ML18221A215

Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities

ML18221A215
Person / Time
Site:	Summer
Issue date:	05/31/2018
From:	South Carolina Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18221A142	List: ML18221A134 ML18221A145 ML18221A147 ML18221A151 ML18221A152 ML18221A153 ML18221A154 ML18221A155 ML18221A156 ML18221A157 ML18221A158 ML18221A159 ML18221A160 ML18221A161 ML18221A162 ML18221A165 ML18221A166 ML18221A167 ML18221A168 ML18221A169 ML18221A171 ML18221A172 ML18221A175 ML18221A178 ML18221A180 ML18221A181 ML18221A182 ML18221A206 ML18221A210 ML18221A211 ML18221A212 ML18221A213 ML18221A214 ML18221A215 RC-18-0080, Updated Final Safety Analysis Report, Chapter 9, Figures 9.5-1 Through 9.5-11 - Redacted RC-18-0080, Virgil C. Summer Nuclear Station Unit 1 Submittal of Updated Final Safety Analysis Report, Updated Through May 31, 2018, Cover Sheet RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Approved FSAR Revision Notices RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 11.0, Radioactive Waste Management RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 12.0, Radiation Protection RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 15, Accident Analyses RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 17, Quality Assurance RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 4.0, Reactor RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System ... further results
References
RC-18-0080
Download: ML18221A215 (31)

Text

18-i Reset May 20 18 TABLE OF CONTENTS Section Title Page 18.0 AGING MANAGEMENT PROGRAMS AND ACTIVITIES 18.1-1

18.1 INTRODUCTION

18.1-1 18.2 AGING MANAGEMENT PROGRAMS AND ACTIVITIES 18.2-1 18.2.1 10 CFR 50 Appendix J General Visual Inspection 18.2-1 18.2.2 10 CFR 50 Appendix J Leak Rate Testing 18.2-1 18.2.3 Above Ground Tank Inspection 18.2-2 18.2.4 Alloy 600 Aging Management Program 18.2-2 18.2.5 ASME Section XI ISI Program IWF 18.2-2 18.2.6 Battery Rack Inspection 18.2-2 18.2.7 Boric Acid Corrosion Surveillances 18.2-3 18.2.8 Bottom-Mounted Instrumentation Inspection 18.2-3 18.2.9 Buried Piping and Tanks Inspection 18.2-3 18.2.10 Chemistry Program 18.2-3 18.2.11 Containment Coating Monitoring and Maintenance Program 18.2-4 18.2.12 Containment ISI Program IWE/IWL 18.2-4 18.2.13 Diesel Generator Systems Inspection 18.2-4 18.2.14 Environmental Qualification (EQ) Program 18.2-5 18.2.15 Fire Protection Program 18.2-5 18.2.15.1 Mechanical 18.2-5 18.2.15.2 Fire Barriers and Fire Barrier Penetration Seals 18.2-6 18.2.15.3 Fire Doors 18.2-6 18.2.16 Flood Barrier Inspection 18.2-6 18.2.17 Flow-Accelerated Corrosion Monitoring Program 18.2-6 18.2.18 Non-EQ Insulated Cables and Connections Inspection Program 18.2-7 18.2.19 In-Service Inspection (ISI) Plan 18.2-7 18.2.20 Inspections for Mechanical Components 18.2-7 18.2.21 Liquid Waste System Inspection 18.2-8 18.2.22 Maintenance Rule Structures Program 18.2-8 18.2.23 Material Handling System Inspection Program 18.2-8 18.2.24 Pressure Door Inspection Program 18.2-9 18.2.25 Preventive Maintenance Activities

- Ventilation System Inspections 18.2-9 18.2.26 Reactor Building Cooling Units Inspection 18.2-9 18.2.27 Reactor Vessel Closure Studs Program 18.2-9 18.2.28 Reactor Vessel Internals Inspection 18.2-10 18.2.29 Reactor Vessel Surveillance Program 18.2-10 18.2.30 Service Air System Inspection 18.2-11 18.2.31 Service Water Pond Dam Inspection Program 18.2-11 18.2.32 Service Water Structures Survey Monitoring Program 18.2-11 18.2.33 Service Water System Reliability and In-Service Testing Program 18.2-12 18.2.34 Small Bore Class 1 Piping Inspection 18.2-12 18.2.35 Steam Generator Management Program 18.2-12 18.2.36 Tendon Surveillance Program 18.2-12 18.2.37 Thermal Fatigue Management Program 18.2-13 18.2.38 Underwater Inspection Program (SWIS and SWPH) 18.2-13 18.2.39 Waste Gas System Inspection 18.2-13 18.2.40 Heat Exchanger Inspections 18.2-13 18.2.41 Preventive Maintenance Activities

- Terry Turbine 18.2-14 18.2.42 Area Based Inspections For Refined 10 CFR 54.4(A)(2) Criteria 18.2-14 18-ii Reset May 20 18 TABLE OF CONTENTS (Continued)

Section Title Page 18.2.43 Aging Management Program for Electrical Cables Not Subject to 10CFR50.49 Environmental Qualification Requirements Used in Instrumentation Circuits 18.2-14 18.2.44 License Renewal Aging Management Program for Non

-EQ Electrical Cables Used in Instrumentation Circuits 18.2-15 18.2.45 Aging Management Program for Inaccessible Medium

-Voltage Cables Not Subject to 10CFR50.49 Environmental Qualification Requirements 18.2-15 18.3 TIME-LIMITED AGING ANALYSES (TLAA) EVALUATIONS 18.3-1 18.3.1 Reactor Vessel Neutron Embrittlement 18.3-1 18.3.1.1 Upper-Shelf Energy 18.3-1 18.3.1.2 Pressurized Thermal Shock 18.3-1 18.3.1.3 Pressure-Temperature (P

-T) Limits 18.3-2 18.3.2 Metal Fatigue 18.3-2 18.3.2.1 ASME Boiler and Pressure Vessel Code,Section III, Class 1 18.3-2 18.3.2.2 Leak-Before-Break Analyses 18.3-3 18.3.2.3 ASME Boiler and Pressure Vessel Code,Section III, Class 2 and 3 18.3-4 18.3.3 Environmental Qualification 18.3-4 18.3.4 Reactor Building Tendon Prestress 18.3-4 18.3.5 Reactor Building Liner 18.3-5 18.3.6 Other Plant

-Specific Time

-limited Aging Analyses 18.3-5 18.3.6.1 Crane Load Cycle Limit 18.3-5 18.3.6.2 Service Water Intake Structure Settlement 18.3-5 18.3.6.3 Reactor Coolant Pump Flywheel 18.3-6

18.4 REFERENCES

18.4-1 18-iii Reset May 2018 LIST OF TABLES Table Title Page 18.1-1 Summary Listing o f the Aging Management Programs and Activities 18.1-3 18.1-2 Summary Listing of the TLAA Evaluation for License Renewal 18.1-5 LIST OF FIGURES NONE LIST OF EFFECTIVE PAGES (LEP)

The following list delineates pages to Chapter 18 of the Virgil C. Summer Nuclear Station Final Safety Analysis Report which are current through May 20 18. The latest changes to pages and figures are indicated below by Revision Notice Number (RN) in the RN No. column along with the Month / Year of approval for each page and figure included in the Final Safety Analysis Report, Chapter 18.

18-iv Res et May 20 18 Page / Fig. No.

RN No. Date Page / Fig. No.

RN No. Date Page 18.i Reset May 2018 18.i i Reset May 2018 18.iii Reset May 2018 18.iv Reset May 2018 Page 18.1-1 RN04-019 January 2005 18.1-2 RN04-019 January 2005 18.1-3 RN04-019 January 2005 18.1-4 RN04-019 January 2005 18.1-5 RN04-019 January 2005 Page 18.2-1 RN04-019 January 2005 18.2-2 RN04-019 January 2005 RN18-019 May 2018 18.2-3 RN04-019 January 2005 18.2-4 RN04-019 January 2005 18.2-5 RN04-019 January 2005 RN18-019 May 2018 18.2-6 RN04-019 January 2005 18.2-7 RN04-019 January 2005 18.2-8 RN04-019 January 200 5 18.2-9 RN04-019 January 2005 18.2-10 RN04-019 January 2005 18.2-11 RN04-019 January 2005 18.2-12 RN04-019 January 2005 18.2-13 RN04-019 January 2005 18.2-14 RN04-019 January 2005 18.2-15 RN04-019 January 2005 Page 18.3-1 RN0 9-0 08 May 2009 18.3-2 RN09-008 May 2009 18.3-3 RN04-019 January 2005 18.3-4 RN04-019 January 2005 18.3-5 RN04-019 January 2005 18.3-6 RN04-019 January 2005 18.3-7 RN04-019 January 2005 Page 18.4-1 RN04-019 January 2005 RN18-019 May 2018

"Aging Management Program for Electrical Cables Not Subject to 10CFR50.49 Environmental Qualification Requirements Used in Instrumentation Circuits"

"License Renewal Aging Management Program for Non-EQ Electrical Cables Used in Instrumentation Circuits"