1177
Grand Gulf Nuclear Station License Renewal Application i PREFACE The following describes the information location, layout, and editorial conventions in the Grand Gulf Nuclear Station (GGNS) License Renewal Application (LRA) (hereinafter referred to as “this application” or “the application”). Abbreviated names and acronyms used throughout the application are defined at the end of this preface. Commonly understood terms (such as U.S.) and terms used only in referenced document numbers may not be identified in this table. Regulatory documents such as NUREG-1801, Generic Aging Lessons Learned (GALL) Report, and 10 CFR 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants,” are referred to by the document number, i.e., NUREG-1801 and 10 CFR 54, respectively. References to the UFSAR are to the version of the GGNS Updated Final Safety Analysis Report in effect on March 1, 2011. The effective date of that version is April 5, 2010. Where revised information in subsequent UFSAR amendments materially affects the LRA, the LRA will be amended in the annual update in accordance with 10 CFR 54.21(b). Section 1 provides administrative information required by 10 CFR 54.17 and 10 CFR 54.19. Section 2 describes and justifies the methods used to determine the systems and structures within the scope of license renewal and the structures and components subject to aging management review. The results of the system and structure scoping are provided in Tables 2.2- 1 through 2.2-4. Tables 2.2-1-A, 2.2-1-B and 2.2-3 list mechanical systems, electrical systems and structures, respectively, within the scope of license renewal. Tables 2.2-2 and 2.2-4 list the systems and structures, respectively, not within the scope of license renewal. Section 2 also provides descriptions of in-scope systems and structures and their intended functions with tables identifying components and commodities requiring aging management review and their component intended functions. References are provided to the results of the aging management reviews in Section 3. The descriptions of systems in Section 2 identify license renewal drawings that depict the components subject to aging management review for mechanical systems. The drawings are provided in a separate submittal. Section 3 describes the results of aging management reviews of mechanical, electrical and structural components requiring aging management review. Section 3 is divided into sections that address (1) the reactor vessel, internals, and reactor coolant system, (2) engineered safety features, (3) auxiliary systems, (4) steam and power conversion systems, (5) structures and component supports, and (6) electrical and instrumentation and controls. The tables in Section 3 provide a summary of information concerning aging effects requiring management and applicable aging management programs for component and commodity groups subject to aging management review. The information presented in the tables is based on the format and content of NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U.S. Nuclear Regulatory Commission, December 2010. The tables include comparisons with the evaluations documented in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, U.S. Nuclear Regulatory Commission, December 2010.

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  • Grand Gulf Nuclear StationLicense Renewal Application

    i

    PREFACE

    The following describes the information location, layout, and editorial conventions in the Grand Gulf Nuclear Station (GGNS) License Renewal Application (LRA) (hereinafter referred to as “this application” or “the application”). Abbreviated names and acronyms used throughout the application are defined at the end of this preface. Commonly understood terms (such as U.S.) and terms used only in referenced document numbers may not be identified in this table. Regulatory documents such as NUREG-1801, Generic Aging Lessons Learned (GALL) Report, and 10 CFR 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants,” are referred to by the document number, i.e., NUREG-1801 and 10 CFR 54, respectively. References to the UFSAR are to the version of the GGNS Updated Final Safety Analysis Report in effect on March 1, 2011. The effective date of that version is April 5, 2010. Where revised information in subsequent UFSAR amendments materially affects the LRA, the LRA will be amended in the annual update in accordance with 10 CFR 54.21(b).

    Section 1 provides administrative information required by 10 CFR 54.17 and 10 CFR 54.19.

    Section 2 describes and justifies the methods used to determine the systems and structures within the scope of license renewal and the structures and components subject to aging management review. The results of the system and structure scoping are provided in Tables 2.2-1 through 2.2-4. Tables 2.2-1-A, 2.2-1-B and 2.2-3 list mechanical systems, electrical systems and structures, respectively, within the scope of license renewal. Tables 2.2-2 and 2.2-4 list the systems and structures, respectively, not within the scope of license renewal. Section 2 also provides descriptions of in-scope systems and structures and their intended functions with tables identifying components and commodities requiring aging management review and their component intended functions. References are provided to the results of the aging management reviews in Section 3. The descriptions of systems in Section 2 identify license renewal drawings that depict the components subject to aging management review for mechanical systems. The drawings are provided in a separate submittal.

    Section 3 describes the results of aging management reviews of mechanical, electrical and structural components requiring aging management review. Section 3 is divided into sections that address (1) the reactor vessel, internals, and reactor coolant system, (2) engineered safety features, (3) auxiliary systems, (4) steam and power conversion systems, (5) structures and component supports, and (6) electrical and instrumentation and controls. The tables in Section 3 provide a summary of information concerning aging effects requiring management and applicable aging management programs for component and commodity groups subject to aging management review. The information presented in the tables is based on the format and content of NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, U.S. Nuclear Regulatory Commission, December 2010. The tables include comparisons with the evaluations documented in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, U.S. Nuclear Regulatory Commission, December 2010.

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    Section 4 addresses time-limited aging analyses, as defined by 10 CFR 54.3. It includes identification of the component or subject and an explanation of the time-dependent aspects of the calculation or analysis. Section 4 demonstrates whether (1) the analyses remain valid for the period of extended operation, (2) the analyses have been projected to the end of the period of extended operation, or (3) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.

    Section 4 also documents the determination that no plant-specific exemptions granted pursuant to 10 CFR 50.12 that are based on time-limited aging analyses as defined in §54.3 will remain in effect.

    Appendix A, Updated Final Safety Analysis Report Supplement, provides a summary description of programs and activities for managing the effects of aging for the period of extended operation. A summary description of the evaluation of time-limited aging analyses for the period of extended operation is also included. Following issuance of the renewed license, the material contained in this appendix will be incorporated into the UFSAR. The information in Appendix A fulfills the requirements in 10 CFR 54.21(d).

    Appendix B, Aging Management Programs and Activities, describes aging management programs and activities that will manage aging effects on components and structures within the scope of license renewal such that they will continue to perform their intended functions consistent with the current licensing basis (CLB) for the period of extended operation. Appendix B contains a comparison of site programs to the programs evaluated in NUREG-1801. The information in Section 2, Section 3, and Appendix B fulfills the requirements of 10 CFR 54.21(a).

    Appendix C is the site response to Boiling Water Reactor Vessel and Internals Program (BWRVIP) Applicant Action Items. License renewal application action items identified in the corresponding Nuclear Regulatory Commission (NRC) safety evaluation (SE) for each of the reports listed are addressed in this appendix.

    Appendix D, Technical Specification Changes, concludes that no technical specification changes are necessary to manage the effects of aging during the period of extended operation. The information in Appendix D fulfills the requirements in 10 CFR 54.22.

    Appendix E is the environmental information which fulfills the requirements of 10 CFR 54.23 and 10 CFR 51.53(c).

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    ABBREVIATIONS AND ACRONYMS

    Abbreviation or Acronym DescriptionABV auxiliary building ventilation

    AC alternating current

    ACI American Concrete Institute

    ACSR aluminum conductor steel reinforced

    ADAMS [NRC] Agencywide Documents Access and Management System

    ADHRS alternate decay heat removal subsystem

    ADS automatic depressurization system

    AEM aging effect/mechanism

    Al aluminum

    AMP aging management program

    AMR aging management review

    ANSI American National Standards Institute

    APRM average power range monitor

    ARI alternate rod insertion

    ART adjusted reference temperature

    ASME American Society of Mechanical Engineers

    ASTM American Society for Testing and Materials

    ATWS anticipated transient without scram

    BADGER Boron-10 Areal Density Gage for Evaluating Racks

    BTP Branch Technical Position

    BOP balance of plant

    BWR boiling water reactor

    BWRVIP Boiling Water Reactor Vessel and Internals Program

    CAP Corrective Action Program

    CASS cast austenitic stainless steel

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    CBHVAC control building heating ventilating and air conditioning

    CCW component cooling water

    CDIC containment and drywell instrumentation and control

    CE conducts electricity

    CF chemistry factor

    CFR Code of Federal Regulations

    CGCS combustible gas control system

    CII containment inservice inspection

    CLB current licensing basis

    CLRT containment leak rate test

    CO2 carbon dioxide

    CRD control rod drive

    CRGT control rod guide tube

    CRHVAC control room heating, ventilation and air conditioning

    CRVICS containment and reactor vessel isolation control system

    CRWST condensate and refueling water storage and transfer

    CS carbon steel

    CSA criticality safety analysis

    CST condensate storage tank

    Cu copper

    CUF cumulative usage factor

    DBA design basis accident

    DCW drywell chilled water

    DELS diesel engine lube [oil] system

    P differential pressure

    DGBV diesel generator building ventilation

    DGCAIES diesel generator combustion air intake and exhaust system

    DGCWS diesel generator cooling water system

    Abbreviation or Acronym Description

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    DGSS diesel generator [air] starting system

    DSP&UCP drywell, suppression pool, and upper containment pool

    ECCS emergency core cooling system

    EFPY effective full power years

    EHC electrohydraulic control

    EIC electrical and instrumentation and control

    EN shelter or protection

    EOF Emergency Operations Facility

    EOI Entergy Operations, Inc.

    EPRI Electric Power Research Institute

    EPU extended power uprate

    EPRV emergency pump room ventilation

    EQ environmental qualification

    ESBRV emergency switchgear and battery rooms ventilation

    ESF engineered safety feature

    ESFESRC ESF electrical switchgear rooms cooling

    ext external

    FAC flow-accelerated corrosion

    FB fire barrier

    FC flow control

    FD flow distribution

    FED floor and equipment drainage

    Fen fatigue correction factor(s)

    FERC Federal Energy Regulatory Commission

    FHAR Fire Hazards Analysis Report

    FHAV fuel handling area ventilation

    FLB flood barrier

    Abbreviation or Acronym Description

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    FPCC fuel pool cooling and cleanup

    FSAR Final Safety Analysis Report (historical document)

    ft-lb foot-pound

    FW feedwater

    FW-LCS feedwater leakage control system

    FWPV fire water pumphouse ventilation

    GE General Electric

    GGN2 Grand Gulf Nuclear Station Unit 2 (incomplete and abandoned)

    GGNS Grand Gulf Nuclear Station

    GL Generic Letter

    GSI Generic Safety Issue

    H2 hydrogen

    HCU hydraulic control unit

    HDPE high density polyethylene

    HELB high-energy line break

    HEPA high-efficiency particulate air

    HP high pressure

    HPCS high pressure core spray

    HPCSDG HPCS diesel generator

    HS heat sink

    HVAC heating, ventilation, and air conditioning

    HWC hydrogen water chemistry

    HWC-M moderate hydrogen water chemistry

    IA instrument air

    IASCC irradiation-assisted stress corrosion cracking

    ID inside diameter; identification

    Abbreviation or Acronym Description

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    IN insulation (electrical); [NRC] Information Notice

    INS insulation

    int internal

    IPA integrated plant assessment

    IRM intermediate range monitor

    ISG Interim Staff Guidance

    ISI inservice inspection

    ISP Integrated Surveillance Program

    ksi kilo-pounds per square inch

    KV or kV kilo-volt

    LA Louisiana

    LAR license amendment request

    LAS low alloy steel

    LOCA loss of coolant accident

    LP low pressure

    LPCI low pressure coolant injection

    LPCS low pressure core spray

    LPRM local power range monitors

    LR license renewal

    LRA license renewal application

    MB missile barrier

    MCM thousand circular mils

    MoS2 molybdenum disulfide

    MRS main and reheat steam

    MS Mississippi

    MSIV main steam isolation valve

    Abbreviation or Acronym Description

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    MSIV-LCS main steam isolation valve leakage control system

    MSR moisture separator-reheater

    MUWT makeup water treatment

    MWt megawatts-thermal

    NA not applicable

    NB nuclear boiler

    NBA nickel-based alloy

    n/cm2 neutrons per square centimeter

    NDE nondestructive examinations

    NEI Nuclear Energy Institute

    NESC National Electrical Safety Code

    NFPA National Fire Protection Association

    Ni nickel

    NPS nominal pipe size

    NRC Nuclear Regulatory Commission

    NSSS nuclear steam supply system

    OE operating experience

    OEP Operating Experience Program

    OVHLL Overhead Heavy Load and Light Load

    PB pressure boundary

    PCA plant compressed air

    PCW plant chilled water

    pH potential of hydrogen

    PM preventive maintenance

    ppb parts per billion

    ppm parts per million

    PRM process radiation monitoring

    Abbreviation or Acronym Description

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    PSW plant service water

    P-T pressure-temperature

    PVC polyvinyl chloride

    PWR pressurized water reactor

    QA quality assurance

    QCTP quencher confirmatory test program

    RCIC reactor core isolation cooling

    RCPB reactor coolant pressure boundary

    RCS reactor coolant system

    RFP reactor feed pump

    RFPT reactor feed pump turbine

    RG Regulatory Guide

    RHR residual heat removal

    rpm revolutions per minute

    RPS reactor protection system

    RPV reactor pressure vessel (synonymous with reactor vessel)

    RR reactor recirculation

    RTNDT reference temperature (nil-ductility transition)

    RWCU reactor water cleanup

    RWST refueling water storage tank

    SA service air

    SAMA severe accident mitigation alternatives

    S&PC steam and power conversion

    SBO station blackout

    SC structure or component

    SCBA self-contained breathing apparatus

    Abbreviation or Acronym Description

  • Grand Gulf Nuclear StationLicense Renewal Application

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    SCC stress corrosion cracking

    sccm standard cubic centimeters per minute

    SDG standby diesel generator

    SE, SER Safety Evaluation, Safety Evaluation Report

    SERI System Energy Resources, Inc.

    SGTS standby gas treatment system

    SLC standby liquid control

    SMEPA South Mississippi Electric Power Association

    SNS support for Criterion (a)(2) equipment

    SPCU suppression pool cleanup

    SPMU suppression pool make-up

    SRE support for Criterion (a)(3) equipment

    SRM source range monitor

    SRP [NUREG-1800, License Renewal] Standard Review Plan

    SRV safety relief valve

    SS stainless steel

    SSC system, structure, or component

    SSR support for Criterion (a)(1) equipment

    SSW standby service water

    SSWPV standby service water pumphouse ventilation

    STAMR subject to aging management review

    TBCW turbine building cooling water

    TBV turbine building ventilation

    TIP traversing incore probe

    TLAA time-limited aging analysis (analyses)

    UHS ultimate heat sink

    UFSAR Updated Final Safety Analysis Report

    Abbreviation or Acronym Description

  • Grand Gulf Nuclear StationLicense Renewal Application

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    USE upper-shelf energy

    V volt

    yr year

    Zn zinc

    ¼T one-fourth of the way through the vessel wall measured from the internal surface of the vessel

    Abbreviation or Acronym Description

  • Grand Gulf Nuclear StationLicense Renewal Application

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    TABLE OF CONTENTS

    1.0 ADMINISTRATIVE INFORMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1

    1.1 GENERAL INFORMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11.1.1 Name of Applicant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11.1.2 Address of Applicant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11.1.3 Description of Business of Applicants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-21.1.4 Legal Status and Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-21.1.5 Class and Period of License Sought . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-91.1.6 Alteration Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-101.1.7 Regulatory Agencies with Jurisdiction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-101.1.8 Local News Publications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-101.1.9 Conforming Changes to Standard Indemnity Agreement . . . . . . . . . . . . . . . . . . . . . . 1-111.1.10 Restricted Data Agreement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11

    1.2 PLANT DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-11

    2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RESULTS. . . . . . . . . . . . 2.0-1

    2.1 SCOPING AND SCREENING METHODOLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-12.1.1 Scoping Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1

    2.1.1.1 Application of Safety-Related Scoping Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-32.1.1.2 Application of Criterion for Nonsafety-Related SSCs Whose Failure Could

    Prevent the Accomplishment of Safety Functions . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-42.1.1.2.1 Functional Failures of Nonsafety-Related SSCs. . . . . . . . . . . . . . . . . . . . . . . . 2.1-42.1.1.2.2 Physical Failures of Nonsafety-Related SSCs . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-4

    2.1.1.3 Application of Criterion for Regulated Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-72.1.1.3.1 Commission's Regulations for Fire Protection (10 CFR 50.48) . . . . . . . . . . . . 2.1-72.1.1.3.2 Commission's Regulations for Environmental Qualification (10 CFR 50.49) . . 2.1-82.1.1.3.3 Commission's Regulations for Pressurized Thermal Shock (10 CFR 50.61) . . 2.1-92.1.1.3.4 Commission's Regulations for Anticipated Transients without Scram

    (10 CFR 50.62) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-92.1.1.3.5 Commission's Regulations for Station Blackout (10 CFR 50.63) . . . . . . . . . . . 2.1-9

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    2.1.2 Screening Methodology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-10

    2.1.2.1 Screening of Mechanical Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-112.1.2.1.1 Identifying Components Subject to Aging Management Review . . . . . . . . . . . 2.1-112.1.2.1.2 Identifying Components Subject to Aging Management Review Based on

    Support of an Intended Function for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . . . . . . 2.1-122.1.2.1.3 Mechanical System Drawings. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-14

    2.1.2.2 Screening of Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-152.1.2.2.1 Structural Component and Commodity Groups . . . . . . . . . . . . . . . . . . . . . . . . 2.1-152.1.2.2.2 Evaluation Boundaries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-152.1.2.2.3 Intended Functions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-16

    2.1.2.3 Electrical and Instrumentation and Control Systems . . . . . . . . . . . . . . . . . . . . . . . 2.1-162.1.2.3.1 Passive Screening . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-172.1.2.3.2 Long-Lived Screening . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-17

    2.1.2.4 Consumables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-182.1.2.4.1 Packing, Gaskets, Component Seals, and O-Rings . . . . . . . . . . . . . . . . . . . . . 2.1-182.1.2.4.2 Structural Sealants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-182.1.2.4.3 Oil, Grease, and Filters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-182.1.2.4.4 System Filters, Fire Extinguishers, Fire Hoses, and Air Packs . . . . . . . . . . . . . 2.1-18

    2.1.3 Interim Staff Guidance Discussion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-19

    2.1.4 Generic Safety Issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-19

    2.1.5 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-19

    2.1.6 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-20

    2.2 PLANT LEVEL SCOPING RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2-1

    2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS . . . . . . . . . . . . . 2.3-12.3.1 Reactor Coolant System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1

    2.3.1.1 Reactor System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-22.3.1.1.1 Reactor Vessel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-52.3.1.1.2 Reactor Vessel Internals. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-6

    2.3.1.2 Reactor Coolant Pressure Boundary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-132.3.1.3 Nuclear Boiler System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-162.3.1.4 Reactor Recirculation System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-202.3.1.5 Neutron Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-222.3.1.6 Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-242.3.1.7 Miscellaneous RCS Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . . . . 2.3-25

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    2.3.2 Engineered Safety Features . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-36

    2.3.2.1 Residual Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-372.3.2.2 Low Pressure Core Spray. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-422.3.2.3 High Pressure Core Spray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-442.3.2.4 Reactor Core Isolation Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-462.3.2.5 Pressure Relief . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-482.3.2.6 Standby Gas Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-512.3.2.7 Containment Penetrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-532.3.2.8 Miscellaneous ESF Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . . . . 2.3-57

    2.3.3 Auxiliary Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-71

    2.3.3.1 Control Rod Drive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-722.3.3.2 Standby Liquid Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-752.3.3.3 Suppression Pool Makeup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-772.3.3.4 Leakage Detection and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-792.3.3.5 Combustible Gas Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-832.3.3.6 Fuel Pool Cooling and Cleanup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-872.3.3.7 Standby Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-902.3.3.8 Component Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-922.3.3.9 Plant Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-942.3.3.10 Floor and Equipment Drainage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-972.3.3.11 Compressed Air . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1002.3.3.12 Fire Protection – Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1032.3.3.13 Fire Protection – Halon and CO2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1062.3.3.14 Plant Chilled Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1092.3.3.15 Standby Diesel Generator. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1112.3.3.16 HPCS Diesel Generator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1152.3.3.17 Control Room Heating, Ventilation and Air Conditioning . . . . . . . . . . . . . . . . . . . . 2.3-1192.3.3.18 Heating, Ventilation and Air Conditioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1222.3.3.19 Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . 2.3-134

    2.3.4 Steam and Power Conversion Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-208

    2.3.4.1 Condensate and Refueling Water Storage and Transfer . . . . . . . . . . . . . . . . . . . . 2.3-2092.3.4.2 Miscellaneous Steam and Power Conversion Systems in Scope for 10 CFR

    54.4(a)(2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-212

    2.4 SCOPING AND SCREENING RESULTS: STRUCTURES . . . . . . . . . . . . . . . . . . . . . . 2.4-12.4.1 Containment Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2

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    2.4.2 Water Control Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-7

    2.4.3 Turbine Building, Process Facilities and Yard Structures . . . . . . . . . . . . . . . . . . . . . . 2.4-10

    2.4.4 Bulk Commodities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-24

    2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1

    3.0 AGING MANAGEMENT REVIEW RESULTS . . . . . . . . . . . . . . . . . . . . . . . 3.0-1

    3.1 REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM. . . . . . . . . . 3.1-13.1.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1

    3.1.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1

    3.1.2.1 Materials, Environment, Aging Effects Requiring Management, and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-2

    3.1.2.1.1 Reactor Vessel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-23.1.2.1.2 Reactor Vessel Internals. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-33.1.2.1.3 Reactor Coolant Pressure Boundary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-43.1.2.1.4 Miscellaneous RCS Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . 3.1-5

    3.1.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.1-63.1.2.2.1 Cumulative Fatigue Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-63.1.2.2.2 Loss of Material Due to General, Pitting, and Crevice Corrosion . . . . . . . . . . . 3.1-73.1.2.2.3 Loss of Fracture Toughness due to Neutron Irradiation Embrittlement . . . . . . 3.1-73.1.2.2.4 Cracking due to Stress Corrosion Cracking (SCC) and Intergranular Stress

    Corrosion Cracking (IGSCC) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-73.1.2.2.5 Crack Growth due to Cyclic Loading. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-73.1.2.2.6 Cracking due to Stress Corrosion Cracking . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.7 Cracking due to Cyclic Loading . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.8 Loss of Material due to Erosion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.9 Cracking due to Stress Corrosion Cracking and Irradiation-Assisted Stress

    Corrosion Cracking (IASCC). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.10 Loss of Fracture Toughness due to Neutron Irradiation Embrittlement,

    Change in Dimension due to Void Swelling, Loss of Preload due to Stress Relaxation, or Loss of Material due to Wear. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-8

    3.1.2.2.11 Cracking due to Primary Water Stress Corrosion Cracking (PWSCC) . . . . . . . 3.1-83.1.2.2.12 Cracking due to Fatigue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.13 Cracking due to Stress Corrosion Cracking and Fatigue . . . . . . . . . . . . . . . . . 3.1-83.1.2.2.14 Loss of Material due to Wear . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-8

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    3.1.2.2.15 Quality Assurance for Aging Management of Nonsafety-Related Components 3.1-83.1.2.3 Time-Limited Aging Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-9

    3.1.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-9

    3.2 ENGINEERED SAFETY FEATURES SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-13.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-1

    3.2.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-1

    3.2.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-2

    3.2.2.1.1 Residual Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-23.2.2.1.2 Low Pressure Core Spray. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-33.2.2.1.3 High Pressure Core Spray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-43.2.2.1.4 Reactor Core Isolation Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-53.2.2.1.5 Pressure Relief System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-63.2.2.1.6 Standby Gas Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-73.2.2.1.7 Containment Penetrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-83.2.2.1.8 Miscellaneous ESF Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . . . . 3.2-9

    3.2.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.2-103.2.2.2.1 Cumulative Fatigue Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-103.2.2.2.2 Loss of Material due to Cladding [Breach] . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-103.2.2.2.3 Loss of Material due to Pitting and Crevice Corrosion . . . . . . . . . . . . . . . . . . . 3.2-103.2.2.2.4 Loss of Material due to Erosion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-113.2.2.2.5 Loss of Material due to General Corrosion and Fouling that Leads to

    Corrosion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-113.2.2.2.6 Cracking due to Stress Corrosion Cracking . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-113.2.2.2.7 Quality Assurance for Aging Management of Nonsafety-Related Components 3.2-11

    3.2.2.3 Time-Limited Aging Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-11

    3.2.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-11

    3.3 AUXILIARY SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-13.3.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1

    3.3.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1

    3.3.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-6

    3.3.2.1.1 Control Rod Drive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-63.3.2.1.2 Standby Liquid Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-7

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    3.3.2.1.3 Suppression Pool Makeup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-83.3.2.1.4 Leakage Detection and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-83.3.2.1.5 Combustible Gas Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-93.3.2.1.6 Fuel Pool Cooling and Cleanup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-103.3.2.1.7 Standby Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-113.3.2.1.8 Component Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-123.3.2.1.9 Plant Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-133.3.2.1.10 Floor and Equipment Drains . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-143.3.2.1.11 Compressed Air . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-153.3.2.1.12 Fire Protection – Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-163.3.2.1.13 Fire Protection – Halon and CO2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-173.3.2.1.14 Plant Chilled Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-183.3.2.1.15 Standby Diesel Generator. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-193.3.2.1.16 HPCS Diesel Generator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-203.3.2.1.17 Control Room Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-213.3.2.1.18 Heating, Ventilation and Air Conditioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-223.3.2.1.19 Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) . . . . . . . . . . 3.3-23

    3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.3-253.3.2.2.1 Cumulative Fatigue Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-253.3.2.2.2 Cracking due to Stress Corrosion Cracking and Cyclic Loading. . . . . . . . . . . . 3.3-253.3.2.2.3 Cracking due to Stress Corrosion Cracking . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-253.3.2.2.4 Loss of Material due to Cladding Breach . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-253.3.2.2.5 Loss of Material due to Pitting and Crevice Corrosion . . . . . . . . . . . . . . . . . . . 3.3-253.3.2.2.6 Quality Assurance for Aging Management of Nonsafety-Related Components 3.3-26

    3.3.2.3 Time-Limited Aging Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-26

    3.3.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-26

    3.4 STEAM AND POWER CONVERSION SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-13.4.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-1

    3.4.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-1

    3.4.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-3

    3.4.2.1.1 Condensate and Refueling Water Storage and Transfer . . . . . . . . . . . . . . . . . 3.4-33.4.2.1.2 Miscellaneous Steam and Power Conversion Systems in Scope for 10 CFR

    54.4(a)(2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-43.4.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.4-5

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    3.4.2.2.1 Cumulative Fatigue Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-63.4.2.2.2 Cracking due to Stress Corrosion Cracking (SCC). . . . . . . . . . . . . . . . . . . . . . 3.4-63.4.2.2.3 Loss of Material Due to Pitting and Crevice Corrosion . . . . . . . . . . . . . . . . . . . 3.4-63.4.2.2.4 Quality Assurance for Aging Management of Nonsafety-Related Components 3.4-6

    3.4.2.3 Time-Limited Aging Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-6

    3.4.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-7

    3.5 STRUCTURES AND COMPONENT SUPPORTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-13.5.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1

    3.5.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1

    3.5.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1

    3.5.2.1.1 Containment Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-23.5.2.1.2 Water Control Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-33.5.2.1.3 Turbine Building, Process Facilities, and Yard Structures . . . . . . . . . . . . . . . . 3.5-43.5.2.1.4 Bulk Commodities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-5

    3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.5-63.5.2.2.1 PWR and BWR Containments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-6

    3.5.2.2.1.1 Cracking and Distortion due to Increased Stress Levels from Settlement; Reduction of Foundation Strength, and Cracking due to Differential Settlement and Erosion of Porous Concrete Subfoundations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-6

    3.5.2.2.1.2 Reduction of Strength and Modulus due to Elevated Temperature . . . 3.5-73.5.2.2.1.3 Loss of Material due to General, Pitting and Crevice Corrosion . . . . . 3.5-73.5.2.2.1.4 Loss of Prestress due to Relaxation, Shrinkage, Creep, and Elevated

    Temperature. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-83.5.2.2.1.5 Cumulative Fatigue Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-83.5.2.2.1.6 Cracking due to Stress Corrosion Cracking . . . . . . . . . . . . . . . . . . . . . 3.5-83.5.2.2.1.7 Loss of Material (Scaling, Spalling) and Cracking due to Freeze-Thaw3.5-93.5.2.2.1.8 Cracking due to Expansion from Reaction with Aggregate . . . . . . . . . 3.5-93.5.2.2.1.9 Increase in Porosity and Permeability due to Leaching of Calcium

    Hydroxide and Carbonation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-93.5.2.2.2 Safety-Related and Other Structures and Component Supports . . . . . . . . . . . 3.5-10

    3.5.2.2.2.1 Aging Management of Inaccessible Areas. . . . . . . . . . . . . . . . . . . . . . 3.5-103.5.2.2.2.2 Reduction of Strength and Modulus of Concrete Structures due to

    Elevated Temperature . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-123.5.2.2.2.3 Aging Management of Inaccessible Areas for Group 6 Structures . . . 3.5-12

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    3.5.2.2.2.4 Cracking due to Stress Corrosion Cracking and Loss of Material due to Pitting and Crevice Corrosion . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-13

    3.5.2.2.2.5 Cumulative Fatigue Damage due to Fatigue . . . . . . . . . . . . . . . . . . . . 3.5-133.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components 3.5-14

    3.5.2.3 Time-Limited Aging Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-14

    3.5.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-14

    3.6 ELECTRICAL AND INSTRUMENTATION AND CONTROLS . . . . . . . . . . . . . . . . . . . . 3.6-13.6.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-1

    3.6.2 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-1

    3.6.2.1 Materials, Environment, Aging Effects Requiring Management, and Aging Management Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-2

    3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1800 . . 3.6-43.6.2.2.1 Electrical Equipment Subject to Environmental Qualification . . . . . . . . . . . . . . 3.6-43.6.2.2.2 Degradation of Insulator Quality due to Presence of Any Salt Deposits and

    Surface Contamination, and Loss of Material due to Mechanical Wear . . . . . . 3.6-43.6.2.2.3 Loss of Material due to Wind Induced Abrasion and Fatigue, Loss of Conductor

    Strength due to Corrosion, and Increased Resistance of Connection due to Oxidation or Loss of Pre-load . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-5

    3.6.2.2.4 Quality Assurance for Aging Management of Nonsafety-Related Components 3.6-93.6.2.3 Time-Limited Aging Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-10

    3.6.3 Conclusion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-10

    4.0 TIME-LIMITED AGING ANALYSES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1

    4.1 IDENTIFICATION OF TIME-LIMITED AGING ANALYSES . . . . . . . . . . . . . . . . . . . . . . 4.1-14.1.1 Identification of TLAAs. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-2

    4.1.2 Identification of Exemptions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-3

    4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-14.2.1 Reactor Vessel Fluence . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-1

    4.2.2 Pressure-Temperature Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-2

    4.2.3 Upper Shelf Energy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-3

    4.2.4 Reactor Vessel Circumferential Weld Inspection Relief . . . . . . . . . . . . . . . . . . . . . . . 4.2-7

    4.2.5 Reactor Vessel Axial Weld Failure Probability. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-9

    4.2.6 Reactor Pressure Vessel Core Reflood Thermal Shock Analysis . . . . . . . . . . . . . . . . 4.2-10

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    4.3 METAL FATIGUE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-14.3.1 Class 1 Fatigue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-1

    4.3.1.1 Reactor Vessel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-44.3.1.2 Reactor Vessel Feedwater Nozzle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-64.3.1.3 Reactor Pressure Vessel Internals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-74.3.1.4 Reactor Recirculation Pumps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-84.3.1.5 Control Rod Drives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-94.3.1.6 Class 1 Piping . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-10

    4.3.2 Non-Class 1 Fatigue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-12

    4.3.2.1 Piping and In-Line Components. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-124.3.2.2 Non-Piping Components. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-12

    4.3.3 Effects of Reactor Water Environment on Fatigue Life . . . . . . . . . . . . . . . . . . . . . . . . 4.3-13

    4.4 ENVIRONMENTAL QUALIFICATION (EQ) OF ELECTRIC EQUIPMENT. . . . . . . . . . . 4.4-1

    4.5 CONCRETE CONTAINMENT TENDON PRESTRESS. . . . . . . . . . . . . . . . . . . . . . . . . . 4.5-1

    4.6 CONTAINMENT LINER PLATE, METAL CONTAINMENTS, AND PENETRATIONS FATIGUE ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.6-1

    4.6.1 Containment Liner Plate, Metal Containments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.6-1

    4.6.2 Containment Penetrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.6-2

    4.7 OTHER PLANT-SPECIFIC TLAA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.7-14.7.1 Erosion of the MSL Flow Restrictors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.7-1

    4.7.2 Determination of Intermediate High Energy Line Break Locations . . . . . . . . . . . . . . . 4.7-1

    4.7.3 Fluence Effects for the Reactor Vessel Internals. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.7-2

    4.8 REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.8-1

    LIST OF APPENDICESAppendix A: Updated Final Safety Analysis Report Supplement

    Appendix B: Aging Management Programs and Activities

    Appendix C: Response to BWRVIP Applicant Action Items

    Appendix D: Technical Specification Changes

    Appendix E: Applicant’s Environmental Report, Operating License Renewal Stage

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    LIST OF TABLES

    Table 2.0-1 Component Intended Functions: Abbreviations and Definitions . . . . . . . . . . . . . . . . . . 2.0-2

    Table 2.2-1-AMechanical Systems within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . 2.2-3

    Table 2.2-1-BPlant EIC Systems within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . . 2.2-9

    Table 2.2-2Mechanical Systems Not within the Scope of License Renewal . . . . . . . . . . . . . . . . . . 2.2-11

    Table 2.2-3Structures within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2-12

    Table 2.2-4Structures Not within the Scope of License Renewal . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2-14

    Table 2.3.1.2-ASystems with RCPB Components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-14

    Table 2.3.1.2-BRCPB LRA Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-15

    Table 2.3.1-1Reactor VesselComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-28

    Table 2.3.1-2Reactor Vessel InternalsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-31

    Table 2.3.1-3Reactor Coolant Pressure BoundaryComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-33

    Table 2.3.1-4-1Nuclear Boiler SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-34

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    Table 2.3.1-4-2Reactor Recirculation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-35

    Table 2.3.2-1Residual Heat Removal SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-60

    Table 2.3.2-2Low Pressure Core Spray SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-61

    Table 2.3.2-3High Pressure Core Spray SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-62

    Table 2.3.2-4Reactor Core Isolation Cooling SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-63

    Table 2.3.2-5Pressure Relief SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-64

    Table 2.3.2-6Standby Gas Treatment SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-65

    Table 2.3.2-7Containment Penetrations Components Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-66

    Table 2.3.2-8-1Residual Heat Removal SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-67

    Table 2.3.2-8-2Low Pressure Core Spray SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-68

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    Table 2.3.2-8-3High Pressure Core Spray SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-69

    Table 2.3.2-8-4Reactor Core Isolation Cooling SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-70

    Table 2.3.3-1Control Rod Drive SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-151

    Table 2.3.3-2Standby Liquid Control SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-152

    Table 2.3.3-3Suppression Pool Cleanup SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-153

    Table 2.3.3-4Leakage Detection and Control SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-154

    Table 2.3.3-5Combustible Gas Control SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-155

    Table 2.3.3-6Fuel Pool Cooling and Cleanup SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-156

    Table 2.3.3-7Standby Service Water SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-157

    Table 2.3.3-8Component Cooling Water SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-158

    Table 2.3.3-9Plant Service Water SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-159

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    Table 2.3.3-10Floor and Equipment Drainage SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-160

    Table 2.3.3-11Compressed Air SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-161

    Table 2.3.3-12Fire Protection – Water SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-162

    Table 2.3.3-13Fire Protection – Halon and CO2 SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-163

    Table 2.3.3-14Plant Chilled Water SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-164

    Table 2.3.3-15Standby Diesel Generator SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-165

    Table 2.3.3-16HPCS Diesel Generator SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-166

    Table 2.3.3-17Control Room HVAC SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-168

    Table 2.3.3-18HVAC SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-170

    Table 2.3.3-19-1CRD Hydraulic SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-171

    Table 2.3.3-19-2Standby Liquid Control SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-172

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    Table 2.3.3-19-3Process Radiation Monitoring SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-173

    Table 2.3.3-19-4Leak Detection SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-174

    Table 2.3.3-19-5MSIV – Leakage Control SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-175

    Table 2.3.3-19-6Combustible Gas Control SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-176

    Table 2.3.3-19-7Reactor Water Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-177

    Table 2.3.3-19-8Fuel Pool Cooling and Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-178

    Table 2.3.3-19-9CRD Maintenance Facility, Flush Tank Filter and Leak Test SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-179

    Table 2.3.3-19-10Containment Cooling SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-180

    Table 2.3.3-19-11Drywell Cooling SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-181

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    Table 2.3.3-19-12Containment Leak Rate Test SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-182

    Table 2.3.3-19-13Auxiliary Steam SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-183

    Table 2.3.3-19-14Makeup Water Treatment SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-184

    Table 2.3.3-19-15Process Sampling SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-185

    Table 2.3.3-19-16Standby Service Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-186

    Table 2.3.3-19-17Component Cooling Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-187

    Table 2.3.3-19-18Turbine Building Cooling Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-188

    Table 2.3.3-19-19Plant Service Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-189

    Table 2.3.3-19-20Floor and Equipment Drainage SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-190

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    Table 2.3.3-19-21Compressed Air SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-191

    Table 2.3.3-19-22Suppression Pool Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-192

    Table 2.3.3-19-23Fire Protection SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-193

    Table 2.3.3-19-24Domestic Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-194

    Table 2.3.3-19-25Plant Chilled Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-195

    Table 2.3.3-19-26Drywell Chilled Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-196

    Table 2.3.3-19-27Standby Diesel Generator SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-197

    Table 2.3.3-19-28HPCS Diesel Generator SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-198

    Table 2.3.3-19-29NobleChem™ Injection and Monitoring SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-199

  • Grand Gulf Nuclear StationLicense Renewal Application

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    Table 2.3.3-19-30Auxiliary Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-200

    Table 2.3.3-19-31Fuel Handling Area Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-201

    Table 2.3.3-19-32Turbine Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-202

    Table 2.3.3-19-33Diesel Generator Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-203

    Table 2.3.3-19-34Control Building HVAC SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-204

    Table 2.3.3-19-35Sanitary Waste SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-205

    Table 2.3.3-19-36Control Room HVAC SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-206

    Table 2.3.3-19-37Emergency Switchgear and Battery Rooms Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-207

    Table 2.3.4-1Condensate and Refueling Water Storage and Transfer SystemComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-229

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    Table 2.3.4-2-1 Feedwater Control SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-230

    Table 2.3.4-2-2Main and Reheat Steam SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-231

    Table 2.3.4-2-3Condensate and Feedwater SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-232

    Table 2.3.4-2-4Condensate Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-233

    Table 2.3.4-2-5Heater, Vents, and Drains SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-234

    Table 2.3.4-2-6 Main Turbine and AuxiliariesNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-235

    Table 2.3.4-2-7Main and RFP Turbine Seal Steam and Drain SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-236

    Table 2.3.4-2-8 Lube Oil SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-237

    Table 2.3.4-2-9Moisture Separator-Reheater Vents and Drains SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-238

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    Table 2.3.4-2-10Extraction Steam SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-239

    Table 2.3.4-2-11Turbine Bypass SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-240

    Table 2.3.4-2-12Generator SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-241

    Table 2.3.4-2-13Seal Oil SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-242

    Table 2.3.4-2-14Generator Primary Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-243

    Table 2.3.4-2-15Excitation SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-244

    Table 2.3.4-2-16Condenser Air Removal SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-245

    Table 2.3.4-2-17Low Temperature Off Gas SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-246

    Table 2.3.4-2-18Circulating Water SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-247

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    Table 2.3.4-2-19Condensate and Refueling Water Storage and Transfer SystemNonsafety-Related Components Affecting Safety-Related SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-248

    Table 2.4-1Containment BuildingComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-26

    Table 2.4-2Water Control StructuresComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-31

    Table 2.4-3Turbine Building, Process Facilities and Yard StructuresComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-33

    Table 2.4-4Bulk CommoditiesComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-36

    Table 2.5-1Electrical and Instrumentation and Control SystemsComponents Subject to Aging Management Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-5

    Table 3.0-1Service Environments for Mechanical Aging Management Reviews . . . . . . . . . . . . . . . 3.0-7

    Table 3.0-2Service Environments for Structural Aging Management Reviews . . . . . . . . . . . . . . . . 3.0-9

    Table 3.0-3Service Environments for Electrical Aging Management Reviews . . . . . . . . . . . . . . . . . 3.0-10

    Table 3.1.1Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of NUREG-1801. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-10

    Table 3.1.2-1Reactor VesselSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-32

    Table 3.1.2-2Reactor Vessel InternalsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-51

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    Table 3.1.2-3Reactor Coolant Pressure BoundarySummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-62

    Table 3.1.2-4-1Nuclear Boiler System Nonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-75

    Table 3.1.2-4-2Reactor Recirculation System Nonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-78

    Table 3.2.1Summary of Aging Management Programs for Engineered Safety FeaturesEvaluated in Chapter V of NUREG-1801 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-13

    Table 3.2.2-1Residual Heat Removal SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-34

    Table 3.2.2-2Low Pressure Core Spray SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-44

    Table 3.2.2-3High Pressure Core Spray SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-48

    Table 3.2.2-4Reactor Core Isolation Cooling SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-53

    Table 3.2.2-5Pressure Relief SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-63

    Table 3.2.2-6Standby Gas Treatment SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-67

    Table 3.2.2-7Containment PenetrationsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-71

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    Table 3.2.2-8-1Residual Heat Removal System Nonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-77

    Table 3.2.2-8-2Low Pressure Core Spray SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-80

    Table 3.2.2-8-3High Pressure Core Spray SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-81

    Table 3.2.2-8-4Reactor Core Isolation CoolingNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-83

    Table 3.3.1Summary of Aging Management Programs for the Auxiliary SystemsEvaluated in Chapter VII of NUREG-1801 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-27

    Table 3.3.2-1Control Rod Drive SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-73

    Table 3.3.2-2Standby Liquid Control SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-77

    Table 3.3.2-3Suppression Pool Makeup SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-81

    Table 3.3.2-4Leakage Detection and Control SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-83

    Table 3.3.2-5Combustible Gas Control SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-88

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    Table 3.3.2-6Fuel Pool Cooling and Cleanup SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-96

    Table 3.3.2-7Standby Service Water SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-101

    Table 3.3.2-8Component Cooling Water SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-107

    Table 3.3.2-9Plant Service Water SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-109

    Table 3.3.2-10Floor and Equipment DrainageSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-114

    Table 3.3.2-11Compressed Air SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-118

    Table 3.3.2-12Fire Protection – Water SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-123

    Table 3.3.2-13Fire Protection – Halon and CO2 SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-133

    Table 3.3.2-14Plant Chilled Water SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-138

    Table 3.3.2-15Standby Diesel Generator SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-146

    Table 3.3.2-16HPCS Diesel Generator SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-166

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    Table 3.3.2-17Control Room Heating, Ventilation, and Air Conditioning SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-185

    Table 3.3.2-18Heating, Ventilation and Air Conditioning SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-194

    Table 3.3.2-19-1CRD Hydraulic SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-200

    Table 3.3.2-19-2Standby Liquid Control SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-206

    Table 3.3.2-19-3Process Radiation Monitoring SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-209

    Table 3.3.2-19-4Leak Detection SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-212

    Table 3.3.2-19-5MSIV – Leakage Control SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-215

    Table 3.3.2-19-6Combustible Gas Control SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-217

    Table 3.3.2-19-7Reactor Water Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-223

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    Table 3.3.2-19-8Fuel Pool Cooling and Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-229

    Table 3.3.2-19-9CRD Maintenance Facility, Flush Tank Filter and Leak Test SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-234

    Table 3.3.2-19-10Containment Cooling SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-236

    Table 3.3.2-19-11Drywell Cooling SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-240

    Table 3.3.2-19-12Containment Leak Rate Test SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-243

    Table 3.3.2-19-13Auxiliary Steam SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-245

    Table 3.3.2-19-14Make Up Water Treatment SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-247

    Table 3.3.2-19-15Process Sampling SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-250

    Table 3.3.2-19-16Standby Service Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-256

  • Grand Gulf Nuclear StationLicense Renewal Application

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    Table 3.3.2-19-17Component Cooling Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-258

    Table 3.3.2-19-18Turbine Building Cooling Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-263

    Table 3.3.2-19-19Plant Service Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-269

    Table 3.3.2-19-20Floor and Equipment Drainage SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-272

    Table 3.3.2-19-21Compressed Air SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-278

    Table 3.3.2-19-22Suppression Pool Cleanup SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-282

    Table 3.3.2-19-23Fire Protection SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-284

    Table 3.3.2-19-24Domestic Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-286

    Table 3.3.2-19-25Plant Chilled Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-290

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    Table 3.3.2-19-26Drywell Chilled Water SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-295

    Table 3.3.2-19-27Standby Diesel Generator SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-300

    Table 3.3.2-19-28HPCS Diesel Generator SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-304

    Table 3.3.2-19-29NobleChem Injection and Monitoring SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-309

    Table 3.3.2-19-30Auxiliary Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-311

    Table 3.3.2-19-31Fuel Handling Area Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-313

    Table 3.3.2-19-32Turbine Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-316

    Table 3.3.2-19-33Diesel Generator Building Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-319

    Table 3.3.2-19-34Control Building HVAC SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-320

  • Grand Gulf Nuclear StationLicense Renewal Application

    xxxix

    Table 3.3.2-19-35Sanitary Waste SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-324

    Table 3.3.2-19-36Control Room HVAC SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-326

    Table 3.3.2-19-37Emergency Switchgear and Battery Rooms Ventilation SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-329

    Table 3.4.1Summary of Aging Management Programs for the Steam and Power Conversion SystemsEvaluated in Chapter VIII of NUREG-1801. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-8

    Table 3.4.2-1Condensate and Refueling Water Storage and Transfer SystemSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-27

    Table 3.4.2-2-1Feedwater Control SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-34

    Table 3.4.2-2-2Main and Reheat Steam SystemNonsafety-Related Components Affecting Safety-Related SystemsSummary of Aging Management Evaluation . . . . . . . . . . . . . . . . . . . . . .