ML18024A410

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Updated Final Safety Analysis Report (Ufsar), Amendment 27, Appendix O - Table of Contents
ML18024A410
Person / Time
Site: Browns Ferry  
Issue date: 10/05/2017
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18018A778 List: ... further results
References
Download: ML18024A410 (2)


Text

BFN-26 O.0-i APPENDIX O AGING MANAGEMENT PROGRAMS TABLE OF CONTENTS O.0 INTRODUCTION............................................................................................................................... O.1-1 O.1 AGING MANAGEMENT PROGRAMS.............................................................................................. O.1-1 O.1.1 Accessible Non-Environmental Qualification Cables and Connections Inspection Program.......................................................................................................................... O.1-1 O.1.2 Electrical Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits Program................................................ O.1-2 O.1.3 Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program....................................................... O.1-2 O.1.4 ASME Section XI Inservice Inspection Subsections IWB, IWC, and IWD Program........ O.1-3 O.1.5 Chemistry Control Program............................................................................................. O.1-3 O.1.6 Reactor Head Closure Studs Program........................................................................... O.1-3 O.1.7 Boiling Water Reactor Vessel Inside Diameter Attachment Welds Program................... O.1-3 O.1.8 Boiling Water Reactor Feedwater Nozzle Program......................................................... O.1-4 O.1.9 Boiling Water Reactor Control Rod Drive Return Line Nozzle Program.......................... O.1-4 O.1.10 Boiling Water Reactor Stress Corrosion Cracking Program............................................ O.1-4 O.1.11 Boiling Water Reactor Penetrations Program.................................................................. O.1-5 O.1.12 Boiling Water Reactor Vessel Internals Program............................................................ O.1-6 O.1.13 Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program (DELETED)................................................................................ O.1-6 O.1.14 Flow-Accelerated Corrosion Program............................................................................. O.1-6 O.1.15 Bolting Integrity Program................................................................................................. O.1-6 O.1.16 Open-Cycle Cooling Water System Program.................................................................. O.1-7 O.1.17 Closed-Cycle Cooling Water System Program................................................................ O.1-8 O.1.18 Inspection of Overhead Heavy Load and Light Load Handling Systems Program.......... O.1-8 O.1.19 Compressed Air Monitoring Program.............................................................................. O.1-8 O.1.20 BWR Reactor Water Cleanup System Program.............................................................. O.1-9 O.1.21 Fire Protection Program.................................................................................................. O.1-9 O.1.22 Fire Water System Program............................................................................................ O.1-9 O.1.23 Aboveground Carbon Steel Tanks Program.................................................................. O.1-10 O.1.24 Fuel Oil Chemistry Program.......................................................................................... O.1-10 O.1.25 Reactor Vessel Surveillance Program........................................................................... O.1-10 O.1.26 One-Time Inspection Program...................................................................................... O.1-11 O.1.27 Selective Leaching of Materials Program...................................................................... O.1-11 O.1.28 Buried Piping and Tanks Inspection Program............................................................... O.1-11 O.1.29 ASME Section XI Subsection IWE Program.................................................................. O.1-12 O.1.30 ASME Section XI Subsection IWF Program.................................................................. O.1-12 O.1.31 10 CFR 50 Appendix J Program................................................................................... O.1-13 O.1.32 Masonry Wall Program.................................................................................................. O.1-13 O.1.33 Structures Monitoring Program..................................................................................... O.1-13 O.1.34 Inspection of Water-Control Structures Program........................................................... O.1-14

BFN-26 O.0-ii O.1.35 Environmental Qualification Program............................................................................ O.1-14 O.1.36 Fatigue Monitoring Program.......................................................................................... O.1-14 O.2 PLANT SPECIFIC AGING MANAGEMENT PROGRAMS................................................................ O.2-1 O.2.1 Systems Monitoring Program.............................................................................................. O.2-1 O.2.2 Bus Inspection Program...................................................................................................... O.2-1 O.2.3 Diesel Starting Air Program................................................................................................ O.2-1 O.2.4 Unit 1 Periodic Inspection Program.................................................................................... O.2-2 O.3 TIME-LIMITED AGING ANALYSIS SUMMARIES............................................................................. O.3-1 O.3.1 Neutron Embrittlement of the Reactor Vessel and Internals............................................... O.3-1 O.3.2 Metal Fatigue...................................................................................................................... O.3-4 O.3.3 Environmental Qualification of Electrical Equipment........................................................... O.3-6 O.3.4 Containment Fatigue.......................................................................................................... O.3-6 O.3.5 Other Plant Specific Time-Limited Aging Analysis................................................................. O.3-6 O.4 10 CFR 54.37(b) NEWLY IDENTIFIED SYSTEMS, STRUCTURES, AND COMPONENTS............ O.4-1 O.4.1 Gate Structure Number 2.................................................................................................... O.4-1 O.4.2 Discharge Control Structure............................................................................................... O.4-2 O.5 REFERENCES.................................................................................................................................. O.5-1