ML032820056
| ML032820056 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/31/2003 |
| From: | Kuo P NRC/NRR/DRIP/RLEP |
| To: | Mecredy R Rochester Gas & Electric Corp |
| Kuo PT, NRR/DRIP/RLEP, 415-1183 | |
| Shared Package | |
| ML032820021 | List: |
| References | |
| Download: ML032820056 (6) | |
Text
-v-Table of Contents Abstract................................................................. -iii-Table of Contents......................................................... -v-Abbreviations............................................................ -x-1 INTRODUCTION AND GENERAL DISCUSSION............................... 1-1 1.1 Introduction..................................................... 1-1 1.2 License Renewal Background...................................... 1-2 1.2.1 Safety Reviews.......................................... 1-3 1.2.2 Environmental Reviews.................................... 1-4 1.3 Principal Review Matters.......................................... 1-5 1.3.1 Westinghouse Topical Reports............................... 1-6 1.4 Interim Staff Guidance............................................ 1-7 1.5 Summary of Open Items........................................... 1-9 1.6 Summary of Confirmatory Items.................................... 1-15 1.7 Summary of Proposed License Conditions............................ 1-18 2 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW, AND IMPLEMENTATION RESULTS............................................................. 2-1 2.1 Scoping and Screening Methodology................................. 2-2 2.2 Plant-Level Scoping Results....................................... 2-27 2.2.1 Summary of Technical Information in the Application............. 2-27 2.2.2 Staff Evaluation......................................... 2-27 2.2.3 Evaluation Findings...................................... 2-30 2.3 Scoping and Screening Results: Mechanical Systems
.................. 2-31 2.3.1 Reactor Systems........................................ 2-33 2.3.1.1 Reactor Coolant (Class 1).......................... 2-33 2.3.1.2 Reactor Vessel.................................. 2-36 2.3.1.3 Reactor Vessel Internals........................... 2-38 2.3.1.4 Pressurizer..................................... 2-40 2.3.1.5 Steam Generators................................ 2-41 2.3.1.6 Reactor Coolant (Non-Class 1....................... 2-43 2.3.1.7 Evaluation Findings............................... 2-44 2.3.2 Engineered Safety Features Systems........................ 2-45 2.3.2.1 Safety Injection.................................. 2-45 2.3.2.2 Containment Spray............................... 2-47 2.3.2.3 Residual Heat Removal........................... 2-48 2.3.2.4 Containment Hydrogen Detectors and Recombiners...... 2-50 2.3.2.5 Containment Isolation Components................... 2-52 2.3.2.6 Evaluation Findings............................... 2-54 2.3.3 Auxiliary Systems........................................ 2-54 2.3.3.1 Chemical and Volume Control....................... 2-55 2.3.3.2 Component Cooling Water......................... 2-56 2.3.3.3 Spent Fuel Pool Cooling and Fuel Storage............. 2-60
-vi-2.3.3.4 Waste Disposal.................................. 2-64 2.3.3.5 Service Water................................... 2-65 2.3.3.7 Heating Steam................................... 2-75 2.3.3.8 Emergency Power................................ 2-77 2.3.3.9 Containment Ventilation............................ 2-79 2.3.3.10 Essential Ventilation............................. 2-81 2.3.3.11 Cranes, Hoists, and Lifting Devices.................. 2-89 2.3.3.12 Treated Water.................................. 2-90 2.3.3.13 Radiation Monitoring -- Mechanical.................. 2-93 2.3.3.14 Circulating Water................................ 2-96 2.3.3.15 Chilled Water................................... 2-97 2.3.3.16 Fuel Handling
.................................. 2-98 2.3.3.17 Plant Sampling
................................ 2-100 2.3.3.18 Plant Air...................................... 2-102 2.3.3.19 Nonessential Ventilation......................... 2-104 2.3.3.20 Site Service and Facility Support................... 2-106 2.3.3.21 Evaluation Findings............................. 2-107 2.3.4 Steam and Power Conversion Systems...................... 2-107 2.3.4.1 Main and Auxiliary Steam......................... 2-107 2.3.4.2 Feedwater and Condensate
....................... 2-110 2.3.4.3 Auxiliary Feedwater.............................. 2-112 2.3.4.4 Turbine Generator and Supporting Systems........... 2-115 2.3.4.5 Evaluation Findings.............................. 2-117 2.4 Scoping and Screening Results: Structures.......................... 2-118 2.4.1 Containment Structures.................................. 2-118 2.4.1.1 Summary of Technical Information in the Application.... 2-118 2.4.1.2 Staff Evaluation................................. 2-120 2.4.1.3 Conclusions.................................... 2-122 2.4.2 Essential Buildings and Yard Structures
..................... 2-122 2.4.2.1 Auxiliary Building................................ 2-122 2.4.2.2 Intermediate Building............................. 2-126 2.4.2.3 Turbine Building................................. 2-129 2.4.2.4 Diesel Building.................................. 2-131 2.4.2.5 Control Building................................. 2-134 2.4.2.6 All Volatile Water Treatment Building................ 2-137 2.4.2.7 Screenhouse Building............................ 2-139 2.4.2.8 Standby Auxiliary Feedwater Building................ 2-142 2.4.2.9 Service Building................................. 2-144 2.4.2.10 Cable Tunnel.................................. 2-146 2.4.2.11 Essential Yard Structures........................ 2-148 2.4.2.12 Component Supports Commodity Group............. 2-150 2.4.3 Nonessential Buildings and Yard Structures
.................. 2-154 2.4.3.1 Summary of Technical Information in the Application.... 2-154 2.4.3.2 Staff Evaluation................................. 2-155 2.4.3.3 Conclusions.................................... 2-155 2.4.4 Evaluation Findings..................................... 2-155 2.5.1 Commodity Group Discussion............................. 2-156 2.5.1.1 Medium Voltage Insulated Cables and Connectors...... 2-156
-vii-2.5.1.2 Low Voltage Insulated Cables and Connectors......... 2-160 2.5.1.3 Electrical Penetration Assemblies................... 2-161 2.5.1.4 Electrical Phase Bus............................. 2-162 2.5.1.5 Switchgear Bus................................. 2-164 2.5.1.6 Transmission Conductors......................... 2-166 2.5.1.7 Uninsulated Ground Connectors.................... 2-169 2.5.1.8 High Voltage Insulators.
.......................... 2-170 2.5.2 Evaluation Findings..................................... 2-172 3 AGING MANAGEMENT REVIEW........................................... 3-1 3.0.1 The GALL Format for the LRA............................... 3-2 3.0.2 The Staffs Review Process................................. 3-3 3.0.3 Aging Management Programs
............................... 3-4 3.0.3.1 Water Chemistry Control Program..................... 3-8 3.0.3.2 ASME Section XI, Subsection IWB, IWC, and IWD Inservice Inspection Program................................. 3-9 3.0.3.3 Bolting Integrity Program........................... 3-11 3.0.3.4 Boric Acid Corrosion Program....................... 3-13 3.0.3.5 Closed-Cycle (Component) Cooling Water System Program 3-15 3.0.3.6 Flow-Accelerated Corrosion......................... 3-18 3.0.3.7 One-Time Inspection Program....................... 3-19 3.0.3.8 Periodic Surveillance and Preventive Maintenance Program 3-22 3.0.3.9 Selective Leaching of Materials...................... 3-28 3.0.3.10 Structures Monitoring
............................ 3-30 3.0.3.11 Systems Monitoring Program
...................... 3-31 3.0.3.12 Existing and GALL Aging Management Programs not Credited for License Renewal.............................. 3-33 3.0.3.13 Evaluation Findings.............................. 3-35 3.0.4 R.E. Ginna Quality Assurance Program Attributes Integral to Aging Management Programs.................................. 3-36 3.0.4.1 Summary of Technical Information in Application........ 3-36 3.0.4.2 Staff Evaluation.................................. 3-36 3.0.4.3 Conclusion...................................... 3-38 3.1 Reactor Coolant Systems......................................... 3-39 3.1.1 Summary of Technical Information in the Application............. 3-39 3.1.2 Staff Evaluation......................................... 3-40 3.1.2.1 Aging Management Evaluations in the GALL Report That Are Relied On For License Renewal, Which Do Not Require Further Evaluation....................................... 3-46 3.1.2.2 Aging Management Evaluations in the GALL Report That Are Relied On For License Renewal, For Which GALL Recommends Further Evaluation................................. 3-47 3.1.2.3 Aging Management Programs for Reactor Coolant System Components..................................... 3-57 3.1.2.4 Aging Management Review of Plant-Specific Components. 3-76 3.1.3 Evaluation Findings...................................... 3-90 3.2 Engineered Safety Features Systems
............................... 3-90 3.2.1 Summary of Technical Information in the Application............. 3-91
-viii-3.2.2 Staff Evaluation......................................... 3-91 3.2.2.1 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, Which Do Not Require Further Evaluation...................................... 3-94 3.2.2.2 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation................................ 3-95 3.2.2.3 Aging Management Programs for Engineered Safety Features Systems Component.............................. 3-97 3.2.2.4 AMR of Plant-Specific Engineered Safety Features Systems Components.................................... 3-98 3.2.3 Evaluation Findings..................................... 3-112 3.3 Auxiliary Systems.............................................. 3-112 3.3.1 Summary of Technical Information in the Application
.................................................... 3-113 3.3.2 Staff Evaluation........................................ 3-113 3.3.2.1 Aging Management Evaluations in the GALL Report That Are Relied On For License Renewal, Which Do Not Require Further Evaluation..................................... 3-118 3.3.2.2 Aging Management Evaluations in the GALL Report That Are Relied On For License Renewal, For Which GALL Recommends Further Evaluation............................... 3-119 3.3.2.3 Aging Management Programs (System-Specific)....... 3-126 3.3.2.4 Aging Management Reviews of Plant-Specific Components
.............................................. 3-143 3.3.2.5 General AMR Issues............................. 3-183 3.3.3 Evaluation Findings..................................... 3-190 3.4 Steam and Power Conversion Systems............................. 3-190 3.4.1 Summary of Technical Information in the Application............ 3-191 3.4.2 Staff Evaluation........................................ 3-191 3.4.2.1 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, Which Do Not Require Further Evaluation..................................... 3-193 3.4.2.2 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation............................... 3-194 3.4.2.3 Aging Management Programs for Steam and Power Conversion Systems....................................... 3-198 3.4.2.4 Aging Management of Plant-Specific Components...... 3-199 3.4.3 Evaluation Findings...................................... 3-217 3.5 Containment, Structures, and Component Supports.................... 3-217 3.5.1 Summary of Technical Information in the Application............ 3-217 3.5.2 Staff Evaluation........................................ 3-218 3.5.2.1 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, Which Do Not Require Further Evaluation..................................... 3-223
-ix-3.5.2.2 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation............................... 3-223 3.5.2.3 Aging Management Programs for Containment, Structures, and Component Supports............................. 3-233 3.5.2.4 Aging Management Review of Plant-Specific Structures and Structural Components........................... 3-243 3.5.3 Evaluation Findings..................................... 3-259 3.6 Electrical and Instrumentation and Controls.......................... 3-259 3.6.1 Summary of Technical Information in the Application............ 3-260 3.6.2 Staff Evaluation........................................ 3-260 3.6.2.1 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, Which Do Not Require Further Evaluation..................................... 3-263 3.6.2.2 Aging Management Evaluations in the GALL Report That Are Relied on for License Renewal, For Which GALL Recommends Further Evaluation............................... 3-263 3.6.2.3 Aging Management Programs for Electrical and I&C Components
.............................................. 3-263 3.6.2.4 Aging Management of Plant-Specific Components...... 3-271 3.6.3 Evaluation Findings..................................... 3-284 4 TIME-LIMITED AGING ANALYSES......................................... 4-1 4.1 Identification of Time-Limited Aging Analyses
.......................... 4-1 4.1.1 Summary of Technical Information in the Application.............. 4-1 4.1.2 Staff Evaluation.......................................... 4-1 4.1.3 Conclusions............................................. 4-3 4.2 Reactor Vessel Neutron Embrittlement................................ 4-3 4.2.1 Reactor Vessel Upper-Shelf Energy.......................... 4-3 4.2.1.1 Technical Information the Application.................. 4-4 4.2.1.2 Staff Evaluation................................... 4-4 4.2.2 Pressurized Thermal Shock................................. 4-5 4.2.2.1 Technical Information in the Application................ 4-6 4.2.2.2 Staff Evaluation................................... 4-6 4.2.3 Plant Heatup/Cooldown (Pressure/Temperature) Curves........... 4-7 4.2.3.1 Technical Information in the Application................ 4-7 4.2.3.2 Staff Evaluation................................... 4-8 4.2.4 UFSAR Supplement....................................... 4-8 4.2.5 Conclusions............................................. 4-8 4.3 Metal Fatigue................................................... 4-8 4.3.1 Summary of Technical Information in the Application.............. 4-8 4.3.1.1 ASME Boiler and Pressure Vessel Code,Section III, Class 1
................................................ 4-8 4.3.1.2 ANSI B31.1 Piping................................. 4-9 4.3.1.3 Reactor Vessel Underclad Cracking................... 4-9 4.3.1.4 Accumulator Check Valves.......................... 4-9 4.3.1.5 Reactor Vessel Nozzle-to-Vessel Weld Defect........... 4-9 4.3.1.6 Pressurizer Fracture Mechanics Analysis.............. 4-10
-x-4.3.1.7 Environmentally Assisted Fatigue Evaluation
........... 4-10 4.3.2 Staff Evaluation......................................... 4-11 4.3.2.1 ASME Boiler and Pressure Vessel Code,Section III, Class
............................................... 4-11 4.3.2.2 ANSI B31.1 Piping................................ 4-13 4.3.2.3 Reactor Vessel Underclad Cracking.................. 4-14 4.3.2.4 Accumulator Check Valves......................... 4-15 4.3.2.5 Reactor Vessel Nozzle-to-Vessel Weld Defect.......... 4-15 4.3.2.6 Pressurizer Fracture Mechanics Analysis.............. 4-16 4.3.2.7 Environmentally Assisted Fatigue Evaluation
........... 4-16 4.3.3 Conclusions............................................ 4-19 4.4 Environmental Qualification of Electrical Equipment..................... 4-19 4.4.1 Summary of Technical Information in the Application............. 4-20 4.4.2 Staff Evaluation......................................... 4-21 4.4.3 Conclusions............................................ 4-22 4.5 Concrete Containment Tendon Prestress............................. 4-23 4.5.1 Summary of Information in the Application..................... 4-23 4.5.2 Staff Evaluation......................................... 4-24 4.5.3 Conclusions............................................ 4-26 4.6 Containment Liner Plate and Penetration Fatigue
...................... 4-26 4.6.1 Summary of Technical Information in the Application............. 4-26 4.6.2 Staff Evaluation......................................... 4-27 4.6.3 Conclusions............................................ 4-30 4.7 Other Plant-Specific Time-Limited Aging Analyses...................... 4-30 4.7.1 Containment Liner Stress.................................. 4-31 4.7.1.1 Summary of Technical Information in the Application..... 4-31 4.7.1.2 Staff Evaluation.................................. 4-31 4.7.1.3 Conclusions..................................... 4-31 4.7.2 Containment Tendon Fatigue............................... 4-31 4.7.2.1 Summary of Information in the Application............. 4-32 4.7.2.2 Staff Evaluation.................................. 4-32 4.7.2.3 Conclusions..................................... 4-32 4.7.3 Containment Liner Anchorage Fatigue........................ 4-32 4.7.3.1 Summary of Technical Information in the Application..... 4-32 4.7.3.2 Staff Evaluation.................................. 4-33 4.7.3.3 Conclusions..................................... 4-33 4.7.4 Containment Tendon Bellows Fatigue........................ 4-34 4.7.4.1 Summary of Information in the Application............. 4-34 4.7.4.2 Staff Evaluation.................................. 4-34 4.7.4.3 Conclusions..................................... 4-36 4.7.5 Crane Cycle Load Limits.................................. 4-36 4.7.5.1 Summary of Technical Information in the Application..... 4-36 4.7.5.2 Staff Evaluation.................................. 4-36 4.7.5.3 Conclusions..................................... 4-37 4.7.6 Reactor Coolant Pump Flywheel............................ 4-37 4.7.6.1 Technical Information in the Application............... 4-38 4.7.6.2 Staff Evaluation.................................. 4-38 4.7.6.3 UFSAR Supplement.............................. 4-38
-xi-4.7.6.4 Conclusion...................................... 4-38 4.7.7 Thermal Aging of Cast Austenitic Stainless Steel............... 4-39 4.7.7.1 Summary of Technical Information in the Application..... 4-39 4.7.7.2 Staff Evaluation.................................. 4-39 4.7.7.3 Conclusions..................................... 4-41 4.8 Evaluation Findings............................................. 4-41 5 REVIEW BY THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
......... 5-1 6 CONCLUSIONS........................................................ 6-1 APPENDIX A: COMMITMENT LISTING....................................... A-1 APPENDIX B: CHRONOLOGY.............................................. B-1 APPENDIX C: PRINCIPAL CONTRIBUTORS................................... C-1 APPENDIX D: REFERENCES............................................... D-1