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ASME Section II +  and ASME Section III +

Carbon +  and Hydrogen +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 5 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +  and 10 CFR 50.54#f +

05000391  +  and 00391  +

Tennessee Valley Authority +  and Bajestani M +

NRC Generic Letter 04-02 +, NRC Generic Letter 2006-03 +, NRC Generic Letter 03-02 +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +, ML082750019 +...

ML080320443 +, IR 05000391/2008007 +, ML072570678 +, ML081560183 +  and NRC Generic Letter 1988-18 +

Parker Hannifin +  and Westinghouse +

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-0966 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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 +  and NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +

ML082750019 +  and ML082750019 +

Regulatory Guide 1.97 +, Regulatory Guide 1.82 +, Regulatory Guide 1.106 +  and Regulatory Guide 1.99 +

Tennessee +, Georgia +, Maryland +, Washington +  and California +

Steam Generator +, Service water +, HVAC +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Fire Barrier +, Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, Hemyc +, Control of Heavy Loads +, Fire Protection Program +, Water hammer +  and Leak Before Break +