Brunswick Steam Electric Plant License Renewal Application Brunswick Steam Electric Plant License Renewal Application Administrative Information PREFACE The following describes the content of the BSEP License Renewal Application. Chapter 1 provides the administrative information required by 10 CFR 54.17 and 10 CFR 54.19. Chapter 2 describes and justifies the methodology used to determine the systems, structures, and components within the scope of license renewal and the structures and components subject to an aging management review. The results of applying the scoping methodology are provided in Tables 2.2-1, 2.2-2, and 2.2-3. These tables provide listings of the mechanical systems, structures, and electrical/instrumentation and control systems within the scope of license renewal. Chapter 2 also provides a description of the systems and structures and their intended functions and tables identifying the system and structure components/commodities requiring aging management review and their intended functions. The descriptions also identify the applicable license renewal boundary drawings for mechanical systems. The drawings are included in a separate submittal. A discussion of the NRC Interim Staff Guidance topics for license renewal is included as a subsection of Chapter 2. Chapter 3 describes the results of aging management reviews of structures and components requiring aging management review. Chapter 3 is divided into six sections that address the areas of: (1) Reactor Vessel, Internals, and Reactor Coolant System, (2) Engineered Safety Features, (3) Auxiliary Systems, (4) Steam and Power Conversion Systems, (5) Containments, Structures, and Component Supports, and (6) Electrical and Instrumentation and Controls. The tables in Chapter 3 provide a summary of information concerning aging effects requiring management and applicable aging management programs for structures and components. The information presented in the tables is based on industry guidance for format and content of applications that rely on NUREG-1800, “Standard Review Plan for the Review of License Renewal Applications for Nuclear Power Plants,” U. S. Nuclear Regulatory Commission, April 2001, (the SRP-LR). The tables provide a discussion of the applicability of the component commodity groups to BSEP and information regarding the degree to which proposed aging management programs are consistent with those recommended in NUREG-1801, “Generic Aging Lessons Learned (GALL),” U.S. Nuclear Regulatory Commission, April 2001, (the GALL Report). Chapter 4 addresses Time-Limited Aging Analyses, as defined by 10 CFR 54.3, and includes the identification of the component or subject, and an explanation of the time- dependent aspects of the calculation or analysis. Chapter 4 demonstrates whether (1) the analyses remain valid for the period of extended operation, or (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 Preface Page i Brunswick Steam Electric Plant License Renewal Application Administrative Information operation. Chapter 4 also provides the results of a review of exemptions issued pursuant to 10 CFR 50.12 to determine if any involve a Time-Limited Aging Analysis. Appendix A, Updated Final Safety Analysis Report Supplement, provides a summary description of the programs and activities for managing the effects of aging during 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. Appendix B, Aging Management Programs, describes the programs and activities that are credited to assure the effects of aging of components and structures will be managed such that they will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation. Appendix B also addresses programs that are credited in the evaluation of Time-Limited Aging Analyses. Appendix C is not used. 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. A supplement to the Environmental Report is provided in Appendix E, entitled, “Applicant’s Environmental Report – Operating License Renewal Stage.” The information in Chapter 2, Chapter 3, and Appendix B fulfills the requirements in 10 CFR 54.21(a). Section 1.4 discusses how the requirements of 10 CFR 54.21(b) will be met. The information in Chapter 4 fulfills the requirements in 10 CFR 54.21(c). The information in Appendix A and Appendix D fulfills the requirements in 10 CFR 54.21(d) and 10 CFR 54.22, respectively. Appendix E provides the environmental information required by 10 CFR 54.23. Preface Page ii Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS AC Alternating Current ACI American Concrete Institute ACSR Aluminum Conductor Steel Reinforced ADS Automatic Depressurization System AERM Aging Effects Requiring Management AFFF Aqueous Fire Fighting Foam AISC American Institute of Steel Construction AISI American Iron and Steel Institute AMP Aging Management Program AMR Aging Management Review ANSI American National Standards Institute AOG Augmented Off-Gas/Auxiliary Off-Gas AOO Anticipated Operational Occurrence API American Petroleum Institute APRM Average Power Range Monitor ARI Alternate Rod Injection/Alternate Rod Insertion ARM Area Radiation Monitor ART Adjusted Reference Temperature ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers AST Alternative Source Term ASTM American Society for Testing and Materials ATWS Anticipated Transient Without Scram ATWS-RPT Anticipated Transient Without Scram-Recirculation Pump Trip AWS American Welding Society AWWA American Water Works Association B&PV Boiler and Pressure Vessel BNP Brunswick Nuclear Plant BSEP Brunswick Steam Electric Plant BTP Branch Technical Position BWR Boiling Water Reactor BWROG Boiling Water Reactor Owners Group BWRVIP Boiling Water Reactor Vessel and Internals Program CAC Containment Atmospheric Control CAD Containment Atmosphere Dilution CAP Corrective Action Program CB Control Board CCW Component Cooling Water/Closed Cooling Water CDD Condensate Deep Bed Demineralizer CF Chemistry Factor CFD Condensate Filter Demineralizer CHRS Containment Heat Removal System CL Chlorination CLB Current Licensing Basis CMAA Crane Manufacturers Association of America CP&L Carolina Power & Light Company, a Progress Energy Company Preface Page iii Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS CRD Control Rod Drive CRDH Control Rod Drive Housing CRDM Control Rod Drive Mechanism CS Core Spray/Carbon Steel CSCS Core Standby Cooling System CST Condensate Storage Tank CW Circulating Water CUF Cumulative Usage Factor DBA Design Basis Accident DBE Design Basis Earthquake DC Direct Current DG Diesel Generator DGB Diesel Generator Building DOR Division of Operating Reactors (NRC) D/P Differential Pressure DSCSS Drywell and Suppression Chamber Spray System DWT Demineralized Water Tank EAF Environmentally Assisted Fatigue E&RC Environmental and Radiation Control ECC Emergency Core Cooling ECCS Emergency Core Cooling System EDB (PassPort) Equipment Database EFPY Effective Full Power Years EHC Electro-Hydraulic Control EMA Equivalent Margin Analysis EOF Emergency Operations Facility EPA Electrical Penetration Assembly EPRI Electric Power Research Institute EPU Extended Power Uprate EQ Environmental Qualification EQML Environmental Qualification Master List ER Environmental Report ESF Engineered Safety Features FAC Flow Accelerated Corrosion Fen Environmental Fatigue Factor FERC Federal Energy Regulatory Commission FHA Fire Hazards Analysis FO Fuel Oil FOL Facility Operating License FOST Fuel Oil Storage Tank FP Fire Protection FPP Fire Protection Program FSAR Final Safety Analysis Report FSER Final Safety Evaluation Report FW Feedwater GALL Generic Aging Lessons Learned (the GALL Report is NUREG-1801) GDC General Design Criteria Preface Page iv Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS GE General Electric GL Generic Letter GSI Generic Safety Issue HCU Hydraulic Control Unit HD Heater Drains HDFSS High Density Fuel Storage System HELB High Energy Line Break HEPA High Efficiency Particulate Air HMWPE High Molecular Weight Polyethylene HP High Pressure HPCI High Pressure Coolant Injection HPCS High Pressure Core Spray (not an applicable system for BSEP) HVAC Heating, Ventilating, and Air Conditioning HWC Hydrogen Water Chemistry IA Instrument Air IAN Non-interruptible Instrument Air IASCC Irradiation Assisted Stress Corrosion Cracking I&C Instrumentation and Control ID Inside Diameter IE Inspection and Enforcement (former NRC Office of Inspection and Enforcement) IEEE Institute Of Electrical And Electronic Engineers IGSCC Intergranular Stress Corrosion Cracking ILRT Integrated Leak Rate Test (Containment Type A Test) IN Information Notice INPO Institute Of Nuclear Power Operations IPCEA Insulated Power Cable Engineers Association IPA Integrated Plant Assessment (10 CFR 54.21(a)) IR Insulation Resistance IRM Intermediate Range Monitor ISG Interim (NRC) Staff Guidance ISI In-Service Inspection KV Kilovolt LBB Leak-Before-Break LER Licensee Event Report LO Lubricating Oil LOCA Loss of Coolant Accident LP Low Presure LPCI Low Pressure Coolant Injection LPCS Low Pressure Core Spray LPRM Local Power Range Monitor LR License Renewal LRA License Renewal Application MCB Main Control Board MeV Million Electron Volts MIC Microbiologically Induced Corrosion MOD Motor Operated Disconnect MS Main Steam Preface Page v Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS MSIV/LCS Main Steam Isolation Valve/ Leakage Control System MSL Main Steam Line/Mean Sea Level MSLB Main Steam Line Break MSR Moisture Separator Reheater MVD Miscellaneous Vents and Drains MWTS Makeup Water Treatment System NDE Nondestructive Examination NDTT Nil-Ductility Transition Temperature NEI Nuclear Energy Institute NFPA National Fire Protection Association Ni Nickel NMS Neutron Monitoring System NPS Nominal Pipe Size NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System NUREG Designation of publications prepared by the NRC staff OE Operating Experience OLTP Original Licensed Thermal Power OPRM Oscillation Power Range Monitor PASS Post-Accident Sampling System PBDS Period Based Detection System PCB Power Circuit Breaker PCS Primary Containment Structure PEC Progress Energy Carolinas PFM Probabilistic Fracture Mechanics pH Concentration of Hydrogen Ions PM Preventive Maintenance PNS Pneumatic Nitrogen System PORV Power-Operated Relief Valve PRM Process Radiation Monitoring P-T Presure-Temperature PTS Pressurized Thermal Shock PVC Polyvinyl Chloride PWS Potable Water System QA Quality Assurance RAI Request for Additional Information RBCCW Reactor Building Closed Cooling Water RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling RCPB Reactor Coolant Pressure Boundary RFP Reactor Feedwater Pump RG Regulatory Guide RHR Residual Heat Removal RI Risk Informed RMCS Reactor Manual Control System RMS Radiation Monitoring System RNA Reactor Non-interruptible Air Preface Page vi Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS RPIS Rod Position Information System RPS Reactor Protection System RPV Reactor Pressure Vessel RTNDT Reference Temperature, Nil-Ductility Transition RTNDT(U) Reference Temperature, Nil-Ductility Transition (Unirradiated) RVI Reactor Vessel Internals RWCU Reactor Water Cleanup System RWM Rod Worth Minimizer RXS Reactor Building Sampling System SA Service Air SAT Startup Auxiliary Transformer SBO Station Blackout SC Structure/Component (10 CFR 54.21(a)(1)), also Suppression Chamber SCC Stress Corrosion Cracking SCW Scren Wash Water SDV Scram Discharge Volume SE Safety Evaluation SER Safety Evaluation Report SFP Spent Fuel Pool SGTS Standby Gas Treatment System SI Safety Injection SJAE Steam Jet Air Ejector SLC Standby Liquid Control SLMS Stator Leak Monitoring System SPDS Safety Parameter Display System SR Safety Related SRM Source Range Monitoring SRP Standard Review Plan SRP-LR Standard Review Plan for License Renewal SRV Safety Relief Valve SS Stainless Steel SSC Systems, Structures, and Components (10CFR 54.4(a)) SSE Safe Shutdown Earthquake SW Service Water TAC Technical Assignment Control (internal NRC work management tool) TASCS Thermal Stratification, Cycling, and Striping TB Turbine Building TBCCW Turbine Building Closed Cooling Water TGSCC Trans-Granular Stress Corrosion Cracking TID Total Integrated Dose TIP Traversing Incore Probe TLAA Time-Limited Aging Analysis TSC Technical Support Center TT Thermal Transients UAT Unit Auxiliary Transformer UFSAR Updated Final Safety Analysis Report USAS United States of America Standards Preface Page vii Brunswick Steam Electric Plant License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS USE Upper Shelf Energy UUSE Unirradiated Upper Shelf Energy UT Ultrasonic Test VAC Volts alternating current VDC Volts direct current VFLD Vessel Flange Leak Detection XLPE Cros-linked Polyethylene XLPO Cross-linked Polyolefin WANO World Association of Nuclear Operators Preface Page viii