Susquehanna Steam Electric Station Units 1 and 2 License Renewal

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Susquehanna Steam Electric Station Units 1 and 2 License Renewal LICENSE RENEWAL APPLICATION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 Susquehanna Steam Electric Station Units 1 & 2 License Renewal Application Administrative Information PREFACE The following describes the content of the Susquehanna Steam Electric Station (SSES) License Renewal Application (LRA). Section 1 provides the administrative information required by 10 CFR 54.17 and 10 CFR 54.19. Section 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. Section 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 with the submittal, but are not part of the formal application. A discussion of the Nuclear Regulatory Commission (NRC) Interim Staff Guidance topics for license renewal is included in Section 2.1.3. Section 3 describes the results of aging management reviews of structures and components requiring aging management review. Section 3 is divided into six sections that address the areas of: (3.1) Reactor Vessel, Internals, and Reactor Coolant System, (3.2) Engineered Safety Features, (3.3) Auxiliary Systems, (3.4) Steam and Power Conversion Systems, (3.5) Containments, Structures, and Component Supports, and (3.6) 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 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, Revision 1, (the SRP-LR). The tables provide a discussion of the applicability of the component commodity groups to SSES 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, Revision 1, (the GALL Report). Section 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. Section 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 September 2006 Susquehanna Steam Electric Station Units 1 & 2 License Renewal Application Administrative Information operation. Section 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, 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. In addition, Appendix A contains a listing of commitments associated with license renewal. 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, Response to BWRVIP Applicant Action Items, provides the requested responses to applicant action items contained in the NRC safety evaluation reports associated with NRC-approved Boiling Water Reactor Vessel and Internals Program reports. 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 Section 2, Section 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 Section 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 September 2006 Susquehanna Steam Electric Station Units 1 & 2 License Renewal Application Administrative Information ACRONYMS AND ABBREVIATIONS Acronym or Abbreviation Description AAI Applicant Action Item AC Alternating Current ACI American Concrete Institute ACSR Aluminum Conductor Steel Reinforced ADS Automatic Depressurization System AEM Aging Effect / Mechanism AHU Air Handling Unit AISC American Institute of Steel Construction aka also known as AMP Aging Management Program AMR Aging Management Review ANSI American National Standards Institute APRM Average Power Range Monitor AR Action Request ARI Alternate Rod Injection/Alternate Rod Insertion ART Adjusted Reference Temperature ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers AST Alternate Source Term ASTM American Society for Testing and Materials ATWS Anticipated Transient Without Scram B&PV Boiler and Pressure Vessel BTP APCSB Branch Technical Position Auxiliary Power Conversion Systems Branch BWR Boiling Water Reactor BWRVIP Boiling Water Reactor Vessel and Internals Program CASS Cast Austenitic Stainless Steel CFR Code of Federal Regulations CIG Containment Instrument Gas CIV Combined Intermediate Valve CLB Current Licensing Basis CM Condition Monitoring CMAA Crane Manufacturers Association of America CPX Component Maintenance System CR Condition Report CRD Control Rod Drive Preface Page iii September 2006 Susquehanna Steam Electric Station Units 1 & 2 License Renewal Application Administrative Information Acronym or Abbreviation Description CRDH Control Rod Drive Hydraulics CRDRL Control Rod Drive Return Line CREOASS Control Room Emergency Outside Air Supply System CS Carbon Steel CSS Core Support Structures CSCW Control Structure Chilled Water CST Condensate Storage Tank CWST Clarified Water Storage Tank CUF Cumulative Usage Factor DAR Design Assessment Report DBA Design Basis Accident DBD Design Basis Document DC Direct Current DG Diesel Generator DOR Division of Operating Reactors (NRC) DOT Department of Transportation DP Differential Pressure ECCS Emergency Core Cooling System EFPY Effective Full Power Years EHL Emergency Heat Load EPRI Electric Power Research Institute EPRI-MRP Electric Power Research Institute Materials Reliability Program EPU Extended Power Uprate EQ Environmental Qualification ESF Engineered Safety Features ESS Engineered Safeguard System ESSW Engineered Safeguards Service Water ESW Emergency Service Water FAC Flow Accelerated Corrosion FB Fire Barrier Fen Environmental Fatigue Factor FERC Federal Energy Regulatory Commission FP Fire Protection FPCCU Fuel Pool Cooling and Cleanup System FPRR Fire Protection Review Report FSAR Final Safety Analysis Report FSER Final Safety Evaluation Report FW Feedwater GALL Generic Aging Lessons Learned (the GALL Report is NUREG-1801) Preface Page iv September 2006 Susquehanna Steam Electric Station Units 1 & 2 License Renewal Application Administrative Information Acronym or Abbreviation Description GE General Electric GL Generic Letter GRRCCW Gaseous Radwaste Recomber Closed Cooling Water System GSI Generic Safety Issue HAZ Heat-Affected Zone HCU Hydraulic Control Unit HELB High Energy Line Break HEPA High Efficiency Particulate Air HP High Pressure HPCI High Pressure Coolant Injection HVAC Heating, Ventilating, and Air Conditioning HWC Hydrogen Water Chemistry IASCC Irradiation Assisted Stress Corrosion Cracking I&C Instrumentation and Control ICTM Isolated Condenser Treatment Method ID Inside Diameter IEEE Institute Of Electrical And Electronic Engineers IGA Intergranular Attack IGSCC Intergranular Stress Corrosion Cracking IN Information Notice INPO Institute Of Nuclear Power Operations IP Intermediate Pressure IPA Integrated Plant Assessment (10 CFR 54.21(a)) IPE Individual Plant Evaluation IPEEE Individual Plant Evaluation of External Events IR Insulation Resistance IRM Intermediate Range Monitor ISFSI Independent Spent Fuel Storage Installation ISG Interim (NRC) Staff Guidance ISI In-Service Inspection ISO Independent System Operator ISP Integrated Surveillance Program kV Kilo-volt LLRWHF Low Level Radwaste Holding Facility LOCA Loss of Coolant Accident LP Low Pressure LPCI
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