ML21109A076
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PBAPS UFSAR APPENDIX R - SECOND LICENSE RENEWAL AGING MANAGEMENT UFSAR SUPPLEMENT TABLE OF CONTENTS SECTION TITLE R.
1.0 INTRODUCTION
R.1.1 NUREG-2191 Chapter XI Aging Management Programs R.1.2 Plant-Specific Aging Management Programs R.1.3 NUREG-2191 Chapter X Aging Management Programs R.1.4 Time-Limited Aging Analyses R.1.5 Quality Assurance Program and Administrative Controls R.1.6 Operating Experience R.2.0 AGING MANAGEMENT PROGRAMS R.2.1 NUREG-2191 Chapter XI Aging Management Programs R.2.1.1 ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD R.2.1.2 Water Chemistry R.2.1.3 Reactor Head Closure Stud Bolting R.2.1.4 BWR Vessel ID Attachment Welds R.2.1.5 BWR Stress Corrosion Cracking R.2.1.6 BWR Penetrations R.2.1.7 BWR Vessel Internals R.2.1.8 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)
R.2.1.9 Flow-Accelerated Corrosion R.2.1.10 Bolting Integrity R.2.1.11 Open-Cycle Cooling Water System R.2.1.12 Closed Treated Water Systems R.2.1.13 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems R.2.1.14 Compressed Air Monitoring R.2.1.15 BWR Reactor Water Cleanup System R.2.1.16 Fire Protection R.2.1.17 Fire Water System R.2.1.18 Outdoor and Large Atmospheric Metallic Storage Tanks R.2.1.19 Fuel Oil Chemistry R.2.1.20 Reactor Vessel Material Surveillance R.2.1.21 One-Time Inspection R.2.1.22 Selective Leaching R.2.1.23 ASME Code Class 1 Small-Bore Piping Appendix R R-i Rev. 28, APRIL 2021
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
R.2.1.24 External Surfaces Monitoring of Mechanical Components R.2.1.25 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components R.2.1.26 Lubricating Oil Analysis R.2.1.27 Monitoring of Neutron-Absorbing Materials Other Than Boraflex R.2.1.28 Buried and Underground Piping and Tanks R.2.1.29 Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks R.2.1.30 ASME Section XI, Subsection IWE R.2.1.31 ASME Section XI, Subsection IWF R.2.1.32 10 CFR Part 50, Appendix J R.2.1.33 Masonry Walls R.2.1.34 Structures Monitoring R.2.1.35 Inspection of Water-Control Structures Associated with Nuclear Power Plants R.2.1.36 Protective Coating Monitoring and Maintenance R.2.1.37 Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements R.2.1.38 Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits R.2.1.39 Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements R.2.1.40 Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements R.2.1.41 Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements R.2.1.42 Metal Enclosed Bus R.2.1.43 Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements R.2.2 Plant-Specific Aging Management Programs R.2.2.1 Wooden Pole R.3.0 NUREG-2191 CHAPTER X AGING MANAGEMENT PROGRAMS R.3.1 Evaluation of Chapter X Aging Management Programs R.3.1.1 Fatigue Monitoring R.3.1.2 Neutron Fluence Monitoring R.3.1.3 Environmental Qualification of Electric Equipment R.4.0 TIME-LIMITED AGING ANALYSES R.4.1 Identification and Evaluation of Time-Limited Aging Analyses R.4.2 Reactor Vessel and Internals Neutron Embrittlement Analyses Appendix R R-ii Rev. 28, APRIL 2021
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
R.4.2.1 Reactor Vessel and Internals Neutron Fluence Analyses R.4.2.2 Reactor Vessel Upper-Shelf Energy (USE) Analyses R.4.2.3 Reactor Vessel Adjusted Reference Temperature (ART) Analyses R.4.2.4 Reactor Vessel Pressure-Temperature (P-T) Limits R.4.2.5 Reactor Vessel Circumferential Weld Failure Probability Analyses R.4.2.6 Reactor Vessel Axial Weld Failure Probability Analyses R.4.2.7 Reactor Vessel Reflood Thermal Shock Analysis R.4.2.8 Core Shroud Reflood Thermal Shock Analysis R.4.2.9 Core Plate Rim Hold-Down Bolt Loss of Preload Analysis R.4.2.10 Jet Pump Slip Joint Repair Clamp Loss of Preload Analysis R.4.2.11 Jet Pump Auxiliary Spring Wedge Assembly Loss of Preload Analysis R.4.2.12 Jet Pump Riser Repair Clamp Loss of Preload Analysis R.4.2.13 Replacement Core Plate Extended Life Plug Irradiation-Enhanced Stress Relaxation Analysis R.4.2.14 First License Renewal Application Core Shroud IASCC and Embrittlement Analysis R.4.2.15 Unit 3 Core Spray Replacement Piping Bolting Loss of Preload Evaluation R.4.3 Metal Fatigue Analyses R.4.3.1 Transient Cycle and Cumulative Usage Projections for 80 years R.4.3.2 ASME Section III, Class 1 Fatigue Analyses R.4.3.3 ASME Section III, Class 1 Fatigue Waivers R.4.3.4 ASME Section III, Class 2 and 3 and ANSI B31.1 Allowable Stress Analyses R.4.3.5 Environmental Fatigue Analyses for RPV and Class 1 Piping R.4.3.6 Reactor Vessel Internals Fatigue Analyses R.4.3.7 High-Energy Line Break (HELB) Analyses Based on Cumulative Fatigue Usage R.4.3.8 Inservice 60-Year RPV Closure Head Weld Flaw Analyses R.4.4 Environmental Qualification of Electric Equipment R.4.4.1 Environmental Qualification of Electric Equipment R.4.5 Concrete Containment Tendon Prestress Analysis R.4.5.1 Concrete Containment Tendon Prestress Analysis R.4.6 Primary Containment Fatigue Analyses R.4.6.1 Primary Containment Structures, Penetrations, and Associated Components with Fatigue Analyses R.4.6.2 Containment Process Line Penetration Bellows R.4.7 Other Plant-Specific Time-Limited Aging Analyses R.4.7.1 Cranes Cyclic Loading Analyses R.4.7.2 Reactor Vessel Main Steam Nozzle Clad Removal Corrosion Allowance Appendix R R-iii Rev. 28, APRIL 2021
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
R.4.7.3 Generic Letter 81-11 Crack Growth Analysis to Demonstrate Conformance to the Intent of NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking R.4.7.4 Fracture Mechanics analysis of ISI-Reportable Indications for Group I Piping: As-forged Laminar Tear in a Unit 3 Main Steam Elbow Near Weld 1-B-3BC-LDO Discovered During Preservice UT R.4.7.5 Unit 3 Core Spray Replacement Piping Fatigue and Leakage Assessment R.5.0 SECOND LICENSE RENEWAL COMMITMENT LIST Appendix R R-iv Rev. 28, APRIL 2021