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Letter, Report  and Miscellaneous

ASME Section III +, ASME Section IV +  and ASME Section II +

Boron +, Iodine +, Uranium +, Carbon +, Hydrogen +, Chlorine +  and Lead +

10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 71 +, 10 CFR 16 +, 10 CFR 2.109 +, 10 CFR 11.3, Scope +, 10 CFR 11.5, Policy +, 10 CFR 19.12 +, 10 CFR 20.1201 +, 10 CFR 50.33 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50.68 +, 10 CFR 50 Appendix I +, 10 CFR 61.55 +, 10 CFR 100.11 +, 10 CFR 50.46a#b +, 10 CFR 50.54 +, 10 CFR 1101#b +, 10 CFR 50.55a +, 10 CFR 50.49#e +, 10 CFR 50.54#f +, 10 CFR 50.34#b6iii +...

Emergency Preparedness +  and Physical Protection +

05000391  +  and 00391  +

Tennessee Valley Authority +  and Mccollum W +

GDC 41 +, GDC 15 +, GDC 50 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 61 +, GDC 14 +, GDC 60 +, GDC 13 +, GDC 6 +, GDC 64 +, GDC 62 +, GDC 8 +, GDC 32 +, GDC 52 +, GDC 36 +, GDC 51 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 04-02 +, NRC Generic Letter 99-02 +, NRC Generic Letter 07-01 +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 98-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 2006-03 +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 77-07, Reliability Of Standby Diesel Generator Units +, NRC Generic Letter 77-06, Enclosing Questionaire Relating to Steam Generators +, NRC Generic Letter 78-34, Reactor Vessel Atypical Weld Material +, NRC Generic Letter 78-15, Task Action Plan for Category A Technical Activity No. A-36, "Control of Heavy Loads Near Spent Fuel" +, NRC Generic Letter 78-09, Multiple-Subsequent Actuations of Safety/Relief Valves Following an Isolation Event +, NRC Generic Letter 78-04, GAO Blanket Clearance For Letter Dated 12/09/77 +, NRC Generic Letter 78-03, Request For Information On Cavity Annulus Seal Ring +, NRC Generic Letter 78-02, Asymmetric Loads Background & Revised Request For Additional Information +, NRC Generic Letter 79-58, ECCS Calculations on Fuel Cladding +, NRC Generic Letter 79-57, Acceptance Criteria for the Mark I Containment Long Term Program +, NRC Generic Letter 79-52, Radioactive Release at North Anna Unit 1 and Lessons Learned +, NRC Generic Letter 79-46, Containment Purging and Venting During Normal Operation – Guidelines for Valve Operability +, NRC Generic Letter 79-42, Potential Unreviewed Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems +, NRC Generic Letter 79-36, Adequacy of Station Electric Distribution Systems Voltages +, NRC Generic Letter 79-24, Multiple Equipment Failures in Safety-Related Systems +, NRC Generic Letter 79-20, Cracking in Feedwater Lines +, NRC Generic Letter 80-95, Generic Activity A-10 +, NRC Generic Letter 80-90, Post TMI Requirements, NUREG-0737 +, NRC Generic Letter 80-84, BWR Scram System +, NRC Generic Letter 80-77, Refueling Water Level +...

ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +, ML072190047 +  and ML072190047 +

IEEE 279-1971 +  and IEEE 308-1971 +

Cutler-Hammer +, Westinghouse +, Valcor +, General Electric +  and Target Rock +

NRC Bulletin 03-01 +, NRC Bulletin 80-04 +, NRC Bulletin 05-01 +, NRC Bulletin 88-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 04-01 +, NRC Bulletin 79-27 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 88-09 +, NRC Bulletin 79-15 +, NRC Bulletin 05-02 +, NRC Bulletin 79-19 +, NRC Bulletin 83-03 +, NRC Bulletin 03-02 +, NRC Bulletin 82-02 +, NRC Bulletin 84-02 +, NRC Bulletin 96-03 +, NRC Bulletin 80-06 +, NRC Bulletin 87-01 +, NRC Bulletin 78-01 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +...

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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 +

SP +  and CP +

Regulatory Guide 1.97 +, Regulatory Guide 1.84 +, Regulatory Guide 1.106 +, Regulatory Guide 1.6 +, Regulatory Guide 1.26 +  and Regulatory Guide 1.68 +

6A-C +, 3B-K +  and 4X-C +

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

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Shield Building +, Main Steam Safety Valve +, Emergency Gas Treatment System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-5.5.2 +  and TS-4.3.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Coatings +, Anchor Darling +, Operating Basis Earthquake +, Scram Discharge Volume +, Stress corrosion cracking +, Hemyc +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Offsite Circuit +, Fire Protection Program +, Flow Induced Vibration +, Subsequent actuation +, Loss of condenser vacuum +, Control Room Habitability +  and Leak-Before-Break +