ML19150A504

Revision 28 to Updated Final Safety Analysis Report, Chapter 18, Table of Contents

ML19150A504
Person / Time
Site:	Ginna
Issue date:	05/10/2019
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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GINNA/UFSAR 18 UPDATED FINAL SAFETY ANALYSIS REPORT 1 SUPPLEMENT FOR LICENSE RENEWAL

18.1 INTRODUCTION

2 18.1.1 RENEWED FACILITY OPERATING LICENSE 2 18.1.2 UPDATED FINAL SAFETY ANALYSIS REPORT SUPPLEMENT 2 18.1.3 STRUCTURES, SYSTEMS, OR COMPONENTS ADDED SUBSE- 2 QUENT TO RENEWED LICENSE 18.2 Programs that Manage the Effects of Aging 5 18.2.1 Aging Management Programs 5 18.2.1.1 Aboveground Carbon Steel Tanks 5 18.2.1.2 ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspec- 5 tion 18.2.1.3 ASME Section XI, Subsections IWE & IWL Inservice Inspection 5 18.2.1.4 ASME Section XI, Subsection IWF Inservice Inspection 6 18.2.1.5 Bolting Integrity 6 18.2.1.6 Boric Acid Corrosion 6 18.2.1.7 Buried Piping and Tanks Inspection 6 18.2.1.8 Closed-Cycle (Component) Cooling Water System 6 18.2.1.9 Electrical Cables and Connections Not Subject to 10 CFR 50.49 Envi- 7 ronmental Qualification Requirements 18.2.1.10 Electrical Cables Not Subject to 10CFR50.49 Environmental Qualifi- 7 cation Requirements Used In Instrument Circuits 18.2.1.11 Fire Protection 7 18.2.1.12 Fire Water System 7 18.2.1.13 Flow-Accelerated Corrosion 7 18.2.1.14 Fuel Oil Chemistry 8 18.2.1.15 Inaccessible Medium-Voltage Cables Not Subject to 10CFR50.49 8 Environmental Qualification Requirements 18.2.1.16 Inspection of Overhead Heavy Load and Light Load (Related to Refu- 8 eling) Handling Systems 18.2.1.17 One-Time Inspection 8 18.2.1.18 Open-Cycle Cooling (Service) Water System 9 18.2.1.19 Periodic Surveillance and Preventive Maintenance 9 18.2.1.20 Nickel-Alloy Nozzles and Penetrations Inspection 9 Page 1 of 3 Revision 28 5/2019

GINNA/UFSAR 18 UPDATED FINAL SAFETY ANALYSIS REPORT 1 SUPPLEMENT FOR LICENSE RENEWAL 18.2.1.21 Reactor Vessel Internals 9 18.2.1.22 Reactor Vessel Surveillance 10 18.2.1.23 Spent Fuel Pool Neutron Absorber Monitoring 10 18.2.1.24 Steam Generator Integrity 10 18.2.1.25 Structures Monitoring 10 18.2.1.26 Monitoring 10 18.2.1.27 Thimble Tubes Inspection 10 18.2.1.28 Water Chemistry Control 11 18.3 Evaluation of Time-Limited Aging Analyses 12 18.3.1 Reactor Vessel Neutron Embrittlement 12 18.3.1.1 Upper Shelf Energy 12 18.3.1.2 Pressurized Thermal Shock 12 18.3.1.3 Pressure-Temperature Limits 13 18.3.2 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel 13 (CASS) 18.3.3 Metal Fatigue 14 18.3.3.1 ASME Boiler and Pressure Vessel Code,Section III, Class 1 14 18.3.3.2 Reactor Vessel Underclad Cracking 15 18.3.3.3 ANSI B31.1 Piping 15 18.3.3.4 Accumulator Check Valves 16 18.3.3.5 Environmentally Assisted Fatigue 16 18.3.3.6 Reactor Vessel Nozzle-to-Weld Defect 17 18.3.3.7 Pressurizer Fracture Mechanics Analysis 17 18.3.4 Environmental Qualification of Electric Equipment 18 18.3.5 Concrete Containment Tendon Prestress 19 18.3.5.1 Containment Tendon Fatigue 19 18.3.5.2 Containment Tendon Bellows Fatigue 19 18.3.6 Containment Liner Plate and Penetration Fatigue 20 18.3.6.1 Containment Liner Anchorage Fatigue 20 18.3.7 Containment Liner Stress 20 18.3.8 Other Time-Limited Aging Analyses 21 Page 2 of 3 Revision 28 5/2019

GINNA/UFSAR 18 UPDATED FINAL SAFETY ANALYSIS REPORT 1 SUPPLEMENT FOR LICENSE RENEWAL 18.3.8.1 Crane Load Cycle Limit 21 18.3.8.2 Reactor Coolant Pump (RCP) Flywheel 21 18.3.9 Exemptions 21 18.4 TLAA Supporting Activities 22 18.4.1 Concrete Containment Tendon Prestress 22 18.4.2 Environmental Qualification Program 22 18.4.3 Fatigue Monitoring Program 22 Page 3 of 3 Revision 28 5/2019