 III.A8-4(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures Monitoring" No

07) (inaccessible water/soil porosity and areas): below- permeability; grade exterior; cracking; loss of foundation material (spalling, scaling) z due to aggressive c chemical attack

u m III.A8.TP-67 III.A8-6(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if G)

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Mechanism Evaluation

u Component CD

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aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

III.A8 .TP-1 08 III.A8-5(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants

01) (inaccessible (spalling, scaling) that are located in moderate to severe located in 00 areas): and cracking weathering conditions (weathering moderate to I

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0 CD program is required to manage loss of G) 3 0- material (spalling, scaling) and cracking CD due to freeze-thaw of concrete in 0 I\)

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Mechanism Evaluation a Component The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

111.AS.TP-30 III.AS-2(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-OS) distortion If a de-watering system is relied upon watering due to increased for control of settlement, then the system is stress levels from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation. settlement III.AS.TP-31 III.AS-7(T- Concrete: Concrete; Water - flowing Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-

09) foundation; porous under foundation If a de-watering system is relied upon watering su bfou ndation concrete foundation strength and for control of settlement, then the system is cracking licensee is to ensure proper functioning relied upon to

>>00 due to differential of the de-watering system through the control I

0"1 settlement and period of extended operation. settlement erosion of porous concrete subfoundation III.AS. TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No structural steel, actual uncontrolled or due to stress bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1S52, and ASTM yield A 490 bolts used in civil structures strength ;::: have not shown to be prone to SCC.

150 ksi SCC potential need not be evaluated (1,034 MPa) for these bolts.

z III.AS. TP-302 III.AS-S(T- Steel Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No c

u 11 ) components

uncontrolled or due to corrosion If protective coatings are relied upon to m

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I 00 Structure a Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

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III.A8.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and crevice corrosion 0

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A9. GROUP 9 STRUCTURES (8WR UNIT VENT STACK)

Systems, Structures, and Components This section addresses the elements of the boiling water reactor (8WR) unit vent stack. For this group, the applicable structural element is identified: concrete. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

December 201 0 III A9-1 NUREG-1801, Rev. 2 OAGI0001390_00147

z III STRUCTURES AND COMPONENT SUPPORTS c A9 Group 9 Structures (BWR Unit Vent Stack)

U m

G)

I Structure 00 Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component

u CD III.A9.TP-25 III.A9-1 (T- Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No I\) 03) (accessible environment due to expansion areas)

all from reaction with aggregates III.A9.TP-27 III.A9-3(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (accessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A9.TP-23 III.A9-5(T- Concrete Concrete Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No

01) (accessible (spalling, scaling)

CD areas): exterior and cracking I

I\)

above- and due to freeze-below-grade; thaw foundation III.A9.TP-24 III.A9-6(T- Concrete Concrete Water - flowing Increase in Chapter XI.S6, "Structures Monitoring" No

02) (accessible porosity and areas): exterior permeability; loss above- and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A9.TP-26 III.A9-8(T- Concrete Concrete Air - indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

04) (accessible uncontrolled or bond; and loss of areas): interior Air - outdoor material (spalling, and above- scaling) 0 CD grade exterior due to corrosion C')

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Mechanism Evaluation a Component III.A9.TP-204 III.A9-1 (T- Concrete Concrete Any Cracking Further evaluation is required to Yes, if

03) (inaccessible environment due to expansion determine if a plant-specific aging concrete is not areas): all from reaction with management program is needed to constructed as aggregates manage cracking and expansion due to stated reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not required if (1) as described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295 and other ASTM reactivity tests, as required, can

>>CD demonstrate that those aggregates do I

CJ.)

not adversely react within concrete, or (2) For potentially reactive aggregates, aggregate concrete reaction is not significant if it is demonstrated that the in-place concrete can perform its intended function.

III.A9.TP-212 III.A9-3(T- Concrete Concrete Ground Cracking; loss of Chapter XI.S6, "Structures Monitoring" No

05) (inaccessible water/soil bond; and loss of areas): below- material (spalling, grade exterior; scaling) foundation due to corrosion z of embedded c steel

u m III.A9.TP-29 III.A9-4(T- Concrete Concrete Ground Increase in Chapter XI.S6, "Structures Monitoring" No G) 07) (inaccessible water/soil porosity and I

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z III STRUCTURES AND COMPONENT SUPPORTS c A9 Group 9 Structures (BWR Unit Vent Stack)

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Mechanism Evaluation Component

u CD due to aggressive I\) chemical attack III.A9.TP-67 III.A9-6(T- Concrete Concrete Water - flowing Increase in Further evaluation is required to Yes, if

02) (inaccessible porosity and determine if a plant-specific aging leaching is areas): exterior permeability; loss management program is needed to observed in above- and of strength manage increase in porosity, and accessible below-grade; due to leaching of permeability due to leaching of calcium areas that foundation calcium hydroxide hydroxide and carbonation of concrete impact and carbonation in Inaccessible Areas. A plant-specific intended aging management program is not function required if (1) There is evidence in the accessible areas that the flowing water CD has not caused leaching and I

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III.A9.TP-108 III.A9-5(T- Concrete Concrete Air - outdoor Loss of material Further evaluation is required for plants Yes, for plants

01) (inaccessible (spalling, scaling) that are located in moderate to severe located in areas): and cracking weathering conditions (weathering moderate to foundation due to freeze- index >100 day-inch/yr) (NUREG- severe thaw 1557) to determine if a plant-specific weathering aging management program is needed. conditions A plant-specific aging management program is not required if documented 0

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evidence confirms that the existing 0 CD concrete had air entrainment content G) 3 0- (as per Table CC-2231-2 of the ASME 0

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CD A9 Group 9 Structures (BWR Unit Vent Stack) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. If this condition is not satisfied, then a plant-specific aging management program is required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

The weathering index for the continental US is shown in ASTM C33-90, Fig. 1.

III.A9.TP-30 III.A9-2(T- Concrete: all Concrete Soil Cracking and Chapter XI.S6, "Structures Monitoring" Yes, if a de-

>>CD

08) distortion If a de-watering system is relied upon watering I

0"1 due to increased for control of settlement, then the system is stress levels from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation. settlement III.A9.TP-31 III.A9-7(T- Concrete: Concrete; Water - flowing Reduction in Chapter XI.S6, "Structures Monitoring" Yes, if a de-

09) foundation; porous under foundation If a de-watering system is relied upon watering su bfou ndation concrete foundation strength, cracking for control of settlement, then the system is due to differential licensee is to ensure proper functioning relied upon to settlement, of the de-watering system through the control erosion of porous period of extended operation. settlement concrete z subfoundation c III.A9.TP-28 III.A9-9(T- Concrete: Concrete Air - indoor, Increase in Chapter XI.S6, "Structures Monitoring" No

u m 06) interior; above- uncontrolled or porosity and G)

I grade exterior Air - outdoor permeability; 0 00 cracking; loss of G) a material (spalling, 0

U scaling) 0 CD 0

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z III STRUCTURES AND COMPONENT SUPPORTS c A9 Group 9 Structures (BWR Unit Vent Stack)

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I Structure 00 Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component

u CD chemical attack I\)

III.A9.TP-300 H ig h-stre ngth Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures Monitoring" No structural steel, actual uncontrolled or due to stress bolting measured Air - outdoor corrosion cracking Note: ASTM A 325, F 1852, and ASTM yield A 490 bolts used in civil structures strength ;:: have not shown to be prone to SCC.

150 ksi SCC potential need not be evaluated (1,034 MPa) for these bolts.

III.A9.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No bolting environment due to self-loosening CD III.A9.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures Monitoring" No I

(J) bolting uncontrolled due to general, pitting and crevice corrosion III.A9.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No bolting galvanized due to general, steel pitting, and crevice corrosion 0

CD C')

0 CD G) 3 0-0 CD 0 I\)

0 a

0) a CD 0

I 0

0 (J1 N

111.8 COMPONENT SUPPORTS

81. Supports for ASME Piping and Components

82. Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components

83. Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation

84. Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment

85. Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures December 201 0 1118-i NUREG-1801, Rev. 2 OAGI0001390_00153

81. SUPPORTS FOR ASME PIPING AND COMPONENTS B1.1 Class 1 B1.2 Class 2 and 3 B1.3 Class MC (BWR Containment Supports)

December 201 0 III B1-i NUREG-1801, Rev. 2 OAGI0001390_00154

81.SUPPORTS FOR ASME PIPING AND COMPONENTS Systems, Structures, and Components This section addresses supports and anchorage for ASME piping systems and components. It is subdivided into Class 1 (lII.B1.1), Class 2 and 3 (lII.B1.2), and Class MC (lII.B1.3). Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events so that the supported element can perform its intended function.

December 201 0 III 81-1 NUREG-1801, Rev. 2 OAGI0001390_00155

z III STRUCTURES AND COMPONENT SUPPORTS c

U B1.1 Class 1 m

G)

I 00 Structure a Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B1.1.TP-42 III.B1.1- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

1(T-29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; degradation!

grout pads for service-induced support base cracking or other plates concrete aging mechanisms III.B1.1.T-28 III.B1.1- Constant and Steel Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 2(T-28) variable load uncontrolled or mechanical Subsection IWF" spring Air - outdoor function hangers; due to corrosion, I

I\) guides; stops distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads III.B1.1.TP-41 III.B1.1- High-strength Low-alloy Air - indoor, Cracking Chapter XI.S3, "ASME Section XI, No 3(T-27) structural steel, actual uncontrolled due to stress Subsection IWF" bolting measured corrosion yield strength cracking

150 ksi (1,034 MPa)

III.B1.1.TP-45 III.B1.1- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 5(T-32) surfaces graphitic tool uncontrolled or mechanical Subsection IWF" 0 steel; Air - outdoor function CD C') Fluorogold; due to corrosion, CD Lubrofluor distortion, dirt, 0

G) 3 0- debris, overload, CD wear 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 (J1 (J)

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B1.1 Class 1 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B1.1.TP-229 Structural Any Any Loss of preload Chapter XI.S3, "ASME Section XI, No bolting environment due to self- Subsection IWF" loosening III.B1.1.TP-232 Structural Stainless steel Treated water Loss of material Chapter XI.M2, "Water Chemistry," No bolting due to pitting and and crevice Chapter XI.S3, "ASME Section XI, corrosion Subsection IWF" III.B1.1.TP-226 Structural Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No Bolting uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion III.B1.1.TP-235 Structural Steel; Air - outdoor Loss of material Chapter XI.S3, "ASME Section XI, No bolting galvanized due to pitting Subsection IWF" I steel and crevice CJ.)

corrosion III.B1.1.TP-8 III.B1.1- Support Aluminum; Air - indoor, None None No 6(TP-8) members; galvanized uncontrolled III.B1.1- welds; bolted steel; stainless 7(TP-11) connections; steel III.B1.1- support 9(TP-5) anchorage to building structure III.B1.1.TP-3 III.B1.1- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 8(TP-3) members; steel; water leakage due to boric acid Corrosion" z welds; bolted aluminum corrosion c

u connections; m

G) support I

anchorage to 0 a 00 G) building

U structure 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 (J1

-....J

z III STRUCTURES AND COMPONENT SUPPORTS c

U B1.1 Class 1 m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B1.1.TP-4 III.B1.1- Support Stainless steel Air with borated None None No I\)

10(TP-4) members; water leakage welds; bolted connections; support anchorage to building structure III.B1.1.T-26 III.B1.1- Support Steel Air - indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA 12(T-26) members; uncontrolled fatigue damage analysis (TLAA) to be evaluated for welds; bolted due to fatigue the period of extended operation. See connections; (Only ifCLB the SRP, Section 4.3 "Metal Fatigue,"

support fatigue analysis for acceptable methods for meeting anchorage to exists) the requirements of 10 CFR I

.j:>. building 54.21 (c)(1).

structure III.B1.1.T-24 III.B1.1- Support Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No 13(T-24) members; uncontrolled or due to general Subsection IWF" welds; bolted Air - outdoor and pitting connections; corrosion support anchorage to building structure III.B1.1.T-25 III.B1.1- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 14(T-25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion 0 connections; CD C') support CD anchorage to 0

G) 3 0- building CD structure 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 (J1 CD

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B1.1 Class 1 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B1.1.TP-10 III.B1.1- Support Steel; Treated water Loss of material Chapter XI.M2, "Water Chemistry," for No 11 (TP-1 0) members; stainless steel <60C <<140 F) due to general BWR water, and welds; bolted (steel only), Chapter XI.S3, "ASME Section XI, connections; pitting, and Subsection IWF" support crevice corrosion anchorage to building structure III.B1.1.T-33 III.B1.1- Vibration Non-metallic Air - indoor, Reduction or Chapter XI.S3, "ASME Section XI, No 1S(T-33) isolation (e.g., rubber) uncontrolled or loss of isolation Subsection IWF" elements Air - outdoor function due to radiation hardening, temperature, I

0"1 humidity, sustained vibratory loading z

c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 (J1 CD

z c

U III STRUCTURES AND COMPONENT SUPPORTS m

G) B1.2 Class 2 and 3 I

00 a Structure Aging Effect! Further

u Item Link and!or Material Environment Aging Management Program (AMP)

CD Mechanism Evaluation

< Component I\)

III.B1.2.TP-42 III.B1.2- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No 1(T-29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; degradation!

grout pads for service-induced support base cracking or other plates concrete aging mechanisms III.B1.2.T-28 III.B1.2- Constant and Steel Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 2(T-28) variable load uncontrolled or mechanical Subsection IWF" spring Air - outdoor function I

(J) hangers; due to corrosion, guides; stops distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads III.B1.2.TP-45 III.B1.2- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 3(T-32) surfaces graphitic tool uncontrolled or mechanical Subsection IWF" steel; Air - outdoor function Fluorogold; due to corrosion, Lubrofluor distortion, dirt, debris, overload, wear 0 III.B1.2.TP-229 Structural Any Any Loss of preload Chapter XI.S3, "ASME Section XI, No CD C')

bolting environment due to self- Subsection IWF" CD loosening 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 (J) 0

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B1.2 Class 2 and 3 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B1.2.TP-232 Structural Stainless steel Treated water Loss of material Chapter XI.M2, "Water Chemistry," No bolting due to pitting and and crevice Chapter XI.S3, "ASME Section XI, corrosion Subsection IWF" III.B1.2.TP-226 Structural Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No Bolting uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion III.B1.2.TP-235 Structural Steel; Air - outdoor Loss of material Chapter XI.S3, "ASME Section XI, No bolting galvanized due to pitting Subsection IWF" steel and crevice corrosion III.B1.2.TP-8 III.B1.2- Support Aluminum; Air - indoor, None None No 4(TP-8) members; galvanized uncontrolled I

-J III.B1.2- welds; bolted steel; stainless 5(TP-11) connections; steel III.B1.2- support 7(TP-5) anchorage to building structure III.B1-2.TP-3 III.B1.2- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 6(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support z anchorage to c building

u m structure G)

I III.B1.2.TP-4 III.B1.2- Support Stainless steel Air with borated None None No 0 a 00 8(TP-4) members; water leakage G) welds; bolted

U 0 CD connections; 0

0  :< support

--" I\)

0)

CD 0

I 0

0 (J)

z III STRUCTURES AND COMPONENT SUPPORTS c

U B1.2 Class 2 and 3 m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< anchorage to I\)

building structure III.B1.2.T-26 III.B1.2- Support Steel Air - indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA 9 (T-26) members; uncontrolled fatigue damage analysis (TLAA) to be evaluated for welds; bolted due to fatigue the period of extended operation. See connections; (Only ifCLB the SRP, Section 4.3 "Metal Fatigue,"

support fatigue analysis for acceptable methods for meeting anchorage to exists) the requirements of 10 CFR building 54.21 (c)(1).

structure III.B1.2.T-24 III.B1.2- Support Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No 10(T-24) members; uncontrolled or due to general Subsection IWF" I

welds; bolted Air - outdoor and pitting 00 connections; corrosion support anchorage to building structure III.B1.2.T-25 III.B1.2- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 11 (T-25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion connections; support anchorage to building structure 0 III.B1.2.T-33 III.B1.2- Vibration Non-metallic Air - indoor, Reduction or Chapter XI.S3, "ASME Section XI, No CD C')

CD 12(T-33) isolation (e.g., rubber) uncontrolled or loss of isolation Subsection IWF" 0 elements Air - outdoor function

>> 3 0-G) ...,

CD due to radiation 0 I\) hardening, 0 a 0 temperature,

--" a 0)

CD 0

I 0

0 (J)

N

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD 81.2 Class 2 and 3 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component humidity, sustained vibratory loading I

CD z

c

u m

G)

I 0 a 00 G)

U 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 (J) 0)

z III STRUCTURES AND COMPONENT SUPPORTS c

U B1.3 Class MC (BWR Containment Supports) m G)

I 00 Structure a Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B1.3.TP-42 III.B1.3- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

1(T-29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; degradation!

grout pads for service-induced support base cracking or other plates concrete aging mechanisms III.B1.3.T-28 III.B1.3- Constant and Steel Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 2(T-28) variable load uncontrolled or mechanical Subsection IWF" spring Air - outdoor function hangers; due to corrosion, I

guides; stops distortion, dirt, a

overload, fatigue due to vibratory and cyclic thermal loads III.B1.3.TP-45 III.B1.3- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S3, "ASME Section XI, No 3(T-32) surfaces graphitic tool uncontrolled or mechanical Subsection IWF" steel; Air - outdoor function Fluorogold; due to corrosion, Lubrofluor distortion, dirt, debris, overload, wear III.B1.3.TP-229 Structural Any Any Loss of preload Chapter XI.S3, "ASME Section XI, No 0 bolting environment due to self- Subsection IWF" CD C') loosening CD 0 III.B1.3.TP-232 Structural Stainless steel Treated water Loss of material Chapter XI.M2, "Water Chemistry," No

>> 3 0-G) ...,

CD bolting due to pitting and 0 I\) and crevice Chapter XI.S3, "ASME Section XI, 0 a 0 corrosion Subsection IWF"

--" a 0)

CD 0

I 0

0 (J)

.j::>.

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B1.3 Class MC (BWR Containment Supports) 3 0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B1.3.TP-226 Structural Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No bolting uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion III.B1.3.TP-235 Structural Steel; Air - outdoor Loss of material Chapter XI.S3, "ASME Section XI, No bolting galvanized due to pitting Subsection IWF" steel and crevice corrosion III.B1-3.TP-8 III.B1.3- Support Aluminum; Air - indoor, None None No 4(TP-8) members; galvanized uncontrolled III.B1.3- welds; bolted steel; stainless 5(TP-11) connections; steel III.B1.3- support 7(TP-5) anchorage to I

building structure III.B1.3.TP-3 III.B1.3- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 6(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support anchorage to building structure III.B1.3.TP-4 III.B1.3- Support Stainless steel Air with borated None None No z 8(TP-4) members; water leakage c welds; bolted

u m connections; G)

I support 0 a 00 anchorage to G) building

U structure 0 CD 0

0  :<

--" I\)

0)

CD 0

I 0

0 (J)

(J1

z III STRUCTURES AND COMPONENT SUPPORTS c

U B1.3 Class MC (BWR Containment Supports) m G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B1.3.T-26 III.B1.3- Support Steel Air - indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA I\)

9(T-26) members; uncontrolled fatigue damage analysis (TLAA) to be evaluated for welds; bolted due to fatigue the period of extended operation. See connections; (Only ifCLB the SRP, Section 4.3 "Metal Fatigue,"

support fatigue analysis for acceptable methods for meeting anchorage to exists) the requirements of 10 CFR building 54.21 (c)(1).

structure III.B1.3.T-24 III.B1.3- Support Steel Air - indoor, Loss of material Chapter XI.S3, "ASME Section XI, No 1O(T-24) members; uncontrolled or due to general Subsection IWF" welds; bolted Air - outdoor and pitting connections; corrosion support anchorage to I

building I\)

structure III.B1.3.T-33 III.B1.3- Vibration Non-metallic Air - indoor, Reduction or Chapter XI.S3, "ASME Section XI, No 11 (T-33) isolation (e.g., rubber) uncontrolled or loss of isolation Subsection IWF" elements Air - outdoor function due to radiation hardening, temperature, humidity, sustained vibratory loading 0

CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 (J)

(J)

B2. SUPPORTS FOR CABLE TRAYS, CONDUIT, HVAC DUCTS, TUBETRACK, INSTRUMENT TUBING, NON-ASME PIPING AND COMPONENTS Systems, Structures, and Components This section addresses supports and anchorage for cable trays, conduit, heating, ventilation, and air-conditioning (HVAC) ducts, TubeTrack, instrument tubing, and non-ASME piping and components. Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events so that the supported element can perform its intended function.

December 201 0 11182-1 NUREG-1801, Rev. 2 OAGI0001390_00167

z III STRUCTURES AND COMPONENT SUPPORTS c

U B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components m

G)

I 00 Structure a Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B2.TP-42 III.B2-1 (T- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; grout degradation!

pads for service-induced support base cracking or other plates concrete aging mechanisms III.B2.TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures No structural steel, actual uncontrolled or due to stress Monitoring" bolting measured Air - outdoor corrosion III I\)

yield cracking Note: ASTM A 325, F 1852, and I

I\) strength ;::: ASTM A 490 bolts used in civil 150 ksi structures have not shown to be (1,034 MPa) prone to SCC. SCC potential need not be evaluated for these bolts.

III.B2.TP-46 III.B2- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S6, "Structures No 2(TP-1) support graphitic tool uncontrolled mechanical Monitoring" bearings; steel; function sliding Fluorogold; due to corrosion, support Lubrofluor distortion, dirt, surfaces debris, overload, wear III.B2.TP-47 III.B2- Sliding Lubrite; Air - outdoor Loss of Chapter XI.S6, "Structures No 3(TP-2) support graphitic tool mechanical Monitoring" 0 bearings; steel; function CD C') sliding Fluorogold; due to corrosion, CD support Lubrofluor distortion, dirt, 0

G) 3 0- surfaces debris, overload, CD wear 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 (J)

CD

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components 3

0-CD Structure Aging Effect/ Further I\)

a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B2.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures No bolting environment due to self- Monitoring" loosening III.B2.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No bolting uncontrolled due to general, Monitoring" pitting and crevice corrosion III.B2.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures No bolting galvanized due to general, Monitoring" steel pitting, and crevice corrosion III.B2.TP-8 III.B2- Support Aluminum; Air - indoor, None None No 4(TP-8) members; galvanized uncontrolled III III.B2- welds; bolted steel; I\)

I CJ.) 8(TP-5) connections; stainless III.B2- support steel 5(TP-11) anchorage to building structure III.B2.TP-3 III.B2- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 6(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support anchorage to z building c structure

u m III.B2.TP-6 III.B2- Support Galvanized Air - outdoor Loss of material Chapter XI.S6, "Structures No G)

I 7(TP-6) members; steel; due to pitting and Monitoring" 0

G) a 00 welds; bolted aluminum; crevice corrosion connections; stainless 0 ;U support steel 0 CD 0

< anchorage to 0)

CD 0

I 0

0 (J)

CD

z III STRUCTURES AND COMPONENT SUPPORTS c

U B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< building I\)

structure III.B2.TP-4 III.B2- Support Stainless Air with borated None None No 9(TP-4) members; steel water leakage welds; bolted connections; support anchorage to building structure III.B2.TP-43 III.B2- Support Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No 10(T-30) members; uncontrolled or due to general Monitoring" III I\)

I welds; bolted Air - outdoor and pitting

.j:>.

connections; corrosion support anchorage to building structure III.B2.T-25 III.B2- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 11 (T-25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion connections; support anchorage to building structure 0

CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0

-....J 0

B3. ANCHORAGE OF RACKS, PANELS, CABINETS, AND ENCLOSURES FOR ELECTRICAL EQUIPMENT AND INSTRUMENTATION Systems, Structures, and Components This section addresses supports and anchorage for racks, panels, cabinets, and enclosures for electrical equipment and instrumentation. Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events so that the supported element can perform its intended function.

December 201 0 11183-1 NUREG-1801, Rev. 2 OAGI0001390_00171

z III STRUCTURES AND COMPONENT SUPPORTS c

U B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation m

G)

I 00 Structure a Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< III.B3.TP-42 III.B3-1 (T- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; grout degradation!

pads for service-induced support base cracking or other plates concrete aging mechanisms III.B3.TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures No structural steel, actual uncontrolled or due to stress Monitoring" bolting measured Air - outdoor corrosion III CJ.)

yield cracking Note: ASTM A 325, F 1852, and I

I\) strength ;::: ASTM A 490 bolts used in civil 150 ksi structures have not shown to be (1,034 MPa) prone to SCC. SCC potential need not be evaluated for these bolts.

III.B3.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures No bolting environment due to self- Monitoring" loosening III.B3.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No bolting uncontrolled due to general, Monitoring" pitting and crevice corrosion III.B3.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures No bolting galvanized due to general, Monitoring" 0 steel pitting, and CD C')

CD crevice corrosion 0

G) 3 0-III.B3.TP-8 III.B3- Support Aluminum; Air - indoor, None None No CD 2(TP-8) members; galvanized uncontrolled 0 I\) III.B3- welds; bolted steel; 0 a 0 5(TP-5) connections; stainless

--" a 0)

CD 0

I 0

0

-....J N

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation 3

0-CD Structure I\) Aging Effect/ Further a Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation a Component III.B3- support steel 3(TP-11) anchorage to building structure III.B3.TP-3 III.B3- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 4(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support anchorage to building structure III.B3.TP-4 III.B3- Support Stainless Air with borated None None No III 6(TP-4) members; steel water leakage CJ.)

I CJ.) welds; bolted connections; support anchorage to building structure III.B3.TP-43 III.B3-7(T- Support Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No

30) members; uncontrolled or due to general Monitoring" welds; bolted Air - outdoor and pitting connections; corrosion support z anchorage to c building

u m structure G)

I III.B3.T-25 III.B3-8(T- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 0 a 00 25) members; water leakage due to boric acid Corrosion" G) welds; bolted corrosion

U connections; 0 CD 0

0  :< support 0)

CD 0

I 0

0

-....J 0)

z III STRUCTURES AND COMPONENT SUPPORTS c

U 83 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation m

G)

I 00 Structure a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

u Component CD

< anchorage to I\)

building structure 0

CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0

-....J

.j::>.

84. SUPPORTS FOR EMERGENCY DIESEL GENERATOR (EDG), HVAC SYSTEM COMPONENTS, AND OTHER MISCELLANEOUS MECHANICAL EQUIPMENT Systems, Structures, and Components This section addresses supports and anchorage for the emergency diesel generator (EOG) and HVAC system components, and other miscellaneous mechanical equipment. Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events so that the supported element can perform its intended function.

December 201 0 11184-1 NUREG-1801, Rev. 2 OAGI0001390_00175

z III STRUCTURES AND COMPONENT SUPPORTS c

U B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment m

G)

I 00 Structure a Aging Effect! Aging Management Program Further Item Link and!or Material Environment Mechanism (AMP) Evaluation

u Component CD

< III.B4.TP-42 III.B4-1 (T- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; degradation!

grout pads for service-induced support base cracking or other plates concrete aging mechanisms III.B4.TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures No structural steel, actual uncontrolled or due to stress Monitoring" bolting measured Air - outdoor corrosion III

.j:>.

yield strength cracking Note: ASTM A 325, F 1852, and I

I\)  ;::: 150 ksi ASTM A 490 bolts used in civil (1,034 MPa) structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts.

III.B4.TP-46 III.B4- Sliding Lubrite; Air - indoor, Loss of Chapter XI.S6, "Structures No 2(TP-1) support graphitic tool uncontrolled mechanical Monitoring" bearings; steel; function sliding Fluorogold; due to corrosion, support Lubrofluor distortion, dirt, surfaces debris, overload, wear III.B4.TP-47 III.B4- Sliding Lubrite; Air - outdoor Loss of Chapter XI.S6, "Structures No 3(TP-2) support graphitic tool mechanical Monitoring" 0 bearings; steel; function CD C') sliding Fluorogold; due to corrosion, CD support Lubrofluor distortion, dirt, 0

G) 3 0- surfaces debris, overload, CD wear 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0

-....J (J)

III STRUCTURES AND COMPONENT SUPPORTS oCD B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment C')

CD 3 Structure 0-CD Aging Effect/ Aging Management Program Further Item Link and/or Material Environment I\) Mechanism (AMP) Evaluation a Component a III.B4.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures No bolting environment due to self- Monitoring" loosening III.B4.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No bolting uncontrolled due to general, Monitoring" pitting and crevice corrosion III.B4.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures No bolting galvanized due to general, Monitoring" steel pitting, and crevice corrosion III.B4.TP-8 III.B4- Support Aluminum; Air - indoor, None None No 4(TP-8) members; galvanized uncontrolled III.B4- welds; bolted steel; stainless 8(TP-5) connections; steel III.B4- support 5(TP-11) anchorage to building structure III.B4.TP-3 III.B4- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 6(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support anchorage to building z structure c

u III.B4.TP-6 III.B4- Support Galvanized Air - outdoor Loss of material Chapter XI.S6, "Structures No m

G) 7(TP-6) members; steel; due to pitting Monitoring" 0 ......

I G) 00 welds; bolted aluminum; and crevice a connections; stainless steel corrosion 0 support 0 ;U 0 CD anchorage to

0)  :<

CD 0

I 0

0

-....J

-....J

z III STRUCTURES AND COMPONENT SUPPORTS c

U B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment m

G)

I 00 Structure a Aging Effect/ Aging Management Program Further Item Link and/or Material Environment Mechanism (AMP) Evaluation

u Component CD

< building I\)

structure III.B4.TP-4 III.B4- Support Stainless steel Air with borated None None No 9(TP-4) members; water leakage welds; bolted connections; support anchorage to building structure III.B4.TP-43 III.B4- Support Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No 10(T-30) members; uncontrolled or due to general Monitoring" welds; bolted Air - outdoor and pitting connections; corrosion support anchorage to building structure III.B4.T-25 III.B4- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 11 (T-25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion connections; support anchorage to building structure 0 III.B4.TP-44 III.B4- Vibration Non-metallic Air - indoor, Reduction or Chapter XI.S3, "ASME Section XI, No CD C')

CD 12(T-31) isolation (e.g., rubber) uncontrolled or loss of isolation Subsection IWF" 0 elements Air - outdoor function

>> 3 0-G) ...,

CD due to radiation 0 I\) hardening, 0 a 0 temperature,

--" a 0)

CD 0

I 0

0

-....J CD

III STRUCTURES AND COMPONENT SUPPORTS oCD 84 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment C')

CD 3 Structure 0-CD Aging Effect/ Aging Management Program Further Item Link and/or Material Environment I\) Mechanism (AMP) Evaluation a Component a humidity, sustained vibratory loading III

.j:>.

I 0'1 z

c

u m

G) 0 ......

I G) 00 a

0 0 ;U 0 CD

0)  :<

CD 0

I 0

0

-....J CD

85. SUPPORTS FOR PLATFORMS, PIPE WHIP RESTRAINTS, JET IMPINGEMENT SHIELDS, MASONRY WALLS, AND OTHER MISCELLANEOUS STRUCTURES Systems, Structures, and Components This section addresses supports and anchorage for platforms, pipe whip restraints, jet impingement shields, masonry walls, and other miscellaneous structures. Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events so that the supported element can perform its intended function.

December 201 0 11185-1 NUREG-1801, Rev. 2 OAGI0001390_00180

z c III STRUCTURES AND COMPONENT SUPPORTS

U m B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures G)

I 00 a Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

u Mechanism Evaluation Component CD

< III.B5.TP-42 III.B5-1 (T- Building Concrete; Air - indoor, Reduction in Chapter XI.S6, "Structures No I\)

29) concrete at grout uncontrolled or concrete anchor Monitoring" locations of Air - outdoor capacity expansion due to local and grouted concrete anchors; grout degradation!

pads for service-induced support base cracking or other plates concrete aging mechanisms III.B5.TP-300 High-strength Low-alloy Air - indoor, Cracking Chapter XI.S6, "Structures No structural steel, actual uncontrolled or due to stress Monitoring" bolting measured Air - outdoor corrosion III 0"1 I

yield cracking Note: ASTM A 325, F 1852, and I\) strength ;::: ASTM A 490 bolts used in civil 150 ksi structures have not shown to be (1,034 MPa) prone to SCC. SCC potential need not be evaluated for these bolts.

III.B5.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures No bolting environment due to self- Monitoring" loosening III.B5.TP-248 Structural Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No bolting uncontrolled due to general, Monitoring" pitting and crevice corrosion III.B5.TP-274 Structural Steel; Air - outdoor Loss of material Chapter XI.S6, "Structures No bolting galvanized due to general, Monitoring" 0

CD steel pitting, and C')

CD crevice corrosion 0 3

>> 0- III.B5.TP-8 III.B5- Support Aluminum; Air - indoor, None None No G) ...,

CD 2(TP-8) members; galvanized uncontrolled 0 I\)

0 a III.B5- welds; bolted steel; 0 a 5(TP-5) connections; stainless 0)

CD 0

I 0

0 CD

oCD III STRUCTURES AND COMPONENT SUPPORTS C')

CD B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures 3

0-CD Structure I\)

a Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) a Mechanism Evaluation Component III.B5- support steel 3(TP-11) anchorage to building structure III.B5.TP-3 III.B5- Support Galvanized Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 4(TP-3) members; steel; water leakage due to boric acid Corrosion" welds; bolted aluminum corrosion connections; support anchorage to building structure III.B5.TP-4 III.B5- Support Stainless Air with borated None None No III 0'1 6(TP-4) members; steel water leakage I

CJ.) welds; bolted connections; support anchorage to building structure III.B5.TP-43 III.B5-7(T- Support Steel Air - indoor, Loss of material Chapter XI.S6, "Structures No

30) members; uncontrolled or due to general Monitoring" welds; bolted Air - outdoor and pitting connections; corrosion support z anchorage to c building

u m structure G)

I III.B5.T-25 III.B5-8(T- Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 00 0 a 25) members; water leakage due to boric acid Corrosion" G) welds; bolted corrosion

U 0 CD connections; 0

0

< support

--" I\)

0)

CD 0

I 0

0 CD N

z c III STRUCTURES AND COMPONENT SUPPORTS

U m 85 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures G)

I 00 a Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

u Mechanism Evaluation Component CD

< anchorage to I\)

building structure III 0'1 I

.j:>.

0 CD C')

CD 0 3

>> 0-G) ...,

CD 0 I\)

0 a 0 a 0)

CD 0

I 0

0 CD 0)

CHAPTER IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM December 201 0 IV-i NUREG-1801, Rev. 2 OAGI0001390_00184

MAJOR PLANT SECTIONS A 1. Reactor Vessel (Boiling Water Reactor)

A2. Reactor Vessel (Pressurized Water Reactor)

B1. Reactor Vessel Internals (Boiling Water Reactor)

B2. Reactor Vessel Internals (PWR) - Westinghouse B3. Reactor Vessel Internals (PWR) - Combustion Engineering B4. Reactor Vessel Internals (PWR) - Babcock and Wilcox C1. Reactor Coolant Pressure Boundary (Boiling Water Reactor)

C2. Reactor Coolant System and Connected Lines (Pressurized Water Reactor)

01. Steam Generator (Recirculating)

02. Steam Generator (Once-Through)

E. Common Miscellaneous Material/Environment Combinations December 201 0 IV-iii NUREG-1801, Rev. 2 OAGI0001390_00185

A1.REACTOR VESSEL (BOILING WATER REACTOR)

Systems, Structures, and Components This section addresses the boiling water reactor (BWR) pressure vessel and consists of the vessel shell and flanges, attachment welds, top and bottom heads, nozzles (including safe ends) for the reactor coolant recirculating system and connected systems (such as high and low pressure core spray, high and low pressure coolant injection, main steam, and feedwater systems), penetrations for control rod drive (CRD) stub tubes, instrumentation, standby liquid control, flux monitor, drain lines, and control rod drive mechanism housings. The support skirt and attachment welds for vessel supports are also included in the following table for the BWR vessel. Based on Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants," all structures and components that comprise the reactor vessel are governed by Group A Quality Standards.

Common miscellaneous material/environment combinations where aging effects are not expected to degrade the ability of the structure or component to perform its intended function for the period of extended operation are included in IV.E.

System Interfaces The systems that interface with the reactor vessel include the reactor vessel internals (lV.B1),

the reactor coolant pressure boundary (lV.C1), the emergency core cooling system (V.D2), and the standby liquid control system (VII.E2).

December 201 0 IV A1-1 NUREG-1801, Rev. 2 OAGI0001390_00186

z IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM c

U A1 Reactor Vessel (BWR) m G)

I 00 a Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

u CD

< IV.A1.R-68 IV.A 1-1 (R- Nozzle safe ends Stainless Reactor coolant Cracking Chapter XI.M7, "BWR Stress No I\)

68) and welds: high- steel; due to stress Corrosion Cracking," and pressure core nickel alloy corrosion Chapter XI.M2, "Water Chemistry" spray; low cracking, pressure core intergranular spray; control rod stress corrosion drive return line; cracking recirculating water; low pressure coolant injection or RHR injection mode

<: IV.A1.R-66 IV.A1-2(R- Nozzles: control Steel (with Reactor coolant Cracking Chapter XI.M6, "BWR Control Rod No

...... 66) rod drive return or without due to cyclic Drive Return Line Nozzle" I

I\) line stainless loading steel cladding)

IV.A1.R-65 IV.A1-3(R- Nozzles: Steel (with Reactor coolant Cracking Chapter XI.M5, "BWR Feedwater No

65) feedwater or without due to cyclic Nozzle" stainless loading steel cladding) 0 CD C')

CD 0

G) 3 0-CD 0 I\)

0 a 0

--" a 0)

CD 0

I 0

0 CD

-....J

oCD IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM C')

CD A1 Reactor Vessel (BWR) 3 0-CD I\) Structure and!or Aging Effect! Further a Item Link Material Environment Aging Management Program (AMP) a Component Mechanism Evaluation IV.A1.R-67 IV.A1-4(R- Nozzles: low- Steel Reactor coolant Loss of fracture Neutron irradiation embrittiement is a Yes, TLAA

67) pressure coolant and neutron flux toughness time-limited aging analysis (TLAA) to injection or RHR due to neutron be evaluated for the period of injection mode irradiation extended operation for all ferritic embrittlement materials that have a neutron fluence 2

greater than 1E17 n!cm (E >1 MeV) at the end of the period of extended operation. In accordance with approved BWRVIP-74, the TLAA is to evaluate the impact of neutron embrittiement on: (a) the adjusted reference temperature values used for

<: calculation of the plant's pressure-

...... temperature limits, (b) the need for I

CJ.) inservice inspection of circumferential welds, and (c) the Charpy upper shelf energy or the equivalent margins analyses performed in accordance with 10 CFR Part 50, Appendix G The applicant may choose to demonstrate that the materials of the nozzles are not controlling for the TLAA evaluations. See the Standard Review Plan, Section 4.2 "Reactor Vessel Neutron Embrittiement" for acceptable methods for meeting the requirements z of 10 CFR 54.21 (c).

c

u m

G)

I 0 00 G) a 0 ;U 0 CD 0 <

--" i\J 0)

CD 0

I 0

0 CD CD

z IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM c

U A1 Reactor Vessel (BWR) m G)

I 00 a Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

u CD

< IV.A1.RP-369 IV.A1-5(R- Penetrations: Stainless Reactor coolant Cracking Chapter XI.M8, "BWR Penetrations," No I\)

69) control rod drive steel; due to stress and stub tubes; in nickel alloy corrosion Chapter XI.M2, "Water Chemistry" core monitor cracking, housings; jet intergranular pump instrument; stress corrosion standby liquid cracking, cyclic control; flux loading monitor IV.A1.RP-371 IV.A1-5(R- Penetrations: Stainless Reactor coolant Cracking Chapter XI.M1, "ASME Section XI No

69) drain line steel; due to stress Inservice Inspection, Subsections nickel alloy corrosion IWB, IWC, and IWD," and

<: cracking, Chapter XI.M2, "Water Chemistry"

...... intergranular I

.j:>. stress corrosion cracking, cyclic loading IV.A1.R-70 IV.A1-6(R- Pressure vessel Steel Air - indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA

70) support skirt and uncontrolled fatigue damage (TLAA) to be evaluated for the period attachment welds due to fatigue of extended operation. See the SRP, Section 4.3 "Metal Fatigue," for acceptable methods for meeting the requirements of 10 CFR 54.21 (c)(1).

IV.A1.R-04 IV.A1-7(R- Reactor vessel Steel (with Reactor coolant Cumulative Fatigue is a TLAA evaluated for the Yes, TLAA

04) components: or without fatigue damage period of extended operation, and for flanges; nozzles; nickel-alloy due to fatigue Class 1 components environmental penetrations; safe or effects on fatigue are to be addressed.

0 ends; thermal stainless (See SRP, Sec 4.3 "Metal Fatigue," for CD C') sleeves; vessel steel acceptable methods to comply with 10 CD 0 shells, heads and cladding); CFR 54.21 (c)(1))

G) 3 0- welds stainless CD 0 I\) steel; 0 a nickel alloy 0

--" a 0)

CD 0

I 0

0 CD CD