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 In the Matter of

Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:

Identified:

Admitted: Withdrawn:

Rejected: Stricken: Other: NYS00147A-00-BD01 10/15/2012 10/15/2012 NYS00147A Submitted: December 15, 2011

""tP-f'REGU(.q" 0 " : i Y'1J.: 0' ? '" .. ** ** ci;U.S.NRC NUREG-1801, Rev. 2 United States Nuclear Regulatory Commission 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 As of November 1999, you may electronically access NUREG-series publications and other NRC records at NRC's Public Electronic Reading Room at bitp..:1!YY.YlilN

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OAGI0001390_00002

United States Nuclear Regulatory Commission 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 NUREG-1801, Rev. 2 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 A 1 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 A 1 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 A 1 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 L. Yee O.Yee Materials Engineering Administrative Assistant Mechanical Engineering Office of Nuclear Reactor Regulation G. Casto T. Chan M. Khanna A. Klein T. Lupoid M. Mitchell R. Taylor G. Wilson R. Hardies K. Karwoski K. Manoly D. Alley J. Bettie T. Cheng G. Cheruvenki J. Collins R. Davis S. Gardocki M. Hartzman K. Hoffman N. Iqbal A. Johnson S.Jones B. Lee R. Mathew P. Patniak G. Purciarello A. Tsirigotis M. Yoder E. Wong NUREG-1801, Rev. 2 Branch Chief Branch Chief Branch Chief Branch Chief Branch Chief Branch Chief Branch Chief Branch Chief Senior Level -Materials Engineering Senior Level -Steam Generators Senior Level -Structural Engineering Materials Engineering Mechanical Engineering Structural Engineering Materials Engineering Mechanical Engineering Materials Engineering Mechanical Engineering Materials Engineering Mechanical Engineering Fire Protection Engineering Mechanical Engineering Mechanical Engineering Mechanical Engineering Electrical Engineering Mechanical Engineering Mechanical Engineering Mechanical Engineering Chemical Engineering Chemical Engineering xii December 201 0 OAGI0001390_00011 Region I G. Meyer M. Modes Mechanical Engineering Mechanical Engineering Office of Nuclear Regulatory Research A. Csontos M. Gavrilas R. Hogan T. Koshy M. Salley R. Tregoning S. Aggarwal J. Burke G. Carpenter H. Graves A. Hull B.Lin L. Ramadan G. Stevens D. Stroup G. Wang Branch Chief Branch Chief Branch Chief Branch Chief Branch Chief Senior Level -Materials Engineering Electrical Engineering Mechanical Engineering Materials Engineering Structural Engineering Materials Engineering Structural Engineering Electrical Engineering Materials Engineering Fire Protection Engineering Mechanical Engineering Advanced Technologies and Laboratories International, Inc. (A TL) K. Makeig K. Chang O. Chopra W. Jackson D. Jones M. May A. Ouaou E. Patel J. Davis R. Royal T. Brake December 201 0 Project Manager Mechanical Engineering Materials Engineering Mechanical Engineering Programming (Project Enhancement Corp.) Mechanical Engineering Structural Engineering Mechanical Engineering Materials Engineering Electrical Engineering Technical Editing xiii NUREG-1801, Rev. 2 OAGI0001390_00012 ACAR ACRS ACI ADS AFW ALARA AMP AMR ANSI ASCE ASME ASTM B&PV B&W BWR BWRVIP CASS CB CCCW CE CEA CFR CFS CLB CRD CRDM CRDRL CRGT CVCS DC DHR DSCSS EDG EPDM EPR EPRI December 201 0 ABBREVIA TIONS aluminum conductor aluminum alloy reinforced aluminum conductor steel reinforced American Concrete Institute automatic depressurization system auxiliary feedwater as low as reasonably achievable aging management program aging management review American National Standards Institute American Society of Civil Engineers American Society of Mechanical Engineers American Society for Testing and Materials boiler and pressure vessel Babcock & Wilcox boiling water reactor Boiling Water Reactor Vessel and Internals Project cast austenitic stainless steel core barrel closed-cycle cooling water Combustion Engineering control element assembly Code of Federal Regulations core flood system current licensing basis control rod drive control rod drive mechanism control rod drive return line control rod guide tube chemical and volume control system direct current decay heat removal drywell and suppression chamber spray system emergency diesel generator ethylene propylene diene monosomer ethylene-propylene rubber Electric Power Research Institute xv NUREG-1801, Rev. 2 OAGI0001390_00013 EQ FAC FERC FRN FSAR FW GALL GE GL HOPE HELBs HP HPCI HPCS HPSI HVAC I&C IASCC IC 10 IEB IEEE IGA IGSCC IN INPO IPA IR IRM lSI LER LG LOCA LP LPCI LPCS environmental qualification flow-accelerated corrosion Federal Energy Regulatory Commission Federal Register Notice Final Safety Analysis Report feedwater Generic Aging Lessons Learned General Electric generic letter high density polyethylene high-energy line breaks high pressure high-pressure coolant injection high-pressure core spray high-pressure safety injection heating, ventilation, and air conditioning instrumentation and control irradiation assisted stress corrosion cracking isolation condenser inside diameter inspection and enforcement bulletin Institute of Electrical and Electronics Engineers intergranular attack intergranular stress corrosion cracking information notice Institute of Nuclear Power Operations integrated plant assessment insulation resistance intermediate range monitor inservice inspection licensee event report lower grid loss of coolant accident low pressure low-pressure coolant injection low-pressure core spray NUREG-1801, Rev. 2 xvi December 201 0 OAGI0001390_00014 LPM LPRM LPSI LRAAI LRT LWR MFW MIC MS MSR MT NOE NEI NFPA NPAR NPS NRC NRMS NSAC NSSS NUMARC OCCW 00 OOSCC OM PT PVC PWR PWSCC QA RCCA RCIC RCP RCPB RCS December 201 0 loose part monitoring low-power range monitor low-pressure safety injection license renewal applicant action items leak rate test light water reactor main feedwater microbiologically influenced corrosion main steam moisture separatorireheater magnetic particle testing nondestructive examination Nuclear Energy Institute National Fire Protection Association nuclear plant aging research nominal pipe size Nuclear Regulatory Commission normalized root mean square Nuclear Safety Analysis Center nuclear steam supply system Nuclear Management and Resources Council open-cycle cooling water outside diameter outside diameter stress corrosion cracking operation and maintenance penetrant testing polyvinyl chloride pressurized water reactor primary water stress corrosion cracking quality assurance rod control cluster assemblies reactor core isolation cooling reactor coolant pump reactor coolant pressure boundary reactor coolant system xvii NUREG-1801, Rev. 2 OAGI0001390_00015 RG RHR RMS RWC RWST RWT SAW SCC SOC SFP SG S/G SIL SIT SLC SOER SR SRM SRM SRP-LR SS SSC TGSCC TLAA UCS UHS USI UT UV XPLE Regulatory Guide residual heat removal root mean square reactor water cleanup refueling water storage tank refueling water tank submerged arc weld stress corrosion cracking shutdown cooling spent fuel pool steam generator standards and guides services information letter safety injection tank standby liquid control significant operating experience report silicon rubber source range monitor staff requirements memorandum standard review plan for license renewal stainless steel systems, structures, and components transgranular stress corrosion cracking time-limited aging analysis Union of Concerned Scientists ultimate heat sink unresolved safety issue ultrasonic testing ultraviolet 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 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 I RS. 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 December 201 0 CHAPTER I APPLICATION OF THE ASME CODE 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 1 O-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 December 201 0 CHAPTER II CONTAINMENT STRUCTURES 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.CP-II.A 1-4(C-Concrete Concrete Air -indoor, 87 03) (accessible uncontrolled or areas): dome; Air -outdoor wall; basemat; ring girders; buttresses II.A1.CP-II.A1-2(C-Concrete Concrete Air -outdoor 31 01 ) (accessible areas): dome; wall; basemat; ring girders; buttresses II.A1.CP-II.A1-3(C-Concrete Concrete Any environment 33 04) (accessible areas): dome; wall; basemat; ring girders; buttresses II.A1.CP-II.A 1-6(C-Concrete Concrete Water -flowing 32 02) (accessible areas): dome; wall; basemat; ring girders; buttresses II.A1.CP-II.A 1-7(C-Concrete Concrete; Air -indoor, 68 05) (accessible steel uncontrolled or areas): dome; Air -outdoor wall; basemat; ring girders; buttresses; reinforcing steel Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Increase in porosity Chapter XI.S2, "ASME Section XI, No and permeability; Subsection IWL" cracking; loss of material (spalling, scaling) due to aggressive chemical attack Loss of material Chapter XI.S2, "ASME Section XI, No (spalling, scaling) Subsection IWL" and cracking due to freeze-thaw Cracking Chapter XI.S2, "ASME Section XI, No due to expansion Subsection IWL" from reaction with aggregates Increase in porosity Chapter XI.S2, "ASME Section XI, No and permeability; Subsection IWL" loss of strength due to leaching of calcium hydroxide and carbonation Cracking; loss of Chapter XI.S2, "ASME Section XI, No bond; and loss of Subsection IWL" material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) (J1 o CD C') CD 3 0-CD ..., I\) a a >> ...... I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.CP-II.A 1-4(C-Concrete Concrete Air -indoor, 100 03) (inaccessible uncontrolled or areas): dome; Air -outdoor or wall; basemat; Ground ring girders; water/soil buttresses II.A1.CP-II.A1-2(C-Concrete Concrete Air -outdoor or 147 01 ) (inaccessible Ground areas): dome; water/soil wall; basemat; ring girders; buttresses Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Increase in porosity Chapter XI.S2, "ASME Section XI, No and permeability; Subsection IWL," or cracking; loss of Chapter XI.S6, " Structures Monitoring" material (spalling, scaling) due to aggressive chemical attack Loss of material Further evaluation is required for plants Yes, for plants (spalling, scaling) that are located in moderate to severe located in and cracking weathering conditions (weathering index moderate to 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-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.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) (J) z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.CP-II.A1-3(C-Concrete Concrete Any environment 67 04) (inaccessible areas): dome; wall; basemat; ring girders; buttresses II.A1.CP-II.A 1-6(C-Concrete Concrete Water -flowing 102 02) (inaccessible areas): dome; wall; basemat; ring girders; buttresses Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not 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 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.

Increase in porosity Further evaluation is required to Yes, if and permeability; determine if a plant-specific aging leaching is loss of strength management program is needed to observed in due to leaching of manage increase in porosity, and accessible calcium hydroxide permeability due to leaching of calcium areas that and carbonation hydroxide and carbonation of concrete in impact 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) -....J o CD C') CD 3 0-CD ..., I\) a a >> ...... I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.CP-II.A 1-7(C-Concrete Concrete; Air -indoor, 97 05) (inaccessible steel uncontrolled or areas): dome; Air -outdoor wall; basemat; ring girders; buttresses; reinforcing steel II.A1.CP-II.A1-1(C-Concrete:

Concrete Air -indoor, 34 08) dome; wall; uncontrolled or basemat; ring Air -outdoor girders; buttresses Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure.

Cracking; loss of Chapter XI.S2, "ASME Section XI, No bond; and loss of Subsection IWL," or material (spalling, Chapter XI.S6, " Structures Monitoring" scaling) due to corrosion of embedded steel Reduction of Plant-specific aging management Yes, if strength and program temperature 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 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, such as around penetrations, which are not allowed to exceed 200°F. If significant equipment loads are supported by concrete at temperatures 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) CD z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I (J) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.CP-II.A1-5(C-Concrete:

Concrete Soil 101 37) dome; wall; basemat; ring girders; buttresses II.A1.C-07 II.A1-8(C-Concrete: Concrete; Water -flowing 07) foundation; porous subfoundation concrete II.A 1.C-11 II.A1-9(C-Prestressing Steel Air -indoor, 11 ) system: uncontrolled or tendons Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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.

Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-distortion Subsection IWL," or watering due to increased Chapter XI.S6, " Structures Monitoring" system is stress levels from If a de-watering system is relied upon for relied upon to 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.

Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation strength If a de-watering system is relied upon for watering 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 Loss of prestress Loss of tendon prestress is a time-Yes, TLAA due to relaxation; limited aging analysis (TLAA) to be shrinkage; creep; evaluated for the period of extended elevated operation.

temperature See the SRP, Section 4.5, "Concrete Containment Tendon Prestress" for 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 0) CD o CD C') CD 3 0-CD ..., I\) a a >> ...... I -J z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A1 Concrete Containments (Reinforced and Prestressed)

Structure Item Link and/or Material Environment Component II.A1.C-10 II.A1-Prestressing Steel Air -indoor, 1 0(C-1 0) system: uncontrolled or tendons; Air -outdoor anchorage components II.A1.CP-II.A1-Steel elements Steel Air -indoor, 35 11 (C-09) (accessible uncontrolled areas): liner; liner anchors; integral attachments II.A1.CP-II.A1-Steel elements Steel Air -indoor, 98 11 (C-09) (inaccessible uncontrolled areas): liner; liner anchors; integral attachments Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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. Loss of material Chapter XI.S2, "ASME Section XI, No due to corrosion Subsection IWL" Loss of material Chapter XI.S1, "ASME Section XI, No due to general, Subsection IWE," and pitting, and crevice Chapter XI.S4, "10 CFR Part 50, corrosion AppendixJ" Loss of material Chapter XI.S1, "ASME Section XI, Yes, if due to general, Subsection IWE" and corrosion is pitting, and crevice indicated from corrosion Chapter XI.S4, "10 CFR Part 50, the IWE AppendixJ" examinations Additional plant-specific activities are warranted if loss of material due to 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:

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. 0 z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I 00 0 CD C') CD 3 0-CD ..., I\) a a II A1 Item CONTAINMENT STRUCTURES Concrete Containments (Reinforced and Prestressed)

Structure Aging Effect/ Link and/or Material Environment Component Mechanism Further Aging Management Program (AMP) Evaluation

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

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. N z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Material Component II.A2.CP-51 II.A2-2(C-Concrete Concrete

28) (accessible areas): basemat II.A2.CP-58 II.A2-3(C-Concrete Concrete

38) (accessible areas): basemat II.A2.CP-72 II.A2-4(C-Concrete Concrete

25) (accessible areas): basemat II.A2.CP-155 II.A2-6(C-Concrete Concrete

30) (accessible areas): basemat II.A2.CP-74 II.A2-7(C-Concrete Concrete;

43) (accessible steel areas): basemat; reinforcing steel Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -outdoor Loss of material Chapter XI.S2, "ASME Section XI, No (spalling, scaling) Subsection IWL" and cracking due to freeze-thaw Any Cracking Chapter XI.S2, "ASME Section XI, No environment due to expansion Subsection IWL" from reaction with aggregates Ground Increase in Chapter XI.S2, "ASME Section XI, No water/soil porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack Water -flowing Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL" permeability; loss of strength due to leaching of calcium hydroxide and carbonation Air -indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No uncontrolled or bond; and loss of Subsection IWL" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. 0) o CD C') CD 3 0-CD ..., I\) a a >> I\) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Component II.A2.CP-70 II.A2-2(C-Concrete 28) (inaccessible areas): basemat II.A2.CP-104 II.A2-3(C-Concrete 38) (inaccessible areas): basemat Material Environment Concrete Air -outdoor or Ground water/soil Concrete Any environment Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Loss of material Further evaluation is required for Yes, for plants (spalling, scaling) plants that are located in moderate to located in and cracking severe weathering conditions moderate to 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 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 inaccessible areas. The weathering index for the continental US is shown in ASTM C33-90, Fig. 1. Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Component II.A2.CP-71 II.A2-4(C-Concrete 25) (inaccessible areas): basemat II.A2.CP-53 II.A2-6(C-Concrete 30) (inaccessible areas): basemat Material Environment Concrete Ground water/soil Concrete Water -flowing Aging Effect/ Further Aging Management Program (AMP) 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 concrete can perform its intended function . Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL," or permeability; Chapter XI.S6, II Structures cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack Increase in Further evaluation is required to Yes, if porosity and determine if a plant-specific aging leaching is permeability; loss management program is needed to observed in 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. (J1 o CD C') CD 3 0-CD ..., I\) a a >> I\) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Component II.A2.CP-75 II.A2-7(C-Concrete 43) (inaccessible areas): basemat; reinforcing steel II.A2.CP-69 II.A2-5(C-Concrete:

36) basemat II.A2.C-07 II.A2-8(C-Concrete:

07) foundation; subfoundation Material Environment Concrete; Air -indoor, steel uncontrolled or Air -outdoor Concrete Soil Concrete; Water -flowing porous concrete Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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.

Cracking; loss of Chapter XI.S2, "ASME Section XI, No bond; and loss of Subsection IWL," or material (spalling, Chapter XI.S6, " Structures scaling) Monitoring" due to corrosion of embedded steel Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-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.

Reduction of Chapter XI.S6, " Structures Yes, if a de-foundation Monitoring" watering 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. (J) z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I (J) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Material Environment Component II.A2.CP-35 II.A2-9(C-Steel Steel Air -indoor, 09) elements uncontrolled (accessible areas): liner; liner anchors; integral attachments II.A2.CP-98 II.A2-9(C-Steel Steel Air -indoor, 09) elements uncontrolled (inaccessible areas): liner; liner anchors; integral attachments Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation erosion of porous functioning of the de-watering system concrete through the period of extended su bfou ndation operation.

Loss of material Chapter XI.S1, "ASME Section XI, No due to general, Subsection IWE," and pitting, and Chapter XI.S4, "10 CFR Part 50, crevice corrosion AppendixJ" Loss of material Chapter XI.S1, "ASME Section XI, Yes, if due to general, Subsection IWE" and corrosion is pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from crevice corrosion Appendix J" the IWE Additional plant-specific activities are examinations warranted if loss of material due to 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. 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.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. -....J o CD C') CD 3 0-CD ..., I\) a a >> I\) I -J z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES A2 Steel Containments Structure Item Link and/or Material Component Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation

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 be satisfied, then a plant-specific aging management program for corrosion is necessary.

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 .j::>. CD z c ;U m G) I ...... 00 a ;u CD < i\J >> CJ.) I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES A3 Common Components Structure Item Link and/or Component II.A3.CP-40 II.A3-7(C-Moisture 18) barriers (caulking, flashing, and other sealants)

II.A3.CP-36 II.A3-1 (C-Penetration

12) sleeves II.A3.CP-38 II.A3-2(C-Penetration

15) sleeves; penetration bellows II.A3.CP-37 II.A3-3(C-penetration

14) sleeves; penetration bellows II.A3.C-13 II.A3-4(C-Penetration

13) sleeves; penetration bellows II.A3.C-16 II.A3-6(C-Personnel

16) airlock, equipment hatch, CRD hatch Material Elastomers, rubber and other similar materials Steel; dissimilar metal welds Stainless steel; dissimilar metal welds Steel; stainless steel; dissimilar metal welds Steel; stainless

steel; dissimilar metal welds Steel Aging Effect! Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of sealing Chapter XI.S1, "ASME Section XI, No uncontrolled due to wear, Subsection IWE" damage, erosion, tear, surface cracks, or other defects Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Air -outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice Appendix J" corrosion Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, Yes, detection uncontrolled or due to stress Subsection IWE," and of aging Air -outdoor corrosion Chapter XI.S4, "10 CFR Part 50, effects is to be cracking AppendixJ" evaluated Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled or due to cyclic Subsection IWE," and Air -outdoor loading Chapter XI.S4, "10 CFR Part 50, (CLB fatigue Appendix J" analysis does not exist) Air -indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA uncontrolled or fatigue damage (TLAA) to be evaluated for the period Air -outdoor 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). Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Air -outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice Appendix J" corrosion 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 0 o CD C') CD 3 0-CD ..., I\) a a >> CJ.) I CJ.) z c ;u m G) I ...... 00 a ;U CD < i\J II CONTAINMENT STRUCTURES A3 Common Components Structure Item Link and/or Material Component II.A3.CP-39 II.A3-5(C-Personnel Steel 17) airlock, equipment hatch, CRD hatch: locks, hinges, and closure mechanisms II.A3.CP-150 Pressure-Any retaining bolting II.A3.CP-148 Pressure-Steel retaining bolting II.A3.CP-41 II.A3-7(C-Seals and Elastomers, 18) gaskets rubber and other similar materials II.A3.CP-152 Service Level Coatings I coatings Aging Effect! Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of leak Chapter XI.S1, "ASME Section XI, No uncontrolled or tightness Subsection IWE," and Air -outdoor due to Chapter XI.S4, "10 CFR Part 50, mechanical wear Appendix J" of locks, hinges and closure mechanisms Any Loss of preload Chapter XI.S1, "ASME Section XI, No environment due to self-Subsection IWE," and loosening Chapter XI.S4, "10 CFR Part 50, AppendixJ" Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE" Air -outdoor pitting, and crevice corrosion Air -indoor, Loss of sealing Chapter XI.S4, "10 CFR Part 50, No uncontrolled or due to wear, AppendixJ" Air -outdoor damage, erosion, tear, surface cracks, or other defects Air -indoor, Loss of coating Chapter XI.S8, "Protective Coating No uncontrolled integrity Monitoring and Maintenance" due to blistering, cracking, flaking, peeling, or physical damage 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 0) z c ;U m G) I ...... 00 a ;u CD :< I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B1.1 Mark I Steel Containments Structure Item Link and/or Material Component II.B1.1.CP-43 II.B1.1-Steel elements Steel 2(C-19) (accessible areas): drywell shell; drywell head; drywell shell in sand pocket regions; II.B1.1.C-23 II.B1.1-Steel elements:

Steel 1 (C-23) drywell head; downcomers II.B1.1.CP-44 Steel elements:

Steel drywell support skirt II.B1.1.CP-109 II.B1.1-Steel elements:

Steel 2(C-19) torus ring girders; downcomers; II.B1.1.CP-48 II.B1.1-Steel elements:

Steel 2(C-19) torus shell Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled due to general, Subsection IWE," and pitting, and Chapter XI.S4, "10 CFR Part 50, crevice Appendix J" corrosion Air -indoor, Fretting or Chapter XI.S1, "ASME Section XI, No uncontrolled lockup Subsection IWE" due to mechanical wear Concrete None None No Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE" corrosion is Treated water pitting, and significant 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 review. Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE," and corrosion is Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, significant crevice Appendix J" Recoating of corrosion Significant corrosion of the torus shell the torus is 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 .j::>. o CD C') CD 3 0-CD ..., I\) a a I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B1.1 Mark I Steel Containments Structure Item Link and/or Component II.B1.1.CP-49 II.B1.1-Steel elements:

3(C-20) torus; vent line; vent header; vent line bellows; downcomers II.B1.1.C-21 II.B1.1-Steel elements:

4(C-21) torus; vent line; vent header; vent line bellows; downcomers II.B1.1.CP-50 II.B1.1-Steel elements:

5(C-22) vent line bellows Material Environment Steel; Air -indoor, stainless uncontrolled steel Steel; Air -indoor, stainless uncontrolled steel Stainless Air -indoor, steel uncontrolled Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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 and subject to aging management review. Cracking Chapter XI.S1, "ASME Section XI, No due to cyclic Subsection IWE," and loading Chapter XI.S4, "10 CFR Part 50, (CLB fatigue Appendix J" analysis does not exist) Cumulative Fatigue is a time-limited aging analysis Yes, TLAA fatigue damage (TLAA) to be evaluated for the period of due to fatigue 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). Cracking Chapter XI.S1, "ASME Section XI, No due to stress Subsection IWE," and corrosion Chapter XI.S4, "10 CFR Part 50, cracking AppendixJ" 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 (J1 z c ;U m G) I ...... 00 a ;u CD :< I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Material Component II.B1.2.CP-79 II.B1.2-Concrete Concrete; 2(C-41) (accessible steel areas): basemat; reinforcing steel II.B1.2.CP-S9 II.B1.2-Concrete Concrete 4(C-39) (accessible areas): containment; wall; basemat II.B1.2.CP-S4 II.B1.2-Concrete Concrete 6(C-31) (accessible areas): containment; wall; basemat II.B1.2.CP-80 II.B1.2(C-Concrete Concrete;

41) (inaccessible steel areas): basemat; reinforcing steel II.B1.2.CP-99 II.B1.2-Concrete Concrete 4(C-39) (inaccessible areas):

containment; wall; basemat Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No uncontrolled or bond; and loss of Subsection IWL" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel Any Cracking Chapter XI.S2, "ASME Section XI, No environment due to expansion Subsection IWL" from reaction with aggregates Water -flowing Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL" permeability; loss of strength due to leaching of calcium hydroxide and carbonation Air -indoor, Cracking; loss of Chapter XI.S6, "Structures No uncontrolled or bond; and loss of Monitoring" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel Any Cracking Further evaluation is required to Yes, if environment due to expansion determine if a plant-specific aging concrete is not from reaction with management program is needed to constructed as aggregates manage cracking and expansion due stated to reaction with aggregate of concrete in Inaccessible Areas. A plant-specific 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 (J) o CD C') CD 3 0-CD ..., I\) a a I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Component II.B1.2.CP-110 II.B1.2-Concrete 6(C-31) (inaccessible areas): containment; wall; basemat Aging Effect/ Material Environment Mechanism Concrete Water -flowing Increase in porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Further Aging Management Program (AMP) 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 concrete can perform its intended function.

Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of areas that calcium hydroxide and carbonation of impact 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 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.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 -....J z c ;U m G) I ...... 00 a ;u CD :< I\) I (J) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Component II.B1.2.CP-10S II.B1.2-Concrete 1 (C-06) elements, all II.B1.2.CP-106 II.B1.2-Concrete:

S(C-26) containment; wall; basemat II.B1.2.CP-S7 II.B1.2-Concrete:

3(C-3S) containment; wall; basemat Material Environment Concrete Soil Concrete Air -indoor, uncontrolled or Air -outdoor Concrete Air -indoor, uncontrolled or Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-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.

Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack Reduction of Plant-specific aging management Yes, if strength and program temperature 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 specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 CD o CD C') CD 3 0-CD ..., I\) a a I -J z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Component II.B1.2.C-07 II.B1.2-Concrete:

7(C-07) foundation; subfoundation II.B1.2.CP-46 II.B1.2-Steel elements 8(C-46) (accessible areas): suppression chamber; Material Environment Concrete; Water -flowing porous concrete Steel Air -indoor, uncontrolled or Treated water Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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 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.

Reduction of Chapter XI.S6, "Structures Yes, if a de-foundation Monitoring" watering 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 erosion of porous functioning of the de-watering system concrete through the period of extended subfoundation operation.

Loss of material Chapter XI.S1, "ASME Section XI, No due to general, Subsection IWE," and pitting, and Chapter XI.S4, "10 CFR Part 50, crevice corrosion AppendixJ" 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J1 CD z c ;U m G) I ...... 00 a ;u CD :< I\) I 00 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Material Component drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

II.B1.2.CP-114 Steel elements Steel (inaccessible areas): support skirt II.B1.2.CP-63 II.B1.2-Steel elements Steel 8(C-46) (inaccessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Concrete None None No Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE" and corrosion is Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from crevice corrosion AppendixJ" the IWE Additional plant-specific activities are examinations warranted if loss of material due to 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 concrete in contact with the embedded containment shell or liner. 2. The moisture barrier, at the unction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) 0 o CD C') CD 3 0-CD ..., I\) a a I CD z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B1.2 Mark I Concrete Containments Structure Item Link and/or Material Component II.B1.2.CP-117 II.B1.2-Steel elements:

Steel 8(C-46) downcomer pipes II.B1.2.C-23 II.B1.2-Steel elements:

Steel 9(C-23) drywell head; downcomers II.B1.2.C-49 II.B1.2-Steel elements:

Steel; 1 0(C-49) suppression stainless chamber (torus) steel liner (interior surface) Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation 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. If any of the above cond itions can not be satisfied, then a plant-specific aging management program for corrosion is necessary.

Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE" Treated water pitting, and crevice corrosion Air -indoor, Fretting or lockup Chapter XI.S1, "ASME Section XI, No uncontrolled due to mechanical Subsection IWE" wear Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general Subsection IWE," and Treated water (steel only), Chapter XI.S4, "10 CFR Part 50, pitting, and AppendixJ" crevice corrosion

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) N z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B2.1 Mark II Steel Containments Structure Item Link and/or Material Component II.B2.1.CP-46 II.B2.1-Steel elements Steel 1 (C-46) (accessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

II.B2.1.CP-114 Steel elements Steel (inaccessible areas): support skirt II.B2.1.CP-63 II.B2.1-Steel elements Steel 1 (C-46) (inaccessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, crevice AppendixJ" corrosion Concrete None None No Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE" and corrosion is Treated water pitting, and indicated from crevice Chapter XI.S4, "10 CFR Part 50, the IWE corrosion AppendixJ" examinations Additional plant-specific activities are warranted if loss of material due to 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) 0) o CD C') CD 3 0-CD ..., I\) a a III I\) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B2.1 Mark II Steel Containments Structure Item Link and/or Component II.B2.1.CP-117 II.B2.1-Steel elements:

1 (C-46) downcomer pipes II.B2.1.C-23 II.B2.1-Steel elements:

2(C-23) drywell head; downcomers Material Environment Steel Air -indoor, uncontrolled or Treated water Steel Air -indoor, uncontrolled Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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. 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.

Loss of material Chapter XI.S1, "ASME Section XI, No due to general, Subsection IWE" pitting, and crevice corrosion Fretting or Chapter XI.S1, "ASME Section XI, No lockup Subsection IWE" due to 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B2.1 Mark II Steel Containments Structure Item Link and/or Material Component II.B2.1.CP-107 II.B2.1-Suppression Steel; 3(C-44) pool shell stainless steel; dissimilar metal welds II.B2.1.C-45 II.B2.1-Suppression Steel; 4(C-45) pool shell; stainless unbraced steel; downcomers dissimilar metal welds II.B2.1.CP-142 II.B2.1-Unbraced Steel; 3(C-44) downcomers stainless steel; dissimilar metal welds Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation mechanical wear Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled or due to cyclic Subsection IWE," and Treated Water loading Chapter XI.S4, "10 CFR Part 50, (CLB fatigue AppendixJ" analysis does not exist) Air -indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA uncontrolled fatigue damage (TLAA) to be evaluated for the period of due to fatigue 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 ). Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled or due to cyclic Subsection IWE" Treated water loading (CLB fatigue analysis does not exist) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) (J1 o CD C') CD 3 0-CD ..., I\) a a III I\) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Material Component II.B2.2.CP-79 II.B2.2-Concrete Concrete; 2(C-41) (accessible steel areas): basemat; reinforcing steel II.B2.2.CP-S9 II.B2.2-Concrete Concrete 4(C-39) (accessible areas): containment; wall; base mat II.B2.2.CP-S4 II.B2.2-Concrete Concrete 6(C-31) (accessible areas): containment; wall; base mat II.B2.2.CP-80 II.B2.2-Concrete Concrete; 2(C-41) (inaccessible steel areas): basemat; reinforcing steel II.B2.2.CP-99 II.B2.2-Concrete Concrete 4(C-39) (inaccessible areas): containment; wall; base mat Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No uncontrolled or bond; and loss of Subsection IWL" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel Any Cracking Chapter XI.S2, "ASME Section XI, No environment due to expansion Subsection IWL" from reaction with aggregates Water -flowing Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL" permeability; loss of strength due to leaching of calcium hydroxide and carbonation Air -indoor, Cracking; loss of Chapter XI.S6, "Structures Monitoring" No uncontrolled or bond; and loss of Air -outdoor material (spalling, scaling) due to corrosion of embedded steel Any Cracking Further evaluation is required to Yes, if environment due to expansion determine if a plant-specific aging concrete is not from reaction with management program is needed to constructed as aggregates manage cracking and expansion due stated to reaction with aggregate of concrete in Inaccessible Areas. A plant-specific aging management program is not 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) (J) z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I (J) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Component II.B2.2.CP-110 II.B2.2-Concrete 6(C-31) (inaccessible areas): containment; wall; base mat II.B2.2.CP-105 II.B2.2-Concrete 1 (C-06) elements, all Aging Effect/ Material Environment Mechanism Concrete Water -flowing Increase in porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Concrete Soil Cracking and distortion due to increased Further Aging Management Program (AMP) Evaluation 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 function.

Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Chapter XI.S2, "ASME Section XI, Yes, if a de-Subsection IWL," or watering Chapter XI.S6, " Structures Monitoring" system is 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) -....J o CD C') CD 3 0-CD ..., I\) a a III I\) I -J z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Material Environment Component II.B2.2.CP-106 II.B2.2-Concrete:

Concrete Air -indoor, S(C-26) containment; uncontrolled or wall; base mat Air -outdoor II.B2.2.CP-S7 II.B2.2-Concrete:

Concrete Air -indoor, 3(C-3S) containment; uncontrolled or wall; base mat Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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.

Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures Monitoring" cracking; loss of material (spalling, scaling) due to aggressive chemical attack Reduction of Plant-specific aging management Yes, if strength and program temperature 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.

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) CD z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I 00 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Component II.B2.2.C-07 II.B2.2-Concrete:

7(C-07) foundation; su bfou ndation II.B2.2.C-11 II.B2.2-Prestressing 8(C-11) system: tendons Material Environment Concrete; Water -flowing porous concrete Steel Air -indoor, uncontrolled or Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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 strength and modulus of elasticity, and these reductions are applied to the design calculations.

Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation If a de-watering system is relied upon watering 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 Loss of prestress Loss of tendon prestress is a time-Yes, TLAA due to relaxation; limited aging analysis (TLAA) to be shrinkage; creep; evaluated for the period of extended elevated operation.

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

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 (J) CD o CD C') CD 3 0-CD ..., I\) a a III I\) I CD z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Component II.B2.2.C-10 II.B2.2-Prestressing 9(C-10) system: tendons; anchorage components II.B2.2.CP-46 II.B2.2-Steel elements 1 0(C-46) (accessible areas): suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor I(as applicable)

II.B2.2.CP-114 Steel elements (inaccessible areas): support skirt II.B2.2.CP-63 II.B2.2-Steel elements 1 0(C-46) (inaccessible areas): suppression chamber; drywell; drywell head; embedded shell; region Aging Effect/ Further Material Environment Aging Management Program (AMP) Mechanism Evaluation For periodic monitoring of prestress, see Chapter XI.S2. Steel Air -indoor, Loss of material Chapter XI.S2, "ASME Section XI, No uncontrolled or due to corrosion Subsection IWL" Air -outdoor Steel Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Treated water pitting, and Chapter XI.S4, "10 CFR Part 50, crevice corrosion AppendixJ" Steel Concrete None None No Steel Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE" and corrosion is Treated water pitting, and indicated from crevice corrosion Chapter XI.S4, "10 CFR Part 50, the IWE AppendixJ" examinations Additional plant-specific activities are warranted if loss of material due to corrosion is significant for inaccessible 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J 0 z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I ...... a 0 CD C') CD 3 0-CD ..., I\) a a II B2.2 Item CONTAINMENT STRUCTURES Mark II Concrete Containments Structure Aging Effect/ Link and/or Material Environment Component Mechanism shielded by diaphragm floor (as applicable)

Further Aging Management Program (AMP) Evaluation 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 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. 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 cond itions can not be satisfied, then a plant-specific aging management program for corrosion is necessary.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J --" o CD C') CD 3 0-CD ..., I\) a a III I\) I ...... z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B2.2 Mark II Concrete Containments Structure Item Link and/or Material Component II.B2.2.CP-117 II.B2.2-Steel elements:

Steel 1 0(C-46) downcomer pipes II.B2.2.C-23 II.B2.2-Steel elements:

Steel 11 (C-23) drywell head; downcomers II.B2.2.C-49 II.B2.2-Steel elements:

Steel; 12(C-49) suppression stainless chamber (torus) steel liner (interior surface) II.B2.2.CP-64 II.B2.2-Steel elements:

Steel; 13(C-47) vent header; stainless downcomers steel II.B2.2.C-48 II.B2.2-Steel elements:

Steel; 14(C-48) vent header; stainless downcomers steel Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE" Treated water pitting, and crevice corrosion Air -indoor, Fretting or lockup Chapter XI.S1, "ASME Section XI, No uncontrolled due to mechanical Subsection IWE" wear Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general Subsection IWE," and Treated water (steel only), Chapter XI.S4, "10 CFR Part 50, pitting, and AppendixJ" crevice corrosion Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled or due to cyclic Subsection IWE" Treated water loading (CLB fatigue analysis does not exist) Air -indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA uncontrolled or fatigue damage (TLAA) to be evaluated for the period 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).

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.1 Mark III Steel Containments Structure Item Link and/or Material Component 11.83.1.CP-72 11.83.1-Concrete Concrete 1 (C-2S) (accessible areas): basemat 11.83.1.CP-1S6 11.83.1-Concrete Concrete 3(C-30) (accessible areas): basemat 11.83.1.CP-66 11.83.1-Concrete Concrete S(C-S1) (accessible areas): basemat, concrete fill-in annulus 11.83.1.CP-74 11.83.1-Concrete Concrete; 6(C-43) (accessible steel areas): basemat; reinforcing steel 11.83.1.CP-71 11.83.1-Concrete Concrete 1 (C-2S) (inaccessible areas): basemat Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Ground Increase in Chapter XI.S2, "ASME Section XI, No water/soil porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack Water -flowing Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL" permeability; loss of strength due to leaching of calcium hydroxide and carbonation Any Cracking Chapter XI.S2, "ASME Section XI, No environment due to expansion Subsection IWL" from reaction with aggregates Air -indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No uncontrolled or bond; and loss of Subsection IWL" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel Ground Increase in Chapter XI.S2, "ASME Section XI, No water/soil porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" material (spalling, 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J (J1 o CD C') CD 3 0-CD ..., I\) a a III CJ.) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES 83.1 Mark III Steel Containments Structure Item Link and/or Material Environment Component 11.83.1.CP-53 11.83.1-Concrete Concrete Water -flowing 3(C-30) (inaccessible areas): basemat 11.83.1.CP-83 11.83.1-Concrete Concrete Any 5(C-51) (inaccessible environment areas): basemat, concrete fill-in annulus Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation scaling) due to aggressive chemical attack Increase in Further evaluation is required to Yes, if porosity and determine if a plant-specific aging leaching is permeability; loss management program is needed to observed in 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 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.

Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not from reaction with management program is needed to constructed as 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J (J) z c ;U m G) I ...... 00 a ;u CD :< I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.1 Mark III Steel Containments Structure Item Link and/or Component 11.83.1.CP-75 11.83.1-Concrete 6(C-43) (inaccessible areas): basemat; reinforcing steel 11.83.1.CP-69 11.83.1-Concrete:

2(C-36) basemat 11.83.1.CP-65 11.83.1-Concrete:

4(C-50) basemat, concrete fill-in annulus Material Environment Concrete; Air -indoor, steel uncontrolled or Air -outdoor Concrete Soil Concrete Air -indoor, uncontrolled or Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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.

Cracking; loss of Chapter XI.S2, "ASME Section XI, No bond; and loss of Subsection IWL," or material (spalling, Chapter XI.S6, " Structures scaling) Monitoring" due to corrosion of embedded steel Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-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.

Reduction of Plant-specific aging management Yes, if strength and program temperature modulus limits are due to elevated The implementation of exceeded temperature 10 CFR 50.55a and ASME Section 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J -....J o CD C') CD 3 0-CD ..., I\) a a III CJ.) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES 83.1 Mark III Steel Containments Structure Item Link and/or Material Environment Component 11.83.1.C-07 11.83.1-Concrete: Concrete; Water -flowing 7(C-07) foundation; porous subfoundation concrete Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation

(>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, 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 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.

Reduction of Chapter XI.S6, "Structures Yes, if a de-foundation Monitoring" watering strength and If a de-watering system is relied upon system is cracking for control of erosion of cement from relied upon to 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J CD z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I (J) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.1 Mark III Steel Containments Structure Item Link and/or Material Component 11.83.1.CP-43 11.83.1-Steel elements Steel 8(C-19) (accessible areas): drywell shell; drywell head 11.83.1.CP-113 11.83.1-Steel elements Steel 8(C-19) (inaccessible areas): drywell shell; drywell head; and drywell shell 11.83.1.C-24 11.83.1-Steel elements:

Stainless 9(C-24) suppression steel chamber shell (interior surface) 11.83.1.CP-158 11.83.1-Steel elements:

Steel 8(C-19) suppression chamber shell (interior surface) Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation due to differential porous concrete subfoundations, then control 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.

Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled due to general, Subsection IWE," and pitting, and Chapter XI.S4, "10 CFR Part 50, crevice corrosion AppendixJ" Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE," and corrosion is Concrete pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from crevice corrosion AppendixJ" the IWE examinations Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled due to stress Subsection IWE," and corrosion cracking Chapter XI.S4, "10 CFR Part 50, AppendixJ" Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or due to general, Subsection IWE" corrosion is Treated water pitting, and Plant-specific aging management significant crevice corrosion program is required if plant operating experience identified significant corrosion.

If protective coating is credited for preventing corrosion, the coating should be included in scope of license renewal and subject to aging management review.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 -....J CD o CD C') CD 3 0-CD ..., I\) a a z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Material Component 11.83.2.CP-84 11.83.2-Concrete Concrete 5(C-27) (accessible areas): dome; wall; base mat 11.83.2.CP-52 11.83.2-Concrete Concrete 3(C-29) (accessible areas): dome; wall; base mat 11.83.2.CP-60 11.83.2-Concrete Concrete 4(C-40) (accessible areas): dome; wall; base mat 11.83.2.CP-55 11.83.2-Concrete Concrete 6(C-32) (accessible areas): dome; wall; base mat 11.83.2.CP-88 11.83.2-Concrete Concrete; 7(C-42) (accessible steel areas): dome; wall; base mat; reinforcing steel Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Increase in Chapter XI.S2, "ASME Section XI, No uncontrolled or porosity and Subsection IWL," or Air -outdoor or permeability; Chapter XI.S6, " Structures Ground cracking; loss of Monitoring" water/soil material (spalling, scaling) due to aggressive chemical attack Air -outdoor or Loss of material Chapter XI.S2, "ASME Section XI, No Ground (spalling, scaling) Subsection IWL" water/soil and cracking due to freeze-thaw Any Cracking Chapter XI.S2, "ASME Section XI, No environment due to expansion Subsection IWL" from reaction with aggregates Water -flowing Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL" permeability; loss of strength due to leaching of calcium hydroxide and carbonation Air -indoor, Cracking; loss of Chapter XI.S2, "ASME Section XI, No uncontrolled or bond; and loss of Subsection IWL" Air -outdoor material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD 0 z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I 00 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Component 11.83.2.CP-73 11.83.2-Concrete 5(C-27) (inaccessible areas): dome; wall; base mat 11.83.2.CP-135 11.83.2-Concrete 3(C-29) (inaccessible areas): dome; wall; base mat Material Environment Concrete Air -indoor, uncontrolled or Air -outdoor or Ground water/soil Concrete Air -outdoor or Ground water/soil Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Increase in Chapter XI.S2, "ASME Section XI, No porosity and Subsection IWL," or permeability; Chapter XI.S6, " Structures cracking; loss of Monitoring" material (spalling, scaling) due to aggressive chemical attack Loss of material Further evaluation is required for Yes, for plants (spalling, scaling) plants that are located in moderate to located in and cracking severe weathering conditions moderate to 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 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 inaccessible areas . The weathering index for the 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD --" o CD C') CD 3 0-CD ..., I\) a a III CJ.) I CD z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Material Environment Component 11.83.2.CP-121 11.83.2-Concrete Concrete Any 4(C-40) (inaccessible environment areas): dome; wall; base mat 11.83.2.CP-122 11.83.2-Concrete Concrete Water -flowing 6(C-32) (inaccessible areas): dome; wall; base mat Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation continental US is shown in ASTM C33-90, Fig. 1. Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not from reaction with management program is needed to constructed as 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 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.

Increase in Further evaluation is required to Yes, if porosity and determine if a plant-specific aging leaching is permeability; loss management program is needed to observed in 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD N z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I ...... a 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Component 11.83.2.CP-89 11.83.2-Concrete 7(C-42) (inaccessible areas): dome; wall; base mat; reinforcing steel 11.83.2.CP-10S 11.83.2-Concrete 1 (C-06) elements, all 11.83.2.CP-108 11.83.2-Concrete:

2(C-33) dome; wall; basemat Material Environment Concrete; Air -indoor, steel uncontrolled or Air -outdoor Concrete Soil Concrete Air -indoor, uncontrolled or Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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.

Cracking; loss of Chapter XI.S2, "ASME Section XI, No bond; and loss of Subsection IWL," or material (spalling, Chapter XI.S6, " Structures scaling) Monitoring" due to corrosion of embedded steel Cracking and Chapter XI.S2, "ASME Section XI, Yes, if a de-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.

Reduction of Plant-specific aging management Yes, if strength and program temperature modulus The implementation of 10 CFR SO.SSa limits are due to elevated and ASME Section XI, Subsection exceeded temperature IWL would not be able to identify the (>1S0°F general; reduction of strength and modulus of >200°F local) elasticity due to elevated temperature.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD 0) o CD C') CD 3 0-CD ..., I\) a a III CJ.) I ...... z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Component 11.83.2.C-07 11.83.2-Concrete:

8(C-07) foundation; su bfou ndation Aging Effect/ Material Environment Mechanism Concrete; Water -flowing Reduction of porous foundation concrete strength and cracking due to differential settlement and erosion of porous concrete subfoundation Further Aging Management Program (AMP) Evaluation 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 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.

Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon watering for control of erosion of cement from system is porous concrete subfoundations, then relied upon to the licensee is to ensure proper control functioning of the de-watering system settlement through the period of extended operation.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I ...... I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES 83.2 Mark III Concrete Containments Structure Item Link and/or Material Environment Component 11.83.2.CP-35 11.83.2-Steel elements Steel Air -indoor, 9(C-09) (accessible uncontrolled areas): liner; liner anchors; integral attachments 11.83.2.CP-98 11.83.2-Steel elements Steel Air -indoor, 9(C-09) (inaccessible uncontrolled areas): liner; liner anchors; integral attachments Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Loss of material Chapter XI.S1, "ASME Section XI, No due to general, Subsection IWE," and pitting, and Chapter XI.S4, "10 CFR Part 50, crevice corrosion AppendixJ" Loss of material Chapter XI.S1, "ASME Section XI, Yes, if due to general, Subsection IWE" and corrosion is pitting, and Chapter XI.S4, "10 CFR Part 50, indicated from crevice corrosion AppendixJ" the IWE Additional plant-specific activities are examinations warranted if loss of material due to 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. 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD (J1 o CD C') CD 3 0-CD ..., I\) a a z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B3.2 Mark III Concrete Containments Structure Item Link and/or Material Component II.B3.2.C-24 II.B3.2-Steel Stainless 1 0(C-24) elements:

steel suppression chamber shell (interior surface) Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation 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.

Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled due to stress Subsection IWE," and corrosion cracking Chapter XI.S4, "10 CFR Part 50, AppendixJ"

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD -....J z c ;U m G) I ...... 00 a ;u CD :< I\) III .j:>. I I\) 0 CD C') CD 3 0-CD ..., I\) a a II CONTAINMENT STRUCTURES B4 Common Components Structure Item Link and/or Component II.B4.CP-40 II.B4-7(C-Moisture 18) barriers (caulking, flashing, and other sealants)

II.B4.CP-36 II.B4-1 (C-Penetration

12) sleeves II.B4.CP-38 II.B4-2(C-Penetration

15) sleeves; penetration bellows II.B4.CP-37 II.B4-3(C-penetration

14) sleeves; penetration bellows II.B4.C-13 II.B4-4(C-Penetration

13) sleeves; penetration bellows II.B4.C-16 II.B4-6(C-Personnel

16) airlock, equipment hatch, CRD hatch Material Elastomers, rubber and other similar materials Steel; dissimilar metal welds Stainless steel; dissimilar metal welds Steel; stainless steel; dissimilar metal welds Steel; stainless steel; dissimilar metal welds Steel Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of sealing Chapter XI.S1, "ASME Section XI, No uncontrolled due to wear, Subsection IWE" damage, erosion, tear, surface cracks, or other defects Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Air -outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice AppendixJ" corrosion Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, Yes, detection uncontrolled or due to stress Subsection IWE," and of aging Air -outdoor corrosion Chapter XI.S4, "10 CFR Part 50, effects is to cracking AppendixJ" be evaluated Air -indoor, Cracking Chapter XI.S1, "ASME Section XI, No uncontrolled or due to cyclic Subsection IWE," and Air -outdoor loading Chapter XI.S4, "10 CFR Part 50, (CLB fatigue AppendixJ" analysis does not exist) Air -indoor, Cumulative Fatigue is a time-limited aging analysis Yes, TLAA uncontrolled or fatigue damage (TLAA) to be evaluated for the period of Air -outdoor due to fatigue 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 ). Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE," and Air -outdoor pitting, and Chapter XI.S4, "10 CFR Part 50, crevice AppendixJ" corrosion 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD CD o CD C') CD 3 0-CD ..., I\) a a z c ;u m G) I ...... 00 a ;U CD :< I\) II CONTAINMENT STRUCTURES B4 Common Components Structure Item Link and/or Material Component II.B4.CP-39 II.B4-5(C-Personnel Steel 17) airlock, equipment hatch, CRD hatch: locks, hinges, and closure mechanisms II.B4.CP-150 Pressure-Any retaining bolting II.B4.CP-148 Pressure-Steel retaining bolting II.B4.CP-41 II.B4-7(C-Seals and Elastomers, 18) gaskets rubber and other similar materials II.B4.CP-152 Service Level Coatings I coatings Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of leak Chapter XI.S1, "ASME Section XI, No uncontrolled or tightness Subsection IWE," and Air -outdoor due to Chapter XI.S4, "10 CFR Part 50, mechanical wear AppendixJ" of locks, hinges and closure mechanisms Any Loss of preload Chapter XI.S1, "ASME Section XI, No environment due to self-Subsection IWE," and loosening Chapter XI.S4, "10 CFR Part 50, AppendixJ" Air -indoor, Loss of material Chapter XI.S1, "ASME Section XI, No uncontrolled or due to general, Subsection IWE" Air -outdoor pitting, and crevice corrosion Air -indoor, Loss of sealing Chapter XI.S4, "10 CFR Part 50, No uncontrolled or due to wear, AppendixJ" Air -outdoor damage, erosion, tear, surface cracks, or other defects Air -indoor, Loss of coating Chapter XI.S8, "Protective Coating No uncontrolled integrity Monitoring and Maintenance" due to blistering, cracking, flaking, peeling, or physical damage 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD 0) z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism IILA1.TP-IILA1-2(T-Concrete Concrete Any environment Cracking 25 03) (accessible due to expansion areas): all from reaction with aggregates IILA1.TP-liLA 1-4(T-Concrete Concrete Ground Cracking; loss of 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 23 01 ) (accessible (spalling, scaling) areas): exterior and cracking above-and due to freeze-thaw below-grade; foundation IILA1.TP-liLA 1-7(T-Concrete Concrete Water -flowing Increase in 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 26 04) (accessible uncontrolled or bond; and loss of areas): interior Air -outdoor material (spalling, and above-scaling) grade exterior due to corrosion of embedded steel IILA1.TP-IILA1-2(T-Concrete Concrete Any environment Cracking 204 03) (inaccessible due to expansion areas): all from reaction with aggregates Further Aging Management Program (AMP) Evaluation Chapter XLS6, "Structures Monitoring" No Chapter XLS6, "Structures Monitoring" No Chapter XLS6, "Structures Monitoring" No Chapter XLS6, "Structures Monitoring" No Chapter XLS6, "Structures Monitoring" No Further evaluation is required to Yes, if determine if a plant-specific aging concrete is not management program is needed to constructed as manage cracking and expansion due to stated 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD .j::>. o CD C') CD 3 0-CD ..., I\) a a >> ...... I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism IILA1.TP-liLA 1-4(T-Concrete Concrete Ground Cracking; loss of 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 29 07) (inaccessible water/soil porosity and areas): below-permeability; grade exterior; cracking; loss of foundation material (spalling, scaling) due to aggressive chemical attack IILA1.TP-liLA 1-7(T-Concrete Concrete Water -flowing Increase in 67 02) (inaccessible porosity and areas): exterior permeability; loss Further Aging Management Program (AMP) Evaluation 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 in-place concrete can perform its intended function.

Chapter XLS6, "Structures Monitoring" No Chapter XLS6, "Structures Monitoring" No Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD (J1 z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism above-and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A1.TP-III.A 1-6(T-Concrete Concrete Air -outdoor Loss of material 108 01) (inaccessible (spalling, scaling) areas): and cracking foundation due to freeze-thaw Further Aging Management Program (AMP) Evaluation manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete in impact 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.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering index moderate to >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-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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD (J) o CD C') CD 3 0-CD ..., I\) a a >> ...... I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A1.TP-III.A1-1 (T-Concrete:

all Concrete Air -indoor, Reduction of 114 10) uncontrolled strength and modulus due to elevated temperature

(>150°F general; >200°F local) III.A1.TP-III.A1-3(T-Concrete:

all Concrete Soil Cracking and 30 08) distortion due to increased Further Aging Management Program (AMP) Evaluation 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. Plant-specific aging management Yes, if program temperature limits are Subsection CC-3400 of ASME exceeded Section III, Division 2, and Appendix A of ACI 349 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, 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 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.

Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon for watering control of settlement, then the licensee system is 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD -....J z c ;U m G) I ...... 00 a ;u CD :< I\) >> ...... I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism stress levels from settlement III.A1.TP-III.A1-8(T-Concrete: Concrete; Water -flowing Reduction of 31 09) foundation; porous under foundation foundation strength subfoundation concrete and cracking due to differential settlement and erosion of porous concrete subfoundation III.A1.TP-III.A1-Concrete:

Concrete Air -indoor, Increase in 28 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 III.A1.TP-High-strength Low-alloy Air -indoor, Cracking 300 structural steel, actual uncontrolled or due to stress bolting measured Air -outdoor corrosion cracking yield strength ;::: 150 ksi (1,034 MPa) III.A1.T-12 III.A1-Masonry walls: Concrete Air -indoor, Cracking 11(T-12) all block uncontrolled or due to restraint Air -outdoor shrinkage, creep, and aggressive environment Further Aging Management Program (AMP) Evaluation is to ensure proper functioning of the de-relied upon to watering system through the period of control extended operation.

settlement Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon for watering control of settlement, then the licensee system is is to ensure proper functioning of the de-relied upon to watering system through the period of control extended operation.

settlement Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts. Chapter XI.S5, "Masonry Walls" No 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 0 CD CD o CD C') CD 3 0-CD ..., I\) a a >> ...... I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A1 Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Room/Bldg.)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A1.TP-III.A1-Steel Steel Air -indoor, Loss of material 302 12(T-11) components:

all uncontrolled or due to corrosion structural steel Air -outdoor III.A1.TP-Structural Any Any environment Loss of preload 261 bolting due to self-loosening III.A1.TP-Structural Steel Air -indoor, Loss of material 248 bolting uncontrolled due to general, pitting and crevice corrosion III.A1.TP-Structural Steel; Air -outdoor Loss of material 274 bolting galvanized due to general, steel pitting, and crevice corrosion Further Aging Management Program (AMP) Evaluation Chapter XI.S6, "Structures Monitoring" No If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 0 z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation III.A2.TP-25 III.A2-2(T-Concrete Concrete Any Cracking Chapter XI.S6, "Structures Monitoring" No 03) (accessible environment due to expansion areas): all from reaction with aggregates III.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) areas): exterior and cracking 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, and above-scaling) grade exterior due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 --" o CD C') CD 3 0-CD ..., I\) a a >> I\) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A2.TP-204 III.A2-2(T-Concrete Concrete Any Cracking 03) (inaccessible environment due to expansion areas): all from reaction with aggregates III.A2.TP-212 III.A2-4(T-Concrete Concrete Ground Cracking; loss of 05) (inaccessible water/soil bond; and loss of areas): below-material (spalling, grade exterior; scaling) foundation due to corrosion of embedded steel III.A2.TP-29 III.A2-5(T-Concrete Concrete Ground Increase in 07) (inaccessible water/soil porosity and areas): below-permeability; grade exterior; cracking; loss of foundation material (spalling, scaling) Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging concrete is not management program is needed to constructed as 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 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.

Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 N z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism due to aggressive chemical attack III.A2.TP-67 III.A2-7(T-Concrete Concrete Water -flowing Increase in 02) (inaccessible porosity and areas): exterior permeability; loss above-and of strength below-grade; due to leaching of foundation calcium hydroxide and carbonation III.A2 .TP-1 08 III.A2-6(T-Concrete Concrete Air -outdoor Loss of material 01) (inaccessible (spalling, scaling) areas): and cracking foundation due to freeze-thaw Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering moderate to index >100 day-inch/yr) (NUREG-severe 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 0) o CD C') CD 3 0-CD ..., I\) a a >> I\) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A2.TP-114 III.A2-1 (T-Concrete:

all Concrete Air -indoor, Reduction of 10) uncontrolled strength and modulus due to elevated temperature

(>150°F general; >200°F local) Further Aging Management Program (AMP) Evaluation 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. Plant-specific aging management Yes, if program temperature limits are Subsection CC-3400 of ASME exceeded Section III, Division 2, and Appendix A of ACI 349 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, 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 tests and/or calculations are provided 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) >> I\) I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism 111.A2.TP-30 III.A2-3(T-Concrete:

all Concrete Soil Cracking and 08) distortion due to increased stress levels from settlement III.A2.TP-31 III.A2-8(T-Concrete:

Concrete; Water -flowing Reduction of 09) foundation; porous under foundation su bfou ndation concrete foundation strength and cracking due to differential settlement and erosion of porous concrete subfoundation III.A2.TP-28 III.A2-Concrete:

Concrete Air -indoor, Increase in 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 111.A2. TP-300 H ig h-stre ngth Low-alloy Air -indoor, Cracking structural steel, actual uncontrolled or due to stress bolting measured Air -outdoor corrosion cracking yield strength ;:: 150 ksi Further Aging Management Program (AMP) Evaluation to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon watering for control of settlement, then the system is licensee is to ensure proper functioning relied upon to of the de-watering system through the control period of extended operation.

settlement Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon watering for control of settlement, then the system is licensee is to ensure proper functioning relied upon to of the de-watering system through the control period of extended operation.

settlement Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 (J1 o CD C') CD 3 0-CD ..., I\) a a >> I\) I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism (1,034 MPa) III.A2.T-12 III.A2-Masonry walls: Concrete Air -indoor, Cracking 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 12(T-11) components:

uncontrolled or due to corrosion all structural Air -outdoor steel III.A2.TP-261 Structural Any Any Loss of preload bolting environment due to self-loosening III.A2.TP-248 Structural Steel Air -indoor, Loss of material bolting uncontrolled due to general, pitting and crevice corrosion III.A2.TP-274 Structural Steel; Air -outdoor Loss of material bolting galvanized due to general, steel pitting, and crevice corrosion Further Aging Management Program (AMP) Evaluation for these bolts. Chapter XI.SS, "Masonry Walls" No Chapter XI.S6, "Structures Monitoring" No If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 -....J z c ;U m G) I ...... 00 a ;u CD :< I\) >> CJ.) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 III.A3.TP-23 III.A3-6(T-Concrete Concrete Air -outdoor Loss of material Chapter XI.S6, "Structures Monitoring" No 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 04) (accessible uncontrolled or bond; and loss of areas): interior Air -outdoor material (spalling, and above-scaling) grade exterior due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 CD o CD C') CD 3 0-CD ..., I\) a a >> CJ.) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 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.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, grade exterior; scaling) foundation due to corrosion of embedded steel III.A3.TP-29 III.A3-5(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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0 CD z c ;U m G) I ...... 00 a ;u CD :< I\) >> CJ.) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 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.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 aging management program is conditions needed. A plant-specific aging management program is not required if documented evidence confirms that the existing concrete had air 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" 0 o CD C') CD 3 0-CD ..., I\) a a >> CJ.) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 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.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 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 supported by concrete at temperatures exceeding 150°F, an evaluation of the 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --"

--" z c ;U m G) I ...... 00 a ;u CD :< I\) >> CJ.) I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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-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.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 III.A3.TP-28 III.A3-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) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" N o CD C') CD 3 0-CD ..., I\) a a >> CJ.) I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 11(T-12) all block uncontrolled or due to restraint 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 components:

water/soil due to corrosion piles III.A3.TP-261 Structural Any Any Loss of preload Chapter XI.S6, "Structures Monitoring" No bolting environment due to self-loosening 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" 0) z c ;U m G) I ...... 00 a ;u CD :< I\) >> CJ.) I 00 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS 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)

Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" (J1 z c ;U m G) I ...... 00 a ;u CD :< I\) >> .j:>. I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A4.TP-25 III.A4-2(T-Concrete Concrete Any Cracking 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 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 III.A4.TP-204 III.A4-2(T-Concrete Concrete Any Cracking 03) (inaccessible environment due to areas): all expansion from reaction with aggregates Further Aging Management Program (AMP) Evaluation Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Further evaluation is required to Yes, if determine if a plant-specific aging concrete is not management program is needed to constructed as 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 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.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" (J) o CD C') CD 3 0-CD ..., I\) a a >> .j:>. I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism 111.A4. TP-30S Concrete Concrete Water -flowing Increase in (inaccessible porosity and areas): permeability; exterior loss of strength above-and due to leaching below-grade; of calcium foundation hydroxide and carbonation III.A4.TP-114 III.A4-1 (T-Concrete:

all Concrete Air -indoor, Reduction of 10) uncontrolled strength and modulus due to elevated temperature

(>1S0°F general; >200°F local) Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Plant-specific aging management Yes, if program temperature limits are Subsection CC-3400 of ASME exceeded Section III, Division 2, and Appendix A of ACI 349 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, 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" -....J z c ;U m G) I ...... 00 a ;u CD :< I\) >> .j:>. I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism 111.A4. TP-304 Concrete:

all Concrete Soil Cracking and distortion due to increased stress levels from settlement III.A4.TP-28 III.A4-4(T-Concrete:

Concrete Air -indoor, Increase in 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 structural steel, actual uncontrolled or due to stress bolting measured Air -outdoor corrosion yield cracking strength ;::: 150 ksi (1,034 MPa) Further Aging Management Program (AMP) Evaluation 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.

Chapter XI.S6, "Structures Monitoring" Yes, if a de-If a de-watering system is relied upon watering for control of settlement, then the system is licensee is to ensure proper functioning relied upon to of the de-watering system through the control period of extended operation.

settlement Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts .

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" --" CD o CD C') CD 3 0-CD ..., I\) a a >> .j:>. I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) Structure Aging Effect/ Item Link and/or Material Environment Component Mechanism III.A4.TP-301 Service Level Coatings Air -indoor, Loss of coating I coatings uncontrolled integrity due to blistering, cracking, flaking, peeling, physical damage 111.A4.TP-35 III.A4-6(T-Sliding Lubrite; Air -indoor, Loss of 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 11 ) components:

uncontrolled or due to corrosion all structural Air -outdoor steel III.A4.TP-261 Structural Any Any Loss of preload bolting environment due to self-loosening III.A4.TP-248 Structural Steel Air -indoor, Loss of material bolting uncontrolled due to general, pitting and crevice corrosion III.A4.TP-274 Structural Steel; Air -outdoor Loss of material bolting galvanized due to general, steel pitting, and crevice corrosion Further Aging Management Program (AMP) Evaluation Chapter XI.S8, "Protective Coating No Monitoring and Maintenance" Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No Chapter XI.S6, "Structures Monitoring" No 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N 0 z c ;U m G) I ...... 00 a ;u CD :< I\) >> 0'1 I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component III.A5.TP-25 III.A5-2(T-Concrete Concrete Any 03) (accessible environment areas): all III.A5.TP-27 III.A5-4(T-Concrete Concrete Ground

05) (accessible water/soil areas): below-grade exterior; foundation III.A5.TP-23 III.A5-6(T-Concrete Concrete Air -outdoor 01) (accessible areas): exterior above-and below-grade; foundation III.A5.TP-24 III.A5-7(T-Concrete Concrete Water -flowing 02) (accessible areas): exterior above-and below-grade; foundation III.A5.TP-26 III.A5-9(T-Concrete Concrete Air -indoor, 04) (accessible uncontrolled or areas): interior Air -outdoor and above-grade exterior Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking Chapter XI.S6, "Structures Monitoring" No due to expansion from reaction with aggregates Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Loss of material Chapter XI.S6, "Structures Monitoring" No (spalling, scaling) and cracking due to freeze-thaw Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N --" o CD C') CD 3 0-CD ..., I\) a a >> 0"1 I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component III.A5.TP-204 III.A5-2(T-Concrete Concrete Any 03) (inaccessible environment areas): all III.A5.TP-212 III.A5-4(T-Concrete Concrete Ground

05) (inaccessible water/soil areas): below-grade exterior; foundation III.A5.TP-29 III.A5-5(T-Concrete Concrete Ground

07) (inaccessible water/soil areas): below-grade exterior; foundation Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not 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 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.

Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N N z c ;U m G) I ...... 00 a ;u CD :< I\) >> 0"1 I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component III.A5.TP-67 III.A5-7(T-Concrete Concrete Water -flowing 02) (inaccessible areas): exterior above-and below-grade; foundation III.A5 .TP-1 08 III.A5-6(T-Concrete Concrete Air -outdoor 01 ) (inaccessible areas): foundation Aging Effect/ Mechanism due to aggressive chemical attack Increase in porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Loss of material (spalling, scaling) and cracking due to freeze-thaw Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering moderate to index >100 day-inch/yr) (NUREG-severe 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N 0) o CD C') CD 3 0-CD ..., I\) a a >> 0"1 I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS AS Group S Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component III.AS.TP-114 III.AS-1 (T-Concrete:

all Concrete Air -indoor, 10) uncontrolled Aging Effect/ Mechanism Reduction of strength and modulus due to elevated temperature

(>1S0°F general; >200°F local) Further Aging Management Program (AMP) Evaluation 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. Plant-specific aging management Yes, if program temperature limits are Subsection CC-3400 of ASME exceeded Section III, Division 2, and Appendix A of ACI 349 specifies the concrete 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 supported by concrete at temperatures exceeding 1S0°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 tests and/or calculations are provided 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) >> 0"1 I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS AS Group 5 Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component 111.A5.TP-30 III.A5-3(T-Concrete:

all Concrete Soil 08) III.A5.TP-31 III.A5-8(T-Concrete:

Concrete; Water -flowing 09) foundation; porous under subfoundation concrete foundation III.A5.TP-28 III.A5-Concrete:

Concrete Air -indoor, 10(T-06) interior; above-uncontrolled or grade exterior Air -outdoor 111.A5. TP-300 High-strength Low-alloy Air -indoor, structural steel, actual uncontrolled or bolting measured Air -outdoor yield strength ;::: 150 ksi Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

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 from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control Iperiod of extended operation.

settlement Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation If a de-watering system is relied upon watering 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 subfoundation Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack Cracking Chapter XI.S6, "Structures Monitoring" No due to stress corrosion cracking Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC . SCC potential need not be evaluated 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N (J1 o CD C') CD 3 0-CD ..., I\) a a >> 0"1 I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS AS Group S Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component (1,034 MPa) III.AS.T-12 III.AS-Masonry walls: Concrete Air -indoor, 11(T-12) all block uncontrolled or Air -outdoor 111.AS.TP-34 Masonry walls: Concrete Air -outdoor all block III.AS. TP-302 III.AS-Steel Steel Air -indoor, 12(T-11) components:

uncontrolled or all structural Air -outdoor steel III.AS.T-14 III.AS-Steel Stainless Treated water 13(T-14) components:

steel or Treated fuel pool liner borated water III.AS.TP-261 Structural Any Any bolting environment Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation for these bolts. Cracking Chapter XI.SS, "Masonry Walls" No due to restraint shrinkage, creep, and aggressive environment Loss of material Chapter XI.SS, "Masonry Walls" No (spalling, scaling) and cracking due to freeze-thaw Loss of material Chapter XI.S6, "Structures Monitoring" No due to corrosion If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

Cracking Chapter XI.M2, "Water Chemistry," and No, unless due to stress monitoring of the spent fuel pool water leakages have 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 crevice corrosion accounted for from the leak chase channels Loss of preload Chapter XI.S6, "Structures Monitoring" No due to self-loosening 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N (J) z c ;U m G) I ...... 00 a ;u CD :< I\) >> 0'1 I 00 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS AS Group S Structures (Fuel Storage Facility, Refueling Canal) Structure Item Link and/or Material Environment Component III.AS.TP-248 Structural Steel Air -indoor, bolting uncontrolled III.AS.TP-274 Structural Steel; Air -outdoor bolting galvanized steel Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting and crevice corrosion Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting, and crevice corrosion 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N CD z c ;U m G) I ...... 00 a ;u CD :< I\) >> (J) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Component 111.A6.TP-38 III.A6-1 (T-Concrete Concrete 18) (accessible areas): all 111.A6.TP-36 III.A6-5(T-Concrete Concrete 15) (accessible areas): exterior above-and below-grade; foundation III.A6.TP-37 III.A6-6(T-Concrete Concrete 16) (accessible areas): exterior above-and below-grade; foundation; interior slab III.A6 .TP-1 04 III.A6-1 (T-Concrete Concrete 18) (inaccessible areas): all III.A6.TP-220 III.A6-2(T-Concrete Concrete

17) (inaccessible areas): all Environment Air -indoor, uncontrolled or Air -outdoor or Ground water/soil Air -outdoor Water-flowing Air -indoor, uncontrolled or Air -outdoor or Ground water/soil Any environment Aging Effect! Aging Management Program (AMP) Further Mechanism Evaluation Cracking; loss of Chapter XI.S7, "Regulatory Guide No bond; and loss of 1.127, Inspection of Water-Control material (spalling, Structures Associated with Nuclear scaling) Power Plants" or the FERC/US Army due to corrosion Corp of Engineers dam inspections of embedded and maintenance programs.

steel Loss of material Chapter XI.S7, "Regulatory Guide No (spalling, scaling) 1.127, Inspection of Water-Control and cracking Structures Associated with Nuclear due to freeze-Power Plants" or the FERC/US Army thaw Corp of Engineers dam inspections and maintenance programs.

Increase in Chapter XI.S7, "Regulatory Guide No porosity and 1.127, Inspection of Water-Control permeability; loss Structures Associated with Nuclear of strength Power Plants" or the FERC/US Army due to leaching of Corp of Engineers dam inspections calcium hydroxide and maintenance programs.

and carbonation Cracking; loss of Chapter XI.S6, "Structures No bond; and loss of Monitoring" material (spalling, scaling) due to corrosion of embedded steel Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" N CD o CD C') CD 3 0-CD ..., I\) a a >> (J) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Environment Component III.A6.TP-107 III.A6-3(T-Concrete Concrete Ground 19) (inaccessible water/soil areas): all III.A6.TP-110 III.A6-5(T-Concrete Concrete Air -outdoor 15) (inaccessible areas): exterior above-and below-grade; foundation; interior slab Aging Effect! Aging Management Program (AMP) Further 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 concrete can perform its intended function.

Increase in Chapter XI.S6, "Structures No porosity and Monitoring" permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack Loss of material Further evaluation is required for Yes, for plants (spalling, scaling) plants that are located in moderate to located in and cracking severe weathering conditions moderate to 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) 0 z c ;U m G) I ...... 00 a ;u CD :< I\) >> (J) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Component III.A6 .TP-1 09 III.A6-6(T-Concrete Concrete 16) (inaccessible areas): exterior above-and below-grade; foundation; interior slab Environment Aging Effect! Mechanism Water-Increase in flowing porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Aging Management Program (AMP) Further Evaluation 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 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. Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of areas that calcium hydroxide and carbonation of impact 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 leaching and carbonation, or (2) Evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) --" o CD C') CD 3 0-CD ..., I\) a a >> (J) I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Environment Component 111.A6.TP-30 III.A6-4(T-Concrete:

all Concrete Soil 08) III.A6.T-20 III.A6-7(T-Concrete:

Concrete Water-20) exterior above-flowing and below-grade; foundation; interior slab III.A6.TP-31 III.A6-8(T-Concrete: Concrete; Water-09) foundation; porous flowing under subfoundation concrete foundation III.A6.T-22 III.A6-9(T-Earthen water-Various Water-22) control flowing or structures:

dams; standing embankments; reservoirs; channels; canals and ponds Aging Effect! Aging Management Program (AMP) Further Mechanism Evaluation the intended function of the concrete structure.

Cracking and Chapter XI.S6, "Structures Yes, if a de-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.

Loss of material Chapter XI.S7, "Regulatory Guide No due to abrasion; 1.127, Inspection of Water-Control cavitation Structures Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

Reduction of Chapter XI.S6, "Structures Yes, if a de-foundation Monitoring" watering 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.

su bfou ndation Loss of material; Chapter XI.S7, "Regulatory Guide No loss of form 1.127, Inspection of Water-Control due to erosion, Structures Associated with Nuclear settlement, Power Plants" or the FERC/US Army sedimentation, Corp of Engineers dam inspections frost action, and maintenance programs.

waves, currents, 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) N z c ;U m G) I ...... 00 a ;u CD :< I\) >> (J) I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Component III.A6.TP-223 Group 6: Wood Wooden Piles; sheeting III.A6.T-12 III.A6-Masonry walls: Concrete 10(T-12) all block III.A6.TP-7 III.A6-Seals; gasket; Elastomers 12(TP-7) moisture barriers (such as (caulking, EPDM flashing, and rubber) other sealants)

III.A6.TP-261 Structural bolting Any Environment Aging Effect! Aging Management Program (AMP) Further Mechanism Evaluation surface runoff, seepage Air -outdoor Loss of material; Chapter XI.S7, "Regulatory Guide No or Water-change in material 1.127, Inspection of Water-Control 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 decay Air -indoor, Cracking Chapter XI.SS, "Masonry Walls" No uncontrolled or due to restraint Air -outdoor shrinkage, creep, and aggressive environment Various Loss of sealing Chapter XI.S6, "Structures No due to Monitoring" deterioration of seals, gaskets, and moisture barriers (caulking, flashing, and other sealants)

Any Loss of preload Chapter XI.S6, "Structures No environment due to self-Monitoring" loosening 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) 0) o CD C') CD 3 0-CD ..., I\) a a >> (J) I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A6 Group 6 Structures (Water-Control Structures)

Item Link Structure and/or Material Component III.A6.TP-248 Structural bolting Steel III.A6.TP-221 Structural bolting Steel Environment Aging Effect! Aging Management Program (AMP) Further Mechanism Evaluation Air -indoor, Loss of material Chapter XI.S6, "Structures No uncontrolled due to general, Monitoring" pitting and crevice corrosion 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.

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) (J1 z c ;U m G) I ...... 00 a ;u CD :< I\) >> -J I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A7.TP-25 III.A7-1 (T-Concrete Concrete Any 03) (accessible environment areas): all III.A7.TP-27 III.A7-3(T-Concrete Concrete Ground 05) (accessible water/soil areas): below-grade exterior; foundation III.A7.TP-23 III.A7-5(T-Concrete Concrete Air -outdoor 01) (accessible areas): exterior above-and below-grade; foundation III.A7.TP-24 III.A7-6(T-Concrete Concrete Water -flowing 02) (accessible areas): exterior above-and below-grade; foundation III.A7.TP-26 III.A7-8(T-Concrete Concrete Air -indoor, 04) (accessible uncontrolled or areas): interior Air -outdoor and above-grade exterior Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation Cracking Chapter XI.S6, "Structures Monitoring" No due to expansion from reaction with aggregates Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Loss of material Chapter XI.S6, "Structures Monitoring" No (spalling, scaling) and cracking due to freeze-thaw Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) (J) o CD C') CD 3 0-CD ..., I\) a a >> -J I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component liLA 7 .TP-204 IILA7-1 (T-Concrete Concrete Any 03) (inaccessible environment areas): all liLA 7 .TP-212 IILA7-3(T-Concrete Concrete Ground 05) (inaccessible water/soil areas): below-grade exterior; foundation IILA7.TP-29 IILA7-4(T-Concrete Concrete Ground 07) (inaccessible water/soil areas): below-grade exterior; foundation Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not 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 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.

Cracking; loss of Chapter XLS6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Increase in Chapter XLS6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) -....J z c ;U m G) I ...... 00 a ;u CD :< I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A7.TP-67 III.A7-6(T-Concrete Concrete Water -flowing 02) (inaccessible areas): exterior above-and below-grade; foundation III.A7.TP-108 III.A7-5(T-Concrete Concrete Air -outdoor 01) (inaccessible areas): foundation Aging Effect! Mechanism due to aggressive chemical attack Increase in porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Loss of material (spalling, scaling) and cracking due to freeze-thaw Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering moderate to index >100 day-inch/yr) (NUREG-severe 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) CD o CD C') CD 3 0-CD ..., I\) a a >> -J I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A7.TP-30 III.A7-2(T-Concrete:

all Concrete Soil 08) III.A7.TP-31 III.A7-7(T-Concrete: Concrete; Water -flowing 09) foundation; porous under subfoundation concrete foundation III.A7.TP-28 III.A7-9(T-Concrete:

Concrete Air -indoor, 06) interior; above-uncontrolled or grade exterior Air -outdoor Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation 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. 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 from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation.

settlement Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation If a de-watering system is relied upon watering 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 subfoundation Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" 0) CD z c ;U m G) I ...... 00 a ;u CD :< I\) >> -J I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component liLA 7 .TP-300 High-strength Low-alloy Air -indoor, structural steel, actual uncontrolled or bolting measured Air -outdoor yield strength ;::: 150 ksi (1,034 MPa) liLA 7 .TP-302 IILA7-Steel Steel Air -indoor, 10(T-11) components:

uncontrolled or all structural Air -outdoor steel IILA7.T-23 IILA7-Steel Stainless Water-11 (T-23) components:

steel standing tank liner IILA7.TP-261 Structural Any Any bolting environment liLA 7 .TP-248 Structural Steel Air -indoor, bolting uncontrolled Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation due to aggressive chemical attack Cracking Chapter XLS6, "Structures Monitoring" No due to stress corrosion cracking Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts. Loss of material Chapter XLS6, "Structures Monitoring" No due to corrosion If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

Cracking A plant-specific aging management Yes, plant-due to stress program is to be evaluated.

specific corrosion cracking; Loss of material due to pitting and crevice corrosion Loss of preload Chapter XLS6, "Structures Monitoring" No due to self-loosening Loss of material Chapter XLS6, "Structures Monitoring" No due to general, pitting and crevice corrosion 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. 0 o CD C') CD 3 0-CD ..., I\) a a >> -J I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A7 Group 7 Structures (Concrete Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A 7 .TP-27 4 Structural Steel; Air -outdoor bolting galvanized steel Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting, and crevice corrosion 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. N z c ;U m G) I ...... 00 a ;u CD :< I\) >> 00 I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A8 Group 8 Structures (Steel Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A8.TP-25 III.A8-1 (T-Concrete Concrete Any 03) (accessible environment areas): all III.A8.TP-27 III.A8-3(T-Concrete Concrete Ground 05) (accessible water/soil areas): below-grade exterior; foundation III.A8.TP-23 III.A8-5(T-Concrete Concrete Air -outdoor 01) (accessible areas): exterior above-and below-grade; foundation III.A8.TP-24 III.A8-6(T-Concrete Concrete Water -flowing 02) (accessible areas): exterior above-and below-grade; foundation III.A8.TP-204 III.A8-1 (T-Concrete Concrete Any 03) (inaccessible environment areas): all Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation Cracking Chapter XI.S6, "Structures Monitoring" No due to expansion from reaction with aggregates Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Loss of material Chapter XI.S6, "Structures Monitoring" No (spalling, scaling) and cracking due to freeze-thaw Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not 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-0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. 0) o CD C') CD 3 0-CD ..., I\) a a >> 00 I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A8 Group 8 Structures (Steel Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A8.TP-212 III.A8-3(T-Concrete Concrete Ground 05) (inaccessible water/soil areas): below-grade exterior; foundation III.A8.TP-29 III.A8-4(T-Concrete Concrete Ground 07) (inaccessible water/soil areas): below-grade exterior; foundation III.A8.TP-67 III.A8-6(T-Concrete Concrete Water -flowing 02) (inaccessible areas): exterior above-and below-grade; foundation Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation 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.

Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) due to aggressive chemical attack Increase in Further evaluation is required to Yes, if porosity and determine if a plant-specific aging leaching is permeability; loss management program is needed to observed in of strength manage increase in porosity, and accessible due to leaching of permeability due to leaching of calcium areas that calcium hydroxide hydroxide and carbonation of concrete impact 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) >> 00 I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A8 Group 8 Structures (Steel Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A8 .TP-1 08 III.A8-5(T-Concrete Concrete Air -outdoor 01) (inaccessible areas): foundation Aging Effect! Mechanism and carbonation Loss of material (spalling, scaling) and cracking due to freeze-thaw Further Aging Management Program (AMP) Evaluation 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 the intended function of the concrete structure.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering moderate to index >100 day-inch/yr) (NUREG-severe 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 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 required to manage loss of material (spalling, scaling) and cracking due to freeze-thaw of concrete in inaccessible areas.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. (J1 o CD C') CD 3 0-CD ..., I\) a a >> 00 I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS AS Group S Structures (Steel Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component 111.AS.TP-30 III.AS-2(T-Concrete:

all Concrete Soil OS) III.AS.TP-31 III.AS-7(T-Concrete: Concrete; Water -flowing 09) foundation; porous under su bfou ndation concrete foundation III.AS. TP-300 High-strength Low-alloy Air -indoor, structural steel, actual uncontrolled or bolting measured Air -outdoor yield strength ;::: 150 ksi (1,034 MPa) III.AS. TP-302 III.AS-S(T-Steel Steel Air -indoor, 11 ) components:

uncontrolled or all structural Air -outdoor steel Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation The weathering index for the continental US is shown in ASTM C33-90, Fig. 1. 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 from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation.

settlement Reduction of Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation If a de-watering system is relied upon watering 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 subfoundation Cracking Chapter XI.S6, "Structures Monitoring" No due to stress corrosion cracking Note: ASTM A 325, F 1S52, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts. Loss of material Chapter XI.S6, "Structures Monitoring" No due to corrosion If protective coatings are relied upon to manage the effects of aging, the structures monitoring program is to include provisions to address protective coating monitoring and maintenance.

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. (J) z c ;U m G) I ...... 00 a ;u CD :< I\) >> 00 I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A8 Group 8 Structures (Steel Tanks and Missile Barriers)

Structure Item Link and/or Material Environment Component III.A8.T-23 III.A8-9(T-Steel Stainless Water-23) components:

steel standing tank liner III.A8.TP-261 Structural Any Any bolting environment III.A8.TP-248 Structural Steel Air -indoor, bolting uncontrolled III.A8.TP-274 Structural Steel; Air -outdoor bolting galvanized steel Aging Effect! Further Aging Management Program (AMP) Mechanism Evaluation Cracking A plant-specific aging management Yes, plant-due to stress program is to be evaluated.

specific corrosion cracking; Loss of material due to pitting and crevice corrosion Loss of preload Chapter XI.S6, "Structures Monitoring" No due to self-loosening Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting and crevice corrosion Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting, and crevice corrosion 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. CD z c ;U m G) I ...... 00 a ;u CD :< I\) >> CD I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A9 Group 9 Structures (BWR Unit Vent Stack) Structure Item Link and/or Material Environment Component III.A9.TP-25 III.A9-1 (T-Concrete Concrete Any 03) (accessible environment areas): all III.A9.TP-27 III.A9-3(T-Concrete Concrete Ground 05) (accessible water/soil areas): below-grade exterior; foundation III.A9.TP-23 III.A9-5(T-Concrete Concrete Air -outdoor 01) (accessible areas): exterior above-and below-grade; foundation III.A9.TP-24 III.A9-6(T-Concrete Concrete Water -flowing 02) (accessible areas): exterior above-and below-grade; foundation III.A9.TP-26 III.A9-8(T-Concrete Concrete Air -indoor, 04) (accessible uncontrolled or areas): interior Air -outdoor and above-grade exterior Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking Chapter XI.S6, "Structures Monitoring" No due to expansion from reaction with aggregates Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Loss of material Chapter XI.S6, "Structures Monitoring" No (spalling, scaling) and cracking due to freeze-thaw Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" .j::>. CD o CD C') CD 3 0-CD ..., I\) a a >> CD I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A9 Group 9 Structures (BWR Unit Vent Stack) Structure Item Link and/or Material Environment Component III.A9.TP-204 III.A9-1 (T-Concrete Concrete Any 03) (inaccessible environment areas): all III.A9.TP-212 III.A9-3(T-Concrete Concrete Ground 05) (inaccessible water/soil areas): below-grade exterior; foundation III.A9.TP-29 III.A9-4(T-Concrete Concrete Ground 07) (inaccessible water/soil areas): below-grade exterior; foundation Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation Cracking Further evaluation is required to Yes, if due to expansion determine if a plant-specific aging concrete is not 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 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.

Cracking; loss of Chapter XI.S6, "Structures Monitoring" No bond; and loss of material (spalling, scaling) due to corrosion of embedded steel Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 0 z c ;U m G) I ...... 00 a ;u CD :< I\) >> CD I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A9 Group 9 Structures (BWR Unit Vent Stack) Structure Item Link and/or Material Environment Component III.A9.TP-67 III.A9-6(T-Concrete Concrete Water -flowing 02) (inaccessible areas): exterior above-and below-grade; foundation III.A9.TP-108 III.A9-5(T-Concrete Concrete Air -outdoor 01) (inaccessible areas): foundation Aging Effect/ Mechanism due to aggressive chemical attack Increase in porosity and permeability; loss of strength due to leaching of calcium hydroxide and carbonation Loss of material (spalling, scaling) and cracking due to freeze-thaw Further Aging Management Program (AMP) Evaluation Further evaluation is required to Yes, if determine if a plant-specific aging leaching is management program is needed to observed in manage increase in porosity, and accessible permeability due to leaching of calcium areas that hydroxide and carbonation of concrete impact 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 the intended function of the concrete structure.

Further evaluation is required for plants Yes, for plants that are located in moderate to severe located in weathering conditions (weathering moderate to index >100 day-inch/yr) (NUREG-severe 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 --" o CD C') CD 3 0-CD ..., I\) a a >> CD I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS A9 Group 9 Structures (BWR Unit Vent Stack) Structure Item Link and/or Material Environment Component III.A9.TP-30 III.A9-2(T-Concrete:

all Concrete Soil 08) III.A9.TP-31 III.A9-7(T-Concrete:

Concrete; Water -flowing 09) foundation; porous under su bfou ndation concrete foundation III.A9.TP-28 III.A9-9(T-Concrete:

Concrete Air -indoor, 06) interior; above-uncontrolled or grade exterior Air -outdoor Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation 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. 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 from licensee is to ensure proper functioning relied upon to settlement of the de-watering system through the control period of extended operation.

settlement Reduction in Chapter XI.S6, "Structures Monitoring" Yes, if a de-foundation If a de-watering system is relied upon watering 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 subfoundation Increase in Chapter XI.S6, "Structures Monitoring" No porosity and permeability; cracking; loss of material (spalling, scaling) due to aggressive 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 N z c ;U m G) I ...... 00 a ;u CD :< I\) >> CD I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS A9 Group 9 Structures (BWR Unit Vent Stack) Structure Item Link and/or Material Environment Component III.A9.TP-300 H ig h-stre ngth Low-alloy Air -indoor, structural steel, actual uncontrolled or bolting measured Air -outdoor yield strength ;:: 150 ksi (1,034 MPa) III.A9.TP-261 Structural Any Any bolting environment III.A9.TP-248 Structural Steel Air -indoor, bolting uncontrolled III.A9.TP-274 Structural Steel; Air -outdoor bolting galvanized steel Aging Effect/ Further Aging Management Program (AMP) Mechanism Evaluation chemical attack Cracking Chapter XI.S6, "Structures Monitoring" No due to stress corrosion cracking Note: ASTM A 325, F 1852, and ASTM A 490 bolts used in civil structures have not shown to be prone to SCC. SCC potential need not be evaluated for these bolts. Loss of preload Chapter XI.S6, "Structures Monitoring" No due to self-loosening Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting and crevice corrosion Loss of material Chapter XI.S6, "Structures Monitoring" No due to general, pitting, and crevice corrosion 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 (J) z c ;U m G) I ...... 00 a ;u CD :< I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.1 Class 1 Structure Item Link and!or Material Component III.B1.1.TP-42 III.B1.1-Building Concrete; 1 (T-29) concrete at grout locations of expansion and grouted anchors; grout pads for support base plates III.B1.1.T-28 III.B1.1-Constant and Steel 2(T-28) variable load spring hangers; guides; stops III.B1.1.TP-41 III.B1.1-High-strength Low-alloy 3(T-27) structural steel, actual bolting measured yield strength ;::: 150 ksi (1,034 MPa) III.B1.1.TP-45 III.B1.1-Sliding Lubrite; 5(T-32) surfaces graphitic tool steel; Fluorogold; Lubrofluor Aging Effect! Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Reduction in Chapter XI.S6, "Structures No uncontrolled or concrete anchor Monitoring" Air -outdoor capacity due to local concrete degradation!

service-induced cracking or other concrete aging mechanisms Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads Air -indoor, Cracking Chapter XI.S3, "ASME Section XI, No uncontrolled due to stress Subsection IWF" corrosion

cracking Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, debris, overload, wear 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 -....J o CD C') CD 3 0-CD ..., I\) a a I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS B1.1 Class 1 Structure Item Link and/or Material Component III.B1.1.TP-229 Structural Any bolting III.B1.1.TP-232 Structural Stainless steel bolting III.B1.1.TP-226 Structural Steel Bolting III.B1.1.TP-235 Structural Steel; bolting galvanized steel III.B1.1.TP-8 III.B1.1-Support Aluminum; 6(TP-8) members; galvanized 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 8(TP-3) members; steel; welds; bolted aluminum connections; support anchorage to building structure Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Any Loss of preload Chapter XI.S3, "ASME Section XI, No environment due to self-Subsection IWF" loosening Treated water Loss of material Chapter XI.M2, "Water Chemistry," No due to pitting and and crevice Chapter XI.S3, "ASME Section XI, corrosion Subsection IWF" Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion Air -outdoor Loss of material Chapter XI.S3, "ASME Section XI, No due to pitting Subsection IWF" and crevice corrosion Air -indoor, None None No uncontrolled Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No water leakage due to boric acid Corrosion" corrosion 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 CD z c ;U m G) I ...... 00 a ;u CD :< I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.1 Class 1 Structure Item Link and/or Material Component III.B1.1.TP-4 III.B1.1-Support Stainless steel 10(TP-4) members; welds; bolted connections; support anchorage to building structure III.B1.1.T-26 III.B1.1-Support Steel 12(T-26) members; welds; bolted connections; support anchorage to building structure III.B1.1.T-24 III.B1.1-Support Steel 13(T-24) members; welds; bolted connections; support anchorage to building structure III.B1.1.T-25 III.B1.1-Support Steel 14(T-25) members; welds; bolted connections; support anchorage to building structure Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air with borated None None No water leakage Air -indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA uncontrolled fatigue damage analysis (TLAA) to be evaluated for due to fatigue the period of extended operation.

See (Only ifCLB the SRP, Section 4.3 "Metal Fatigue," fatigue analysis for acceptable methods for meeting exists) the requirements of 10 CFR 54.21 (c)(1). Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled or due to general Subsection IWF" Air -outdoor and pitting corrosion Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No water leakage due to boric acid Corrosion" corrosion 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J1 CD o CD C') CD 3 0-CD ..., I\) a a I 0"1 z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS B1.1 Class 1 Structure Item Link and/or Material Component III.B1.1.TP-10 III.B1.1-Support Steel; 11 (TP-1 0) members; stainless steel welds; bolted connections; support anchorage to building structure III.B1.1.T-33 III.B1.1-Vibration Non-metallic 1S(T-33) isolation (e.g., rubber) elements Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Treated water Loss of material Chapter XI.M2, "Water Chemistry," for No <60C <<140 F) due to general BWR water, and (steel only), Chapter XI.S3, "ASME Section XI, pitting, and Subsection IWF" crevice corrosion Air -indoor, Reduction or Chapter XI.S3, "ASME Section XI, No uncontrolled or loss of isolation Subsection IWF" Air -outdoor function due to radiation hardening, temperature, humidity, sustained vibratory loading 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) 0 z c ;U m G) I ...... 00 a ;u CD :< I\) I (J) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.2 Class 2 and 3 Structure Item Link and!or Material Component III.B1.2.TP-42 III.B1.2-Building Concrete; 1 (T-29) concrete at grout locations of expansion and grouted anchors; grout pads for support base plates III.B1.2.T-28 III.B1.2-Constant and Steel 2(T-28) variable load spring hangers; guides; stops III.B1.2.TP-45 III.B1.2-Sliding Lubrite; 3(T-32) surfaces graphitic tool steel; Fluorogold; Lubrofluor III.B1.2.TP-229 Structural Any bolting Aging Effect! Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Reduction in Chapter XI.S6, "Structures No uncontrolled or concrete anchor Monitoring" Air -outdoor capacity due to local concrete degradation!

service-induced cracking or other concrete aging mechanisms Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, debris, overload, wear Any Loss of preload Chapter XI.S3, "ASME Section XI, No environment due to self-Subsection IWF" loosening 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) --" o CD C') CD 3 0-CD ..., I\) a a I -J z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS B1.2 Class 2 and 3 Structure Item Link and/or Material Component III.B1.2.TP-232 Structural Stainless steel bolting III.B1.2.TP-226 Structural Steel Bolting III.B1.2.TP-235 Structural Steel; bolting galvanized steel III.B1.2.TP-8 III.B1.2-Support Aluminum; 4(TP-8) members; galvanized 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 6(TP-3) members; steel; welds; bolted aluminum connections; support anchorage to building structure III.B1.2.TP-4 III.B1.2-Support Stainless steel 8(TP-4) members; welds; bolted connections; support Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Treated water Loss of material Chapter XI.M2, "Water Chemistry," No due to pitting and and crevice Chapter XI.S3, "ASME Section XI, corrosion Subsection IWF" Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion Air -outdoor Loss of material Chapter XI.S3, "ASME Section XI, No due to pitting Subsection IWF" and crevice corrosion Air -indoor, None None No uncontrolled Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No water leakage due to boric acid Corrosion" corrosion Air with borated None None No water leakage 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) N z c ;U m G) I ...... 00 a ;u CD :< I\) I 00 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.2 Class 2 and 3 Structure Item Link and/or Material Component anchorage to building structure III.B1.2.T-26 III.B1.2-Support Steel 9 (T-26) members; welds; bolted connections; support anchorage to building structure III.B1.2.T-24 III.B1.2-Support Steel 1 0(T-24) members; welds; bolted connections; support anchorage to building structure III.B1.2.T-25 III.B1.2-Support Steel 11 (T-25) members; welds; bolted connections; support anchorage to building structure III.B1.2.T-33 III.B1.2-Vibration Non-metallic 12(T-33) isolation (e.g., rubber) elements Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA uncontrolled fatigue damage analysis (TLAA) to be evaluated for due to fatigue the period of extended operation.

See (Only ifCLB the SRP, Section 4.3 "Metal Fatigue," fatigue analysis for acceptable methods for meeting exists) the requirements of 10 CFR 54.21 (c)(1). Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled or due to general Subsection IWF" Air -outdoor and pitting corrosion Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No water leakage due to boric acid Corrosion" corrosion Air -indoor, Reduction or Chapter XI.S3, "ASME Section XI, No uncontrolled or loss of isolation Subsection IWF" Air -outdoor function due to radiation hardening, temperature, 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) 0) o CD C') CD 3 0-CD ..., I\) a a I CD z c ;u m G) I ...... 00 a ;U CD :< I\) III 81.2 Item STRUCTURES AND COMPONENT SUPPORTS Class 2 and 3 Structure Aging Effect/ Further Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation humidity, sustained vibratory loading 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) I ...... a 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.3 Class MC (BWR Containment Supports)

Structure Item Link and!or Material Component III.B1.3.TP-42 III.B1.3-Building Concrete; 1 (T-29) concrete at grout locations of expansion and grouted anchors; grout pads for support base plates III.B1.3.T-28 III.B1.3-Constant and Steel 2(T-28) variable load spring hangers; guides; stops III.B1.3.TP-45 III.B1.3-Sliding Lubrite; 3(T-32) surfaces graphitic tool steel; Fluorogold; Lubrofluor III.B1.3.TP-229 Structural Any bolting III.B1.3.TP-232 Structural Stainless steel bolting Aging Effect! Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Reduction in Chapter XI.S6, "Structures No uncontrolled or concrete anchor Monitoring" Air -outdoor capacity due to local concrete degradation!

service-induced cracking or other concrete aging mechanisms Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads Air -indoor, Loss of Chapter XI.S3, "ASME Section XI, No uncontrolled or mechanical Subsection IWF" Air -outdoor function due to corrosion, distortion, dirt, debris, overload, wear Any Loss of preload Chapter XI.S3, "ASME Section XI, No environment due to self-Subsection IWF" loosening Treated water Loss of material Chapter XI.M2, "Water Chemistry," No due to pitting and and crevice Chapter XI.S3, "ASME Section XI, corrosion Subsection IWF" 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) (J1 o CD C') CD 3 0-CD ..., I\) a a I ...... z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS B1.3 Class MC (BWR Containment Supports)

Structure Item Link and/or Material Component III.B1.3.TP-226 Structural Steel bolting III.B1.3.TP-235 Structural Steel; bolting galvanized steel III.B1-3.TP-8 III.B1.3-Support Aluminum; 4(TP-8) members; galvanized III.B1.3-welds; bolted steel; stainless 5(TP-11) connections; steel III.B1.3-support 7(TP-5) anchorage to building structure III.B1.3.TP-3 III.B1.3-Support Galvanized 6(TP-3) members; steel; welds; bolted aluminum connections; support anchorage to building structure III.B1.3.TP-4 III.B1.3-Support Stainless steel 8(TP-4) members; welds; bolted connections; support anchorage to building structure Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled due to general, Subsection IWF" pitting, and crevice corrosion Air -outdoor Loss of material Chapter XI.S3, "ASME Section XI, No due to pitting Subsection IWF" and crevice corrosion Air -indoor, None None No uncontrolled Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No water leakage due to boric acid Corrosion" corrosion Air with borated None None No water leakage 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) (J) z c ;U m G) I ...... 00 a ;u CD :< I\) I ...... I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B1.3 Class MC (BWR Containment Supports)

Structure Item Link and/or Material Component III.B1.3.T-26 III.B1.3-Support Steel 9(T-26) members; welds; bolted connections; support anchorage to building structure III.B1.3.T-24 III.B1.3-Support Steel 1 O(T-24) members; welds; bolted connections; support anchorage to building structure III.B1.3.T-33 III.B1.3-Vibration Non-metallic 11 (T-33) isolation (e.g., rubber) elements Aging Effect/ Further Environment Aging Management Program (AMP) Mechanism Evaluation Air -indoor, Cumulative Fatigue is a time-limited aging Yes, TLAA uncontrolled fatigue damage analysis (TLAA) to be evaluated for due to fatigue the period of extended operation.

See (Only ifCLB the SRP, Section 4.3 "Metal Fatigue," fatigue analysis for acceptable methods for meeting exists) the requirements of 10 CFR 54.21 (c)(1). Air -indoor, Loss of material Chapter XI.S3, "ASME Section XI, No uncontrolled or due to general Subsection IWF" Air -outdoor and pitting corrosion Air -indoor, Reduction or Chapter XI.S3, "ASME Section XI, No uncontrolled or loss of isolation Subsection IWF" Air -outdoor function due to radiation hardening, temperature, humidity, sustained vibratory loading 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) CD z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation III.B2.TP-42 III.B2-1 (T-Building Concrete; Air -indoor, Reduction in Chapter XI.S6, "Structures No 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 yield cracking Note: ASTM A 325, F 1852, and 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" bearings; steel; function sliding Fluorogold; due to corrosion, support Lubrofluor distortion, dirt, surfaces debris, overload, wear 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" (J) CD o CD C') CD 3 0-CD ..., I\) a a III I\) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< III STRUCTURES AND COMPONENT SUPPORTS B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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.B2-welds; bolted steel; 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 building structure III.B2.TP-6 III.B2-Support Galvanized Air -outdoor Loss of material Chapter XI.S6, "Structures No 7(TP-6) members; steel; due to pitting and Monitoring" welds; bolted aluminum; crevice corrosion connections; stainless support steel anchorage to 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J 0 z c ;U m G) I ...... 00 a ;u CD :< I\) III I\) I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation building 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" welds; bolted Air -outdoor and pitting 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 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J N z c ;U m G) I ...... 00 a ;u CD :< I\) III CJ.) I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation III.B3.TP-42 III.B3-1 (T-Building Concrete; Air -indoor, Reduction in Chapter XI.S6, "Structures No 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 yield cracking Note: ASTM A 325, F 1852, and 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" steel pitting, and crevice corrosion III.B3.TP-8 III.B3-Support Aluminum; Air -indoor, None None No 2(TP-8) members; galvanized uncontrolled III.B3-welds; bolted steel; 5(TP-5) connections; stainless 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J 0) o CD C') CD 3 0-CD ..., I\) a a III CJ.) I CJ.) z c ;u m G) I ...... 00 a ;U CD :< III STRUCTURES AND COMPONENT SUPPORTS B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 6(TP-4) members; steel water leakage 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 anchorage to building structure III.B3.T-25 III.B3-8(T-Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion connections; support 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J .j::>. z c ;U m G) I ...... 00 a ;u CD :< I\) 0 CD C') CD 3 0-CD ..., I\) a a III 83 Item STRUCTURES AND COMPONENT SUPPORTS Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation Structure Aging Effect/ Further Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation anchorage to building structure

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J (J) z c ;U m G) I ...... 00 a ;u CD :< I\) III .j:>. I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment Structure Aging Effect! Aging Management Program Further Item Link and!or Material Environment Component Mechanism (AMP) Evaluation III.B4.TP-42 III.B4-1 (T-Building Concrete; Air -indoor, Reduction in Chapter XI.S6, "Structures No 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 yield strength cracking Note: ASTM A 325, F 1852, and ;::: 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" bearings; steel; function sliding Fluorogold; due to corrosion, support Lubrofluor distortion, dirt, surfaces debris, overload, wear 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J -....J o CD C') CD 3 0-CD ..., I\) a a z c ;u m G) I ...... 00 a ;U CD :< III STRUCTURES AND COMPONENT SUPPORTS B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment Structure Aging Effect/ Aging Management Program Further Item Link and/or Material Environment Component Mechanism (AMP) Evaluation 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 structure III.B4.TP-6 III.B4-Support Galvanized Air -outdoor Loss of material Chapter XI.S6, "Structures No 7(TP-6) members; steel; due to pitting Monitoring" welds; bolted aluminum; and crevice connections; stainless steel corrosion support anchorage to 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J CD z c ;U m G) I ...... 00 a ;u CD :< I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B4 Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment Structure Aging Effect/ Aging Management Program Further Item Link and/or Material Environment Component Mechanism (AMP) Evaluation building 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 III.B4.TP-44 III.B4-Vibration Non-metallic Air -indoor, Reduction or Chapter XI.S3, "ASME Section XI, No 12(T-31) isolation (e.g., rubber) uncontrolled or loss of isolation Subsection IWF" elements Air -outdoor function due to radiation hardening, temperature, 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" -....J CD o CD C') CD 3 0-CD ..., I\) a a III .j:>. I 0'1 z c ;u m G) I ...... 00 a ;U CD :< III 84 Item STRUCTURES AND COMPONENT SUPPORTS Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment Structure Aging Effect/ Aging Management Program Further Link and/or Material Environment Component Mechanism (AMP) Evaluation humidity, sustained vibratory loading

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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD --" z c ;U m G) I ...... 00 a ;u CD :< I\) III 0"1 I I\) 0 CD C') CD 3 0-CD ..., I\) a a III STRUCTURES AND COMPONENT SUPPORTS B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation III.B5.TP-42 III.B5-1 (T-Building Concrete; Air -indoor, Reduction in Chapter XI.S6, "Structures No 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 yield cracking Note: ASTM A 325, F 1852, and 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" steel pitting, and crevice corrosion III.B5.TP-8 III.B5-Support Aluminum; Air -indoor, None None No 2(TP-8) members; galvanized uncontrolled III.B5-welds; bolted steel; 5(TP-5) connections; stainless 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD N o CD C') CD 3 0-CD ..., I\) a a III 0'1 I CJ.) z c ;u m G) I ...... 00 a ;U CD :< I\) III STRUCTURES AND COMPONENT SUPPORTS B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation 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 6(TP-4) members; steel water leakage 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 anchorage to building structure III.B5.T-25 III.B5-8(T-Support Steel Air with borated Loss of material Chapter XI.M1 0, "Boric Acid No 25) members; water leakage due to boric acid Corrosion" welds; bolted corrosion connections; support 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD 0) z c ;U m G) I ...... 00 a ;u CD :< I\) III 0'1 I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a III 85 Item STRUCTURES AND COMPONENT SUPPORTS Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures Structure Aging Effect/ Further Link and/or Material Environment Aging Management Program (AMP) Component Mechanism Evaluation anchorage to building structure 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 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD -....J z c ;U m G) I ...... 00 a ;u CD :< I\) <: >> ...... I I\) 0 CD C') CD 3 0-CD ..., I\) a a IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM A1 Reactor Vessel (BWR) Item Link Structure and/or Material Environment Aging Effect/ Component Mechanism IV.A1.R-68 IV.A 1-1 (R-Nozzle safe ends Stainless Reactor coolant Cracking 68) and welds: high-steel; due to stress pressure core nickel alloy corrosion 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 66) rod drive return or without due to cyclic line stainless loading steel cladding)

IV.A1.R-65 IV.A1-3(R-Nozzles: Steel (with Reactor coolant Cracking 65) feedwater or without due to cyclic stainless loading steel cladding)

Aging Management Program (AMP) Further Evaluation Chapter XI.M7, "BWR Stress No Corrosion Cracking," and Chapter XI.M2, "Water Chemistry" Chapter XI.M6, "BWR Control Rod No Drive Return Line Nozzle" Chapter XI.M5, "BWR Feedwater No Nozzle" 0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD CD o CD C') CD 3 0-CD ..., I\) a a <: >> ...... I CJ.) z c ;u m G) I ...... 00 a ;U CD < i\J IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM A1 Reactor Vessel (BWR) Item Link Structure and!or Material Environment Aging Effect! Component Mechanism IV.A1.R-67 IV.A1-4(R-Nozzles: low-Steel Reactor coolant Loss of fracture 67) pressure coolant and neutron flux toughness injection or RHR due to neutron injection mode irradiation embrittlement Aging Management Program (AMP) Further Evaluation Neutron irradiation embrittiement is a Yes, TLAA time-limited aging analysis (TLAA) to be evaluated for the period of extended operation for all ferritic materials that have a neutron fluence greater than 1 E17 n!cm 2 (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 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 of 1 0 CFR 54.21 (c).

0 >> G) 0 0 0 --" 0) CD 0 I 0 0 --" CD CD z c ;U m G) I ...... 00 a ;u CD :< I\) <: >> ...... I .j:>. 0 CD C') CD 3 0-CD ..., I\) a a IV REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM A1 Reactor Vessel (BWR) Item Link Structure and/or Material Environment Aging Effect/ Component Mechanism IV.A1.RP-369 IV.A1-5(R-Penetrations:

Stainless Reactor coolant Cracking 69) control rod drive steel; due to stress stub tubes; in nickel alloy corrosion 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 69) drain line steel; due to stress nickel alloy corrosion cracking, intergranular stress corrosion cracking, cyclic loading IV.A1.R-70 IV.A1-6(R-Pressure vessel Steel Air -indoor, Cumulative

70) support skirt and uncontrolled fatigue damage attachment welds due to fatigue IV.A1.R-04 IV.A1-7(R-Reactor vessel Steel (with Reactor coolant Cumulative

04) components:

or without fatigue damage flanges; nozzles; nickel-alloy due to fatigue penetrations; safe or ends; thermal stainless sleeves; vessel steel shells, heads and cladding);

welds stainless steel; nickel alloy Aging Management Program (AMP) Further Evaluation Chapter XI.M8, "BWR Penetrations," No and Chapter XI.M2, "Water Chemistry" Chapter XI.M1, "ASME Section XI No Inservice Inspection, Subsections IWB, IWC, and IWD," and Chapter XI.M2, "Water Chemistry" Fatigue is a time-limited aging analysis Yes, TLAA (TLAA) to be evaluated for the period 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). Fatigue is a TLAA evaluated for the Yes, TLAA period of extended operation, and for Class 1 components environmental effects on fatigue are to be addressed. (See SRP, Sec 4.3 "Metal Fatigue," for acceptable methods to comply with 10 CFR 54.21 (c)(1))