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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

ANSI N-18.1 +  and ANSI-18.1 +

Lead +  and Carbon +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 59.49 +  and 10 CFR 50.54#f +

05000260  +  and 00259  +

Gears G +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +  and NRC Generic Letter 88-19, Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material +

ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +, ML19330D064 +...

ML031150236 +, ML18033A833 +, ML18033A791 +, ML18033A512 +, ML18033A340 +, ML18033A184 +, ML18033A167 +, ML18033A165 +, ML18032A737 +, ML18032A659 +, ML18031B291 +, ML18031B137 +, ML18031B036 +, ML18024A997 +, ML18024A978 +, ML18029A536 +, ML20148B956 +, ML20153G803 +, ML20153E148 +, IR 05000259/1987045 +, IR 05000259/1988031 +, ML20155C932 +, IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl +, ML20245A735 +, IR 05000259/1989021 +, ML20247M468 +, IR 05000259/1988035 +, IR 05000259/1987031 +, 05000260/LER-1989-020, :on 890702,logic Circuit Deenergized During Replacement of Fuse Resulting in Isolation of Reactor Zone Ventilation.Caused by Electricians Incorrectly Jumpering Fuse Prior to Removal.Instruction Revised +, 05000259/LER-1988-036-01, :on 881018,two Possible Unanalyzed Electrical Loading on Safety Related Electrical Sys Identified.Caused by Inadequate Design Control & Review Program.Accident Signals from Units 1 & 2 Disabled +...

NRC Bulletin 79-14 +, NRC Bulletin 87-01 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-3232 +, NUREG-20555 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +, NuREG-1232 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

RT +, TP +, Emergency Operating Procedure +  and RT-in +

Regulatory Guide 1.97 +, Regulatory Guide 1.60 +  and Regulatory Guide 1.61 +

1c-failure +  and 07-85-038 +

Tennessee +, Maryland +, Washington +, California +, Alabama +  and New York +

Secondary containment +, Service water +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Decay Heat Removal +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Probabilistic Risk Assessment +, Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Earthquake +, Biofouling +  and Fire Protection Program +