ML022280033
| ML022280033 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/06/2002 |
| From: | Byrne S South Carolina Electric & Gas Co |
| To: | Rajender Auluck Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RC-02-0123 | |
| Download: ML022280033 (33) | |
Text
License Renewal Application Wt I-rmber-501395 I
mberiNPF-1 2 A SCANA COMPANY 3u
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 TABLE OF CONTENTS LIST OF TABLES 1
SECTION 1 - ADMINISTRATIVE INFORMATION 1
INTRODUCTION 1
1.0 ADMINISTRATIVE INFORMATION 1
1.1 NAMES OF APPLICANTS 1
1.2 ADDRESSES OF APPLICANTS 1
1.3 DESCRIPTION
OF BUSINESS 3
1.4 ORGANIZATION AND MANAGEMENT OF APPLICANTS 4
1.5 CLASS AND PERIOD OF LICENSE SOUGHT 6
1.6 ALTERATION SCHEDULE 6
1.7 LISTING OF REGULATORY AGENCIES HAVING JURISDICTION &
APPROPRIATE NEWS PUBLICATIONS 6
1.8 CONFORMING CHANGES TO THE STANDARD INDEMNITY AGREEMENT 6
1.9 RESTRICTED DATA AGREEMENT 7
SECTION 2 - SCOPING AND SCREENING REVIEW 1
2.0 STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW 1
2.1 SCOPING AND SCREENING METHODOLOGY 3
2.1.1 PLANT LEVEL SCOPING 3
2.1.1.1 Information Sources 5
2.1.1.1.1 Design Basis Documents 5
2.1.1.1.2 Component Database 5
2.1.1.1.3 Flow Diagrams (P&ID) 5 2.1.1.1.4 Electrical Boundaries 6
2.1.1.2 Safety-Related Criteria Pursuant To 10 CFR 54.4(a)(1) 6 2.1.1.2.1 Safety-Related Mechanical Systems 7
2.1.1.2.2 Safety-Related Structures 9
2.1.1.2.3 Safety-Related Electrical Systems 10 I ALL Ut-L.U4 I E'4 I
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 2.1.1.3 Non-Safety-Related Criteria Pursuant To 10 CFR 54.4(a)(2) 2.1.1.3.1 Non-Safety-Related Mechanical Systems 2.1.1.3.2 Non-Safety-Related Structures 2.1.1.3.3 Non-Safety-Related Electrical Systems 2.1.1.4 Regulated Events Pursuant To 10 CFR 54.4 (a)(3) 2.1.1.4.1 Fire Protection (FP) 2.1.1.4.2 Environmental Qualification (EQ) 2.1.1.4.3 Pressurized Thermal Shock (PTS) 2.1.1.4.4 Anticipated Transient Without Scram (ATWS) 2.1.1.4.5 Station Blackout (SBO) 2.1.1.5 Systems And Structures Intended Functions 2.1.2 SCREENING METHODOLOGY 2.1.2.1 Screening Methodology Mechanical Systems 2.1.2.1.1 Establish System Evaluation Boundaries 2.1.2.1.2 Determine Components Within The System Evaluation Boundaries 2.1.2.1.3 Identify Component Intended Functions 2.1.2.1.4 Determine Components Subject To Aging Management Review 2.1.2.1.5 Establish Commodity Groupings 2.1.2.1.6 Results 2.1.2.2 Screening Methodology For Structures 2.1.2.2.1 Establish Structure Evaluation Boundaries 2.1.2.2.2 Determine Structural Components Within The Evaluation Boundaries 2.1.2.2.3 Determine Components Subject To Aging Management Review 2.1.2.2.4 Identify Component Intended Functions 2.1.2.2.5 Establish Commodity Groupings 2.1.2.2.6 Results 2.1.2.3 Screening Methodology For Electrical/l&C Components 2.1.2.3.1 Establish Commodity Groups And Intended Functions 2.1.2.3.2 Determine Commodity Groups Subject To Aging Management Review 2.1.2.3.3 Results 2.
1.3 CONCLUSION
S 2
1.4 REFERENCES
'ILANT 2.2.1 10 11 13 13 14 14 16 18 19 20 20 21 23 23 23 24 25 26 26 27 27 27 27 28 28 29 29 29 30 30 30 31 33 33 LEVEL SCOPING RESULTS SYSTEMS, STRUCTURES, AND COMPONENTS WITHIN THE SCOPE OF LICENSE RENEWAL I AbLLEUO GUONTINTS 2.2 D A
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 2.2.2 SYSTEMS AND STRUCTURES NOT WITHIN THE SCOPE OF LICENSE RENEWAL 33 2.
2.3 REFERENCES
34 2.3 SYSTEM SCOPING AND SCREENING RESULTS: MECHANICAL 53 2.3.1 REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM 53 2.3.1.1 Reactor Coolant System Description 54 2.3.1.2 Piping, Valves And Pumps 56 2.3.1.3 Reactor Vessel 59 2.3.1.4 Reactor Vessel Internals 62 2.3.1.5 Incore Instrumentation System 67 2.3.1.6 Pressurizer 68 2.3.1.7 Steam Generators 69 2.3.2 ENGINEERED SAFETY FEATURES 73 2.3.2.1 Chemical And Volume Control System 73 2.3.2.2 Containment Isolation System 77 2.3.2.2.1 Auxiliary Coolant / Control Rod Drive Mechanism (CRDM) Cooling Water System 78 2.3.2.2.2 Demineralized Water - Nuclear Services 79 2.3.2.2.3 Nitrogen Blanketing System 80 2.3.2.2.4 Reactor Building Leak Rate Testing System 81 2.3.2.3 Hydrogen Removal - Post Accident System 82 2.3.2.4 Reactor Building Spray System 83 2.3.2.5 Refueling Water System 85 2.3.2.6 Residual Heat Removal System 85 2.3.2.7 Safety Injection System 87 2.3.3 AUXILIARY SYSTEMS 90 2.3.3.1 Air Handling And Local Ventilation And Cooling Systems 90 2.3.3.2 Boron Recycle System 94 2.3.3.3 Building Services 96 2.3.3.4 Chilled Water System 97 2.3.3.5 Circulating Water System 100 2.3.3.6 Component Cooling Water System 100 2.3.3.7 Diesel Generator Services Systems 103 2.3.3.8 Fire Service System 107 2.3.3.9 Fuel Handling System 110 2.3.3.10 Gaseous Waste Processing System 111 2.3.3.11 Industrial Cooler System 113 2.3.3.12 Instrument Air Supply System 114 2.3.3.13 Leak Detection System 115 2.3.3.14 Liquid Waste Processing System 116 2.3.3.15 Nuclear & Non-nuclear Plant Drains 117 I PtL ur t.,urd I hI I
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 2.3.3.16 Nuclear Sampling System 118 2.3.3.17 Radiation Monitoring System 120 2.3.3.18 Reactor Makeup Water Supply System 122 2.3.3.19 Roof Drains System 123 2.3.3.20 Station F-rvice Air System 124 2.3.3.21 Service ater System 125 2.3.3.22 Spent Fuel Cooling System 127 2.3.3.23 Thermal Regeneration System 129 2.3.4 STEAM AND POWER CONVERSION SYSTEMS 131 2.3.4.1 Auxiliary Boiler Steam And Feedwater System 131 2.3.4.2 Condensate System 132 2.3.4.3 Emergency Feedwater System 133 2.3.4.4 Extraction Steam System 135 2.3.4.5 Feedwater System 136 2.3.4.6 Gland Sealing Steam System 137 2.3.4.7 Main Steam System 138 2.3.4.8 Main Steam Dump System 140 2.3.4.9 Main Turbine and Turbine Accessories Systems 141 2.3.4.10 Turbine Cycle Sampling System 142 2.3.4.11 Steam G-erator Blowdown System 143 2.3.4.12 Turbine ELectro-Hydraulic System 144 2.
3.5 REFERENCES
144 2.4 STRUCTURES AND STRUCTURAL COMPONENTS SCOPING AND SCREENING RESULTS 145 2.4.1 REACTOR BUILDING 147 2.4.1.1 Structure And Foundation 147 2.4.1.2 Containment Liner 147 2.4.1.3 Penetrations 148 2.4.1.4 Internal Structures 149 2.4.1.5 Conclusions 150 2.4.2 OTHER STRUCTURES 157 2.4.2.1 Auxiliary Building 157 2.4.2.2 Control Building 163 2.4.2.3 Diesel Generator Building 168 2.4.2.4 Fuel Handling Building 172 2.4.2.5 Intermediate Building 177 2.4.2.6 Turbine Building 183 2.4.2.7 Service Water Pumphouse, Intake And Discharge Structures 186 2.4.2.7.1 Service Water Pumphouse 186 2.4.2.7.2 Service Water Intake And Discharge Structures 187 I-IP-4" AA Iil NEl F/'IL*,* IE. we l*lk 1^
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 2.4.2.8 Yard Structures 192 2.4.2.8.1 Condensate Storage Tank Foundation 192 2.4.2.8.2 Fire Service Pumphouse 194 2.4.2.8.3 Electrical Manhole MH-2 196 2.4.2.8.4 Earthen Embankments 198 2.4.2.8.5 Electrical Substation and Transformer Area 200 2.
4.3 REFERENCES
202 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL 203 2.5.1 NON-EQ INSULATED CABLES & CONNECTIONS 204 2.5.2 NON-EQ ELECTRICAL PENETRATION ASSEMBLIES 204 2.5.3 NON-EQ TERMINAL BLOCKS 205 2.5.4 HIGH VOLTAGE ELECTRICAL SWITCHYARD EQUIPMENT 206 2.
5.5 REFERENCES
207 SECTION 3 - AGING MANAGEMENT REVIEW 1
3.0 AGING MANAGEMENT REVIEW RESULTS 1
3.1 AGING MANAGEMENT OF REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM 2
3.1.1 SYSTEM DESCRIPTION 2
3.1.2 AGING MANAGEMENT REVIEW 2
3.1.2.1 Methodology 2
3.1.2.2 Operating Experience 3
3.1.3 AGING MANAGEMENT PROGRAMS 4
3.1.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 4
3.1.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 4
3.1.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 33 3.
1.4 REFERENCES
45 3.2 AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES 46 3.2.1 SYSTEM DESCRIPTION 46 3.2.2 AGING MANAGEMENT REVIEW 46 3.2.2.1 Methodology 46 3.2.2.2 Operating Experience 47 3.2.3 AGING MANAGEMENT PROGRAMS 48 3.2.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 48 IAbLUl LUNILNI
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.2.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 3.2.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 3.
2.4 REFERENCES
3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 3.3.1 SYSTEM DESCRIPTION 3.3.2 AGING MANAGEMENT REVIEW 3.3.2.1 Methodology 3.3.2.2 Operating Experience 3.3.3 AGING MANAGEMENT PROGRAM 3.3.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 3.3.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 3.3.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 3.
3.4 REFERENCES
3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEMS 3.4.1 SYSTEM DESCRIPTION 3.4.2 AGING MANAGEMENT REVIEW 3.4.2.1 Methodology 3.4.2.2 Operating Experience 3.4.3 AGING MANAGEMENT PROGRAM 3.4.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 3.4.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 3.4.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 3.
4.4 REFERENCES
3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORTS 3.5.1 CONTAINMENT, STRUCTURES, AND COMPONENT SUPPORTS DESCRIPTIONS 3.5.1.1 Reactor Building 3.5.1.2 Auxiliary Building 3.5.1.3 Control Building 3.5.1.4 Intermediate Building 3.5.1.5 Diesel Generator Building 3.5.1.6 Fuel Handling Building 48 60 68 69 69 69 69 70 71 71 71 111 149 150 150 150 150 151 151 151 152 166 171 172 172 172 173 173 173 173 174 93Ar'-P A nr-'
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.5.1.7 Turbine Building 174 3.5.1.8 Service Water Structures 174 3.5.1.9 Yard Structures 175 3.5.1.10 Earthen Embankments 175 3.5.1.11 Class 1 Component Supports 175 3.5.2 AGING MANAGEMENT REVIEW 176 3.5.2.1 Methodology 176 3.5.2.2 Operating Experience 176 3.5.3 AGING MANAGEMENT PROGRAM 177 3.5.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 177 3.5.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 177 3.5.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 224 3.
5.4 REFERENCES
234 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 235 3.6.1 ELECTRIC DESCRIPTION 235 3.6.1.1 Non-EQ Insulated Cables 235 3.6.1.2 Non-EQ Electrical Connectors 236 3.6.1.3 Non-EQ Electrical Splices 236 3.6.1.4 Non-EQ Electrical Penetration Assemblies 236 3.6.1.5 Non-EQ Terminal Blocks 237 3.6.1.6 High Voltage Electrical Switchyard Bus 238 3.6.1.7 High Voltage Transmission Conductors and Connections 238 3.6.1.8 High Voltage Insulators 238 3.6.2 AGING MANAGEMENT REVIEW 239 3.6.2.1 Methodology 239 3.6.2.2 Operating Experience 240 3.6.3 AGING MANAGEMENT PROGRAM 241 3.6.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal 241 3.6.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 241 3.6.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1 801 246 3.
6.4 REFERENCES
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 SECTION 4 - TIME-LIMITING AGING ANALYSIS 1
4.0 TIME-LIMITED AGING ANALYSIS 1
4.1 IDENTIFICATION OF TIME-LIMITED AGING ANALYSIS 1
4.1.1 TLAA PROCESS OVERVIEW 2
4.1.2 EXEMPTIONS TO 10 CFR 50.12 2
4.1.3 TLLA
SUMMARY
3 4.2 REACTOR VESSEL NEUTRON EMBRITTLEMENT 5
4.2.1 UPPER-SHELF ENERGY 5
4.2.2 PRESSURIZED THERMAL SHOCK 6
4.2.3 PRESSURE-TEMPERATURE (P-T) LIMITS 7
4.3 METAL FATIGUE 8
4.3.1 ASME SECTION III, CLASS 1 8
4.3.2 ASME SECTION III, CLASS 2 AND 3 PIPING FATIGUE 8
4.4 ENVIRONMENTAL QUALIFICATION (EQ) 9 4.4.1 TLAA EVALUATION 14 4.4.1.1 Analytical EQ Re-analysis Methods 14 4.4.1.2 Data Collection And Reduction Methods For EQ 14 4.4.1.3 Evaluation Of Underlying EQ Assumptions 15 4.4.2 EQ PROGRAM REVIEW 15 4.4.3 EQ TLAA EVALUATION CONCLUSIONS 15 4.5 CONCRETE CONTAINMENT (REACTOR BUILDING) TENDON PRESTRESS ANALYSIS 15 4.6 CONTAINMENT (REACTOR BUILDING) LINER PLATE, METAL CONTAINMENTS, AND PENETRATION FATIGUE ANALYSIS 17 4.6.1 CONTAINMENT (REACTOR BUILDING) LINER 17 4.6.2 METAL CONTAINMENTS - N/A 17 4.6.3 CONTAINMENT (REACTOR BUILDING) ISOLATION 17 4.6.3.1 Containment (Reactor Building) Isolation Bellows 17 4.6.3.2 Containment (Reactor Building) Isolation - Fracture Toughness And Effects Radiation 18 4.7 OTHER PLANT-SPECIFIC TIME-LIMITED AGING ANALYSES 19 4.7.1 REACTOR COOLANT PUMP FLYWHEEL 19 4.7.2 LEAK-BEFORE-BREAK ANALYSES 20 4.7.3 CRANE LOAD CYCLE LIMIT 20 4.7.3.1 Reactor Building Polar Crane 21 4.7.3.2 Spent Fuel Cask Handling Crane 22 4.7.3.3 Fuel Handling Machine And Refueling Machine 22 4.7.3.4 Summary 22 MAf r0 P
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 4.7.4 SERVICE WATER INTAKE STRUCTURE SETTLEMENT
4.8 REFERENCES
4.8.1 CALCULATIONS AND ANALYSES 4.8.2 CORRESPONDENCE 4.8.3 LICENSING DOCUMENTS AND REPORTS 4.8.4 REGULATORY DOCUMENTS 4.8.5 INDUSTRY DOCUMENTS APPENDIX A - FSAR CHAPTER 18 INTRODUCTION FSAR SUPPLEMENT 18.0 AGING MANAGEMENT PROGRAMS AND ACTIVITIES
18.1 INTRODUCTION
18.2 AGING MANAGEMENT PROGRAMS AND ACTIVITIES 18.2.1 10 CFR 50 APPENDIX J GENERAL VISUAL INSPECTION 18.2.2 10 CFR 50 APPENDIX J LEAK RATE TESTING 18.2.3 ABOVE GROUND TANK INSPECTION 18.2.4 ALLOY 600 AGING MANAGEMENT PROGRAM 18.2.5 ASME SECTION XI ISI PROGRAM - IWF 18.2.6 BATTERY RACK INSPECTION 18.2.7 BORIC ACID CORROSION SURVEILLANCES 18.2.8 BOTTOM-MOUNTED INSTRUMENTATION INSPECTION 18.2.9 BURIED PIPING AND TANKS INSPECTION 18.2.10 CHEMISTRY PROGRAM 18.2.11 CONTAINMENT COATING MONITORING AND MAINTENANCE PROGRAM 18.2.12 CONTAINMENT ISI PROGRAM - IWE/IWL 18.2.13 DIESEL GENERATOR SYSTEMS INSPECTION 18.2.14 ENVIRONMENTAL QUALIFICATION (EQ) PROGRAM 18.2.15 FIRE PROTECTION PROGRAM 18.2.15.1 Mechanical 18.2.15.2 Fire Barriers And Fire Barrier Penetration Seals 18.2.15.3 Fire Doors 18.2.16 FLOOD BARRIER INSPECTION 18.2.17 FLOW-ACCELERATED CORROSION MONITORING PROGRAM 18.2.18 NON-EQ INSULATED CABLES AND CONNECTIONS INSPECTION PROGRAM 18.2.19 IN-SERVICE INSPECTION (ISI) PLAN I A LE J"
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 18.2.20 INSPECTIONS FOR MECHANICAL COMPONENTS 12 18.2.21 LIQUID WASTE SYSTEM INSPECTION 13 18.2.22 MAINTENANCE RULE STRUCTURES PROGRAM 13 18.2.23 MATERIAL HANDLING SYSTEM INSPECTION PROGRAM 13 18.2.24 PRESSURE DOOR INSPECTION PROGRAM 13 18.2.25 PREVENTIVE MAINTENANCE ACTIVITIES - VENTILATION SYSTEM INSPECTIONS 14 18.2.26 REACTOR BUILDING COOLING UNIT INSPECTION 14 18.2.27 REACTOR HEAD CLOSURE STUDS PROGRAM 14 18.2.28 REACTOR VESSEL INTERNALS INSPECTION 14 18.2.29 REACTOR VESSEL SURVEILLANCE PROGRAM 15 18.2.30 SERVICE AIR SYSTEM INSPECTION 15 18.2.31 SERVICE WATER POND DAM INSPECTION PROGRAM 15 18.2.32 SERVICE WATER STRUCTURES SURVEY MONITORING
".PROGRAM 16 18.2.33 SERVICE WATER SYSTEM RELIABILITY AND IN-SERVICE TESTING PROGRAM 16 18.2.34 SMALL BORE CLASS 1 PIPING INSPECTION 16 18.2.35 STEAM GENERATOR MANAGEMENT PROGRAM 16 18.2.36 TENDON SURVEILLANCE PROGRAM 17 18.2.37 THERMAL FATIGUE MANAGEMENT PROGRAM 17 18.2.38 UNDERWATER INSPECTION PROGRAM (SWIS AND SWPH) 17 18.2.39 WASTE GAS SYSTEM INSPECTION 17 18.2.40 HEAT EXCHANGER INSPECTIONS 18 18.2.41 PREVENTIVE MAINTENANCE ACTIVITIES - TERRY TURBINE 18 18.3 TIME-LIMITED AGING ANALYSES (TLAA) EVALUATIONS 19 18.3.1 REACTOR VESSEL NEUTRON EMBRITTLEMENT 19 18.3.1.1 Upper-Shelf Energy 19 18.3.1.2 Pressurized Thermal Shock 19 18.3.1.3 Pressure-Temperature (P-T) Limits 20 18.3.2 METAL FATIGUE 20 18.3.2.1 ASME Section III, Class 1 20 18.3.2.2 Leak-Before-Break Analyses 21 18.3.2.3 ASME Section III, Class 2 and 3 Piping Fatigue 21 18.3.3 ENVIRONMENTAL QUALIFICA'7- -)N (EQ) 21 18.3.4 REACTOR BUILDING TENDON
-<ESTRESS 22 18.3.5 REACTOR BUILDING LINER 22 18.3.6 OTHER PLANT-SPECIFIC TIME-LIMITED AGING ANALYSES 22 18.3.6.1 Crane Load Cycle Limit 22 18.3.6.2 Service Water Intake Structure Settlement 23 18.3.6.3 Reactor Coolant Pump Flywheel 23
18.4 REFERENCES
24 PAGE 10 OF 14 TABLE OF CONTENTS
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 APPENDIX B - AGING MANAGEMENT PROGRAMS AND ACTIVITIES 1
INTRODUCTION 1
B.1.0 EXISTING AGING MANAGEMENT ACTIVITIES 8
B.1.1 ALLOY 600 AGING MANAGEMENT PROGRAM 8
B.1.1.1 Operating Experience 8
B.1.1.2 Conclusion 10 B.1.2 BORIC ACID CORROSION SURVEILLANCES 11 B.1.2.1 Operating Experience 11 B.1.2.2 Conclusion 12 B.1.3 BOTTOM-MOUNTED INSTRUMENTATION INSPECTION 13 B.1.3.1 Operating Experience 14 B.1.3.2 Conclusion 14 B.1.4 CHEMISTRY PROGRAM 15 B.1.4.1 Operating Experience 15 B.1.4.2 Conclusion 16 B.1.5 FIRE PROTECTION PROGRAM 17 B.1.5.1 Operating Experience 19 B.1.5.1.1 Mechanical 19 B.1.5.1.2 Fire Barriers And Fire Barriers Penetration Seals 19 B.1.5.1.3 Fire Doors 20 B.1.5.2 Conclusion 20 B.1.6 FLOW-ACCELERATED CORROSION MONITORING PROGRAM 21 B.1.6.1 Operating Experience 21 B.1.6.2 Conclusion 21 B.1.7 IN-SERVICE INSPECTION (ISI) PLAN 22 B.1.7.1 Operating Experience 22 B.1.7.2 Conclusion 22 B.1.8 REACTOR HEAD CLOSURE STUDS PROGRAM 23 B.1.8.1 Operating Experience 23 B.1.8.2 Conclusion 23 B.1.9 SERVICE WATER SYSTEM RELIABILITY AND IN-SERVICE TESTING PROGRAM 24 B.1.9.1 Operating Experience 24 B.1.9.2 Conclusion 24 r*Is
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 B.1.10 STEAM GENERATOR MANAGEMENT PROGRAM 25 B. 1.10.1 Operating Experience 25 B.1.10.2 Conclusion 25 B.1.11 10 CFR 50 APPENDIX J GENERAL VISUAL INSPECTION 26 B. 1.11.1 Operating Experience 26 B.1.11.2 Conclusion 26 B.1.12 10 CFR 50 APPENDIX J LEAK RATE TESTING 27 B.1.12.1 Operating Experience 27 B. 1.12.2 Conclusion 27 B.1.13 ASME SECTION XI ISI PROGRAM - IWF 28 B. 1.13.1 Operating Experience 28 B. 1.13.2 Conclusion 28 B.1.14 BATTERY RACK INSPECTION 30 B.1.14.1 Operating Experience 31 B. 1.14.2 Conclusion 32 B.1.15 CONTAINMENT COATING MONITORING AND MAINTENANCE PROGRAM 33 B.1.15.1 Operating Experience 33 B. 1.15.2 Conclusion 34 B.1.16 CONTAINMENT ISI PROGRAM - IWE/IWL 35 B.1.16.1 Operating Experience 35 B.1.16.2 Conclusion 35 B.1.17 FLOOD BARRIER INSPECTION 37 B.1.17.1 Operating Experience 38 B.1.17.2 Conclusion 39 B.1.18 MAINTENANCE RULE STRUCTURES PROGRAM 40 B.1.18.1 Operating Experience 40 B. 1.18.2 Conclusion 41 B.1.19 MATERIAL HANDLING SYSTEM INSPECTION PROGRAM 42 B.1.19.1 Operating Experience 42 B.1.19.2 Conclusion 43 B.1.20 PRESSURE DOOR INSPECTION PROGRAM 44 B.1.20.1 Operating Experience 45 B. 1.20.2 Conclusion 46 B.1.21 SERVICE WATER POND DAM INSPECTION PROGRAM 47 B. 1.21.1 Operating Experience 47 B.1.21.2 Conclusion 48 PAGE 12 OF 14 TABLE OF CONTENTS
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 B.1.22 SERVICE WATER STRUCTURES SURVEY MONITORING PROGRAM 49 B.1.22.1 Operating Experience 51 B. 1.22.2 Conclusion 52 B.1.23 UNDERWATER INSPECTION PROGRAM (SWIS AND SWPH) 53 B.1.23.1 Operating Experience 54 B. 1.23.2 Conclusion 55 B.1.24 REACTOR VESSEL SURVEILLANCE PROGRAM 56 B.1.24.1 Operating Experience 56 B.1.24.2 Conclusion 57 B.1.25 PREVENTIVE MAINTENANCE ACTIVITIES - TERRY TURBINE 58 B.1.25.1 Operating Experience 59 B. 1.25.2 Conclusion 59 B.1.26 PREVENTIVE MAINTENANCE ACTIVITIES - VENTILATION SYSTEMS INSPECTIONS 60 B.1.26.1 Operating Experience 62 B.1.26.2 Conclusion 62 B.2.0 NEW AGING MANAGEMENT ACTIVTIES 63 B.2.1 ABOVE GROUND TANK INSPECTION 63 B.2.1.1 Operating Experience 65 B.2.1.2 Conclusion 65 B.2.2 DIESEL GENERATOR SYSTEMS INSPECTION 66 B.2.2.1 Operating Experience 67 B.2.2.2 Conclusion 67 B.2.3 LIQUID WASTE SYSTEM INSPECTION 68 B.2.3.1 Operating Experience 69 B.2.3.2 Conclusion 70 B.2.4 REACTOR VESSEL INTERNALS INSPECTION 71 B.2.4.1 Operating Experience 74 B.2.4.2 Conclusion 74 B.2.5 REACTOR BUILDING COOLING UNIT INSPECTION 75 B.2.5.1 Operating Experience 76 B.2.5.2 Conclusion 76 B.2.6 SERVICE AIR SYSTEM INSPECTION 77 B.2.6.1 Operating Experience 78 B.2.6.2 Conclusion 78 I AIL" U? LUIl I MIN I MA&-= 412 fC 4A FAUr I,*I vr I*
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 B.2.7 SMALL BORE CLASS 1 PIPING INSPECTION 79 B.2.7.1 Operating Experience 80 B.2.7.2 Conclusion 81 B.2.8 WASTE GAS SYSTEM INSPECTION 82 B.2.8.1 Operating Experience 83 B.2.8.2 Conclusion 84 B.2.9 NON-EQ INSULATED CABLES AND CONNECTIONS INSPECTION PROGRAM 85 B.2.9.1 Operating Experience 87 B.2.9.2 Conclusion 87 B.2.10 BURIED PIPING AND TANKS INSPECTION 88 B.2.10.1 Operating Experience 89 B.2.10.2 Conclusion 89 B.2.11 INSPECTIONS FOR MECHANICAL COMPONENTS 91 B.2.11.1 Operating Experience 92 B.2.11.2 Conclusion 93 B.2.12 HEAT EXCHANGER INSPECTIONS 94 B.2.12.1 Operating Experience 95 B.2.12.2 Conclusion 96 B.3.0 TLAA SUPPORT ACTIVITIES 97 B.3.1 ENVIRONMENTAL QUALIFICATION (EQ) PROGRAM 97 B.3.1.1 Operating Experience 97 B.3.1.2 Conclusion 97 B.3.2 THERMAL FATIGUE MANAGEMENT PROGRAM 98 B.3.2.1 Operating Experience 98 B.3.2.2 Conclusion 98 B.3.3 TENDON SURVEILLANCE PROGRAM 99 B.3.3.1 Operating Experience 99 B.3.3.2 Conclusion 100 B.
4.0 REFERENCES
101 APPENDIX C - COMMODITY GROUPS (OPTIONAL) 1 APPENDIX D - TECHNICAL SPECIF :CATION CHANGES 1
APPENDIX E - ENVIRONMENTAL REPORT 1
PA(*Il 4A
'P 4A IAULE OF CONTENTS
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 LIST OF TABLES Table Table Title Page(s)
Number 2.2-1 MECHANICAL SCOPING RESULTS 35 -40 2.2-2 STRUCTURAL SCOPING RESULTS 42 -47 2.2-3 ELECTRICAL SCOPING RESULTS 49 -51 2.3-1 REACTOR COOLANT SYSTEM NON-CLASS 1 COMPO-55-56 NENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-2 REACTOR COOLANT SYSTEM CLASS 1 PIPING, VALVE, &
58-59 PUMP COMPONENT TYPES SUBJECT TO AGING MAN AGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-3 REACTOR VESSEL COMPONENT TYPES SUBJECT TO 60-62 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-4 REACTOR VESSEL INTERNALS COMPONENT TYPES 63-66 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-5 INCORE INSTRUMENTATION SYSTEM COMPONENT 67 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-6 PRESSURIZER COMPONENT TYPES SUBJECT TO AGING 68-69 MANAGEMENT REVIEW AND THEIR INTENDED FUNC TIONS 2.3-7 STEAM GENERATORS COMPONENT TYPES SUBJECT TO 70-72 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-8 CHEMICAL AND VOLUME CONTROL SYSTEM COMPO-75-77 NENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-9 AUXILIARY COOLANT / CRDM COOLING WATER SYSTEM 79 COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS LIST OF TABLES PAGE 1 OF 10 LIST OF TABLES PAGE 1 OF 10
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table Number Table Title Page(s) 2.3-10 DEMINERALIZED WATER - NUCLEAR SERVICES SYSTEM 80 COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-11 NITROGEN BLANKETING SYSTEM COMPONENT TYPES 80-81 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-12 REACTOR BUILDING LEAK RATE TESTING SYSTEM COM-81 PONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-13 HYDROGEN REMOVAL SYSTEM COMPONENT TYPES 82-83 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-14 REACTOR BUILDING SPRAY SYSTEM COMPONENT 84 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-15 REFUELING WATER SYSTEM COMPONENT TYPES SUB-85 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-16 RESIDUAL HEAT REMOVAL SYSTEM COMPONENT TYPES 86-87 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-17 SAFETY INJECTION SYSTEM COMPONENT TYPES SUB-88-89 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-18 AIR HANDLING AND LOCAL VENTILATION AND COOLING 93-94 SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNC TIONS 2.3-19 BORON RECYCLE SYSTEM COMPONENT TYPES SUB-95 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTi.NS PAGE 2 OF 10 LIST OF TABLES
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table Table Title Page(s)
Number 2.3-20 BUILDING SERVICES SYSTEM COMPONENT TYPES SUB-96 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-21 CHILLED WATER SYSTEM COMPONENT TYPES SUBJECT 97-100 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTION 2.3-22 COMPONENT COOLING WATER SYSTEM COMPONENT 101 - 103 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-23 DIESEL GENERATOR SERVICES SYSTEMS COMPONENT 104 - 107 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-24 FIRE SERVICE SYSTEM COMPONENT TYPES SUBJECT 109 - 110 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-25 FUEL HANDLING SYSTEM COMPONENT TYPES SUBJECT 111 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-26 GASEOUS WASTE PROCESSING SYSTEM COMPONENT 112 - 113 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-27 INSTRUMENT AIR SUPPLY SYSTEM COMPONENT TYPES 115 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-28 LIQUID WASTE PROCESSING SYSTEM COMPONENT 116 - 117 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-29 NUCLEAR PLANT DRAINS COMPONENT TYPES SUBJECT 118 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-30 NUCLEAR SAMPLING SYSTEM COMPONENT TYPES SUB-119 - 120 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS LIST OF TABLES PAGE 3 OF 10 LIST OF TABLES PAGE 3 OF 10
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table Number Table Title Page(s) 2.3-31 RADIATION MONITORING SYSTEM COMPONENT TYPES 121 - 122 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-32 REACTOR MAKEUP WATER SUPPLY SYSTEM COMPO-123 NENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-33 ROOF DRAINS SYSTEM COMPONENT TYPES SUBJECT 124 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-34 STATION SERVICE AIR SYSTEM COMPONENT TYPES 125 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-35 SERVICE WATER SYSTEM COMPONENT TYPES SUBJECT 126-127 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-36 SPENT FUEL COOLING SYSTEM COMPONENT TYPES 128 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-37 THERMAL REGENERATION SYSTEM COMPONENT TYPES 129 - 130 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-38 AUXILIARY BOILER STEAM AND FEEDWATER SYSTEM 132 COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-39 CONDENSATE SYSTEM COMPONENT TYPES SUBJECT 133 TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-40 EMERGENCY FEEDWATER SYSTEM COMPONENT TYPES 134 - 135 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-41 EXTRACTION STEAM SYSTEM COMPONENT TYPES SUB-136 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS rAePr' A f~r-AA LIST OF TABfL]ES
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table Table Title Page(s)
Number 2.3-42 FEEDWATER SYSTEM COMPONENT TYPES SUBJECT TO 137 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-43 GLAND SEALING STEAM SYSTEM COMPONENT TYPES 138 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-44 MAIN STEAM SYSTEM COMPONENT TYPES SUBJECT TO 139 - 140 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-45 MAIN STEAM DUMP SYSTEM COMPONENT TYPES SUB-141 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-46 TURBINE CYCLE SAMPLING SYSTEM COMPONENT 142 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.3-47 STEAM GENERATOR BLOWDOWN SYSTEM COMPONENT 143 TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-1 INTENDED FUNCTIONS FOR STRUCTURAL COMPONENT 145 - 146 TYPES 2.4-2 REACTOR BUILDING COMPONENT TYPES SUBJECT TO 151 - 156 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-3 AUXILIARY BUILDING COMPONENT TYPES SUBJECT TO 159 - 163 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-4 CONTROL BUILDING COMPONENT TYPES SUBJECT TO 164 - 168 AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-5 DIESEL GENERATOR BUILDING COMPONENT TYPES 169 - 172 SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS LIST OF TABLES PAGE 5 OF 10 LIST OF TABLES PAGE 5 OF 10
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table Title 2.4-6 FUEL HANDLING BUILDING COMPONENT TYPES SUB JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-7 INTERMEDIATE BUILDING COMPONENT TYPES SUB JECT TO AGING ANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-8 TURBINE BUILDING COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-9 SERVICE WATER PUMPHOUSE, INTAKE AND DISCHARGE STRUCTURES COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNC TIONS 2.4-10 YARD STRUCTURES (CONDENSATE STORAGE TANK FOUNDATION) COMPONENT TYPES SUBJECT TO AGING MANAGEMENT EVIEW AND THEIR INTENDED FUNC TIONS 2.4-11 YARD STRUCTURES (FIRE SERVICE PUMPHOUSE) COM PONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-12 YARD STRUCTURES (ELECTRICAL MANHOLE MH-2)
COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-13 EARTHEN EMBANKMENTS COMPONENT TYPES SUB JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.4-14 YARD STR. TURES (ELECTRICAL SUBSTATION AND TRANSFOf V4ER AREA) COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS NON-EQ INSULATED CABLES AND CONNECTIONS COM PONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS E3 A r, r
EU L5 AFTBE Table Number Page(s) 173-177 178-183 184-186 189-191 193 194-196 197-198 199-200 201 204 2.5-1 v* %iUf-I LIST OF TABLES
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table Table Title Page(s)
Number 2.5-2 NON-EQ ELECTRICAL PENETRATION ASSEMBLIES COM-205 PONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.5-3 NON-EQ TERMINAL BLOCKS COMPONENT TYPES SUB-206 JECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 2.5-4 HIGH VOLTAGE ELECTRICAL SWITCHYARD EQUIPMENT 207 COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW AND THEIR INTENDED FUNCTIONS 3.1-1
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR 5-32 THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL 3.1-2
SUMMARY
OF AGING MANAGEMENT EVALUATIONS FOR 34-44 THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL 3.2-1
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR 49-59 THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL 3.2-2
SUMMARY
OF AGING MANAGEMENT EVALUATIONS FOR 61 -67 THE ENGINEERED SAFETY FEATURES THAT ARE DIF FERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL 3.3-1
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR 72-110 THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL 3.3-2
SUMMARY
OF AGING MANAGEMENT EVALUATIONS FOR 112 - 148 THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL LIST OF TABLES PAGE 7 OF 10 LIST OF TABLES PAGE 7 OF 10
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table Number Table Title 3.4-1
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION SYSTEMS EVALU ATED IN NUREG-1 801 THAT ARE RELIED ON FOR LICENSE RENEWAL 3.4-2
SUMMARY
OF AGING MANAGEMENT EVALUATIONS FOR THE STEAM & POWER CONVERSION SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG 1801 BUT ARE RELIED ON FOR LICENSE RENEWAL 3.5-1
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL 3.5-2
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL 3.6-1 3.6-2 4.1-1 4.4-1 18-1 18-2 D A I =
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SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROL COMPONENTS EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR LICENSE RENEWAL
SUMMARY
OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROL COMPONENTS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL VCSNS SPECIFIC - ACTUAL TLAA
SUMMARY
ENVIRONMENTAL QUALIFICATION DOCUMENTS "HARSH" EQ BINDERS
SUMMARY
LISTING OF THE AGING MANAGEMENT PRO GRAMS AND ACTIVITIES
SUMMARY
LISTING OF THE TLAA EVALUATIONS FOR LICENSE RENEWAL Page(s) 153-165 167-170 178-223 225-233 242-245 247-250 4
11 - 13 3-5 5-6
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table Table Title Page(s)
Number B-1 CORRELATION OF NUREG 1801 AND VCSNS PROGRAMS 3-7 LIST OF TABLES PA 9 OF 10 LIST OF TABLES PAGEt 9 UF; 10
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 DA rIn: 4n l'
111.
Li I UI" IABLES
LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 SECTION I - ADMINISTRATIVE INFORMATION INTRODUCTION Pursuant to Part 54 of Title 10 of the Code of Federal Regulations (10 CFR 54), this applica tion seeks renewal for an additional 20 year term of the facility operating license for Virgil C.
Summer Nuclear Station (VCSNS) (NPF-12). The facility operating license (NPF-12) cur rently expires at midnight August 6, 2022. The application includes renewal of the source, special nuclear, and by-product materials licenses that are combined in the facility operating license.
The application is organized in accordance with the U.S. Nuclear Regulatory Commission Regulatory Guide 1.188, "Standard Format And Content For Applications To Renew Nuclear Power Plant Operating Licenses," April 2001, and is consistent with the guidance provided by NEI 95-10, "Industry Guidelines for Implementing the Requirements of 10 CFR 54 License Renewal."
The License Renewal Application is intended to provide sufficient information for the NRC to complete its technical and environmental reviews. Pursuant to 10 CFR Parts 54 and 51, respectively, the License Renewal Application is designed to allow the NRC to make the findings required by 10 CFR 54.29 in support of the issuance of a renewed facility operating license for VCSNS. The following is the general information required by 10 CFR 54.17 and 54.19.
1.0 ADMINISTRATIVE INFORMATION 1.1 NAMES OF APPLICANTS South Carolina Electric & Gas Company (2/3 owner, and exclusive operator)
South Carolina Public Service Authority (1/3 owner) 1.2 ADDRESSES OF APPLICANTS South Carolina Electric & Gas ComDanv US Postal Service Address:
SCE&G Columbia, SC 29218 Private Courier Address:
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 1426 Main Street Columbia, SC 29201 All communications pertaining this application should be sent to:
Stephen A. Byrne Senior Vice President - Nuclear Operation South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 Ronald B. Clary Manager, Plant Life Extension South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. 0. Box 88 Jenkinsville, SC 29065 In addition, it is requested that additional copies be sent to the company's General Counsel and Washington Counsel:
H. Thomas Arthur Senior Vice President - General Counsel and Assistant Secretary SCANA Corporation 1426 Main Street Columbia, SC 29201 Kathryn M. Sutton Winston & Strawn 1400 L Street, N.W.
Washington, D.C. 20005-3502 South Carolina Public Service Authority Maxie C. Chaplin Senior Vice President, Generation South Carolina Public Service Authority P. 0. Box 2946101 Moncks Corner, SC 29461-2901 S.U - illrl, I,
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Robin White Nuclear Coordinator Virgil C. Summer Nuclear Station P. 0. Box 88 Jenkinsville, SC 29065
1.3 DESCRIPTION
OF BUSINESS South Carolina Electric & Gas Company:
South Carolina Electric & Gas Company (SCE&G), a wholly-owned subsidiary of SCANA Corporation, is primarily engaged in the generation, transmission and distri bution of electricity. The service territory covers the southern two-thirds of the state of South Carolina. SCE&G supplies electric service to more than 500,000 residential, commercial, and industrial customers. To service this area, SCE&G operates 19 elec tric generating facilities with an installed capacity of over 4500 MW electric, including VCSNS.
SCE&G is 2/3 owner of VCSNS and is authorized to act as agent for the South Caro lina Public Service Authority and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.1 South Carolina Public Service Authority:
South Carolina Public Service Authority is a state owned electric and water utility that serves approximately 130,000 retail customers in Berkeley, Georgetown and Horry counties. The utility generates the power distributed by 20 electric cooperatives to more than 450,000 customers located in 46 counties, supplies power to 34 large industries, and the municipalities of Bamberg and Georgetown.
South Carolina Public Service Authority is 1/3 owner of VCSNS.
- 1. SCE&G/South Carolina Public Service Authority, Docket No. 50-395, Virgil C. Summer Nuclear Sta tion, Facility Operating License NPF-12
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 1.4 ORGANIZATION AND MANAGEMENT OF APPLICANTS South Carolina Electric & Gas Company:
William B. Timmerman President & Chief Executive Officer SCANA Corporation 1426 Main Street Columbia, SC 29201 NevillE 3. Lorick President and Chief Operating Officer South Carolina Electric & Gas Company 1426 Main Street Columbia, SC 29201 Kevin B. Marsh Chief Financial Officer SCANA Corporation 1426 Main Street Columbia, SC 29201 H. Thomas Arthur Senior Vice President - General Counsel and Assistant Secretary SCANA Corporation 1426 Main Street Columbia, SC 29201 Duane C. Harris Senior Vice President - Human Resources SCANA Corporation 1426 Main Street Columbia, SC 29201 Stephen A. Byrne Senior Vice President - Nuclear Operation South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. 0. Box 88 Jenkinsville, SC 29065 D A
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 J. Patrick Hudson Corporate Compliance and Internal Auditing Officer SCANA Corporation 1426 Main Street Columbia, SC 29201 South Carolina Public Service Authority:
John H. Tiencken President and Chief Executive Officer South Carolina Public Service Authority P. 0. Box 2946101 Moncks Corner, SC 29461-2901 Bill McCall Jr.
Executive Vice President and Chief Operations Officer South Carolina Public Service Authority P. 0. Box 2946101 Moncks Corner, SC 29461-2901 John S. West Executive Vice President and Chief Legal Officer South Carolina Public Service Authority P. O. Box 2946101 Moncks Corner, SC 29461-2901 Lonnie N. Carter Senior Vice President Corporate Planning & Bulk Power South Carolina Public Service Authority P. 0. Box 2946101 Moncks Corner, SC 29461-2901 Elaine G. Peterson Senior Vice President Administration & Finance South Carolina Public Service Authority P. O. Box 2946101 Moncks Corner, SC 29461-2901 1.U
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 1.5 CLASS AND PERIOD OF LICENSE SOUGHT SCE&G requests renewal of the Class 104b facility operating license for VCSNS (facility operating license NPF-12) for a period of 20 years beyond the expiration of the current license term. License renewal would extend the facility operating license from midnight August 6, 2022 until midnight August 6, 2042. This application includes a request for renewal of those NRC source material, special nuclear material, and by-product material licenses that are currently subsumed or combined with the current facility operating license.
1.6 ALTERATION SCHEDULE SCE&G does not propose to construct or alter any production or utilization facility in connec tion with this renewal application.
1.7 LISTING OF REGULATORY AGENCIES HAVING JURISDICTION &
APPROPRIATE NEWS PUBLICATIONS The Public Service Commission of South Carolina has jurisdiction over the rates and ser vices provided by the company's utility operations. It's address is:
Public Service Commission of South Carolina Koger Executive Center Saluda Building 101 Executive Center Drive Columbia, SC 29210 The news publication that serves the VCSNS surrounding area is The State newspaper. It's address is:
The State Newspaper P. 0. Box 1333 Columbia, SC 29202 1.8 CONFORMING CHANGES TO THE STANDARD INDEMNITY AGREE MENT 10 CFR 54.19(b) requires that license renewal applications include,........ conforming changes to the standard indemnity agreement, 10 CFR 140.92 Appendix B, to account for the expiration term of the proposed renewal license." The current indemnity agreement (No.
B-86) for VCSNS states in Article VII that the agreement shall terminate at the time of expi ration of the license specified in Item 3 of the Attachment to the agreement, which is the last to expire. Item 3 of the Attachment to the indemnity agreement, as revised by Amendment No. 2 lists two license numbers (SNM-1 834 and NPF-1 2). SCE&G requests that conforming changes be made to Article VII of the indemniay agreement, and Item 3 of the Attachment to that agreement, specifying the extension of agreement until the expiration date of the PAC*F R flF R
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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 renewed VCSNS facility operating license as sought in this application. In addition, should the license numbers be changed upon issuance of the renewal license, SCE&G requests that conforming changes be made to Item 3 of the Attachment, and any other sections of the indemnity agreement as appropriate.
1.9 RESTRICTED DATA AGREEMENT This application does not contain any Restricted Data or National Security Information, and SCE&G does not expect that any activity under the renewed license for VCSNS will involve such information. However, if such information were to become involved, SCE&G agrees that it will appropriately safeguard such information and not permit any individual to have access to, or any facility to possess, such information until the individual or facility has been approved under the provisions of Parts 10 CFR 25 or 10 CFR 95, respectively.
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