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

ASME Section XI +, ASME Section III +, ASME Section I +  and ASME Section II +

Carbon +, Oxygen +, Hydrogen +, Chromium +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50.73 +, 10 CFR 21 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.49#b2 +, 10 CFR 50.49#b3 +, 10 CFR 50.49#c +, 10 CFR 50.49#2 +, 10 CFR 50.54#f +  and 10 CFR 50.55#e +

05000260  +, 00259  +, 00327  +  and 00390  +

Moran D +  and Office of Nuclear Reactor Regulation +

SIL 007 +, SIL 001 +, SIL 003 +, SIL 005 +, SIL 006 +, SIL 008 +, SIL 002 +  and SIL 004 +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +, NRC Generic Letter 84-01, NRC Use Of The Terms "Important To Safety" and "Safety Related" +  and NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +

ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +, ML18033A729 +...

ML17342B386 +, ML18033A512 +, ML18033A336 +, ML18033A302 +, ML18033A253 +, ML18033A171 +, ML18032A432 +, ML18031B063 +, ML18031A474 +, ML18283B369 +, ML20148G596 +, IR 05000259/1985018 +, ML20154Q779 +, IR 05000259/1988031 +, IR 05000259/1986036 +, 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 +, ML20260C006 +, IR 05000259/1987026 +, IR 05000259/1987039 +, IR 05000259/1988029 +, 05000259/LER-1984-008, :on 840129,trouble Alarms Annunciated in Reactor Protection Sys Analog Trip Units Due to Downscale Failure of Differential Transmitters.Caused by Instrument Sensing Line Snubbers.Snubbers Removed +, 05000260/LER-1987-006-03, :on 870821,discovered Fire Watch Asleep.On 870829,determined That Required Fire Watch Not Present for Grinding Activities.Caused by Area Temp & Poor Communication Between Fire Watch,Craft Personnel & Foreman +, 05000296/LER-1986-009-03, :on 860908,Loop I of RHR Sys Declared Inoperable After Damaged Hanger Discovered.Caused by High Vibration in Shutdown Cooling Mode.Hanger Repaired & Design Mod Will Be Performed +, 05000260/LER-1986-010-02, :on 860702,sensitive Ultrasonic Exam Revealed Crack Indications in Recirculation Sys Reactor Vessel Inlet Nozzle Safe Ends.Corrective Action Proposals Await Development of Acceptance Criteria +, 05000259/LER-1985-051-01, :on 850925,cable Connecting Reactor Protection Sys Panel 9-17 Supply Breaker to Terminal Block Dried & Insulation Cracked.Caused by Loose Breaker Connection. Defective Cable Replaced W/Larger Gauge Cables +, 05000259/LER-1988-033-02, :on 881004,discovered One Batch Sample to Be Included in Sept Monthly Composite Missing.Caused by Inadequate Procedures.Chemistry Procedures for Preparation of Composites Will Be Revised +, 05000260/LER-1987-002-03, :on 870218,drywell Structural Deficiencies Discovered.Caused by Const Differences Between as-built & Designed Drywell Platform.Platform to Be Inspected & Modified as Necessary +, 05000259/LER-1985-026, :on 850701,field Insp Determined Cable Tray Sections Not Seismically Qualified.Caused by Tray Overfill Condition.Potential Application of Alternate Seismic Approaches Re USI A-46 Considered +, 05000259/LER-1988-026-02, :on 880830,condition Adverse to Quality Rept Identified Tech Spec Violation Re Continuous Fire Watch When Fire Doors Blocked Open.Caused by Incorrect Mgt Decision. Fire Doors Closed & Mgt Directive Corrected.W/Undated Ltr +, 05000260/LER-1988-006-03, :on 880824,480-volt Shutdown Board Voltage Transient Initiated Esf.Caused by Voltage Drop on Shutdown Board 2B When LPCI MG Set Returned to Svc.Circuit Protector 2C2 Reset +...

NRC Bulletin 87-01 +, NRC Bulletin 80-07 +  and NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas +

NUREG-0061 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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 +  and 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 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.68 +

45N714-2 +  and 18H-related +

Tennessee +  and Washington +

Feedwater +, Service water +, Reactor Core Isolation Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Remote shutdown +, Emergency Equipment Cooling Water +, Control Rod +, Main Steam +  and Extraction steam +

Safe Shutdown +, Stroke time +, Probabilistic Risk Assessment +, Coatings +, Emergency Lighting +, Condition Adverse to Quality +, Abnormal operational transient +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Liquid penetrant +, Fire Protection Program +  and Operability Assessment +