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Boron +, Uranium +, Carbon +  and Hydrogen +

10 CFR 50.49 +, 10 CFR 50.54#f +  and 10 CFR 3.11 +

05000391  +, 00391  +  and 00390  +

Tennessee Valley Authority +  and Bajestani M +

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 +...

ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +, ML072570678 +...

ML072190047 +, ML070250345 +, NRC Generic Letter 1985-22 +, NRC Generic Letter 1995-09 +, ML031070150 +, ML050930031 +  and ML043080413 +

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

NRC Bulletin 80-04 +, NRC Bulletin 88-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 79-27 +, 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 79-19 +, NRC Bulletin 83-03 +, NRC Bulletin 82-02 +, NRC Bulletin 84-02 +, NRC Bulletin 80-06 +, NRC Bulletin 87-01 +, NRC Bulletin 78-01 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +, NRC Bulletin 88-11 +, NRC Bulletin 80-25 +, NRC Bulletin 88-08 +, NRC Bulletin 77-06 +, NRC Bulletin 79-24 +, NRC Bulletin 85-02 +, NRC Bulletin 74-03 +, NRC Bulletin 84-03 +, NRC Bulletin 76-02 +...

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG/CR-4005 +, NUREG/CR-4933 +, NUREG/CR-5292 +, NUREG/CR-5297 +, NUREG/CR-4934 +, NUREG/CR-5287 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

6A-C +, 3B-K +  and 4X-C +

Tennessee +, Georgia +, Maryland +  and Washington +

Steam Generator +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Fire Barrier +, Scram Discharge Volume +, Stress corrosion cracking +, Loss of Offsite Power +, Hemyc +, Control of Heavy Loads +, Fuel cladding +, Brachytherapy +, Subsequent actuation +  and Control Room Habitability +