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IWB-3514 +, IWB-2500 +, IWB-3523 +, IWA-5250 +  and IWA-5242 +

L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003 +, L-02-121, Updated Information Regarding Bulletin 2001-01 & Bulletin 2002-01 +, L-01-136 +, L-02-066, Risk-Informed Inservice Inspection Program Plans, ISI (Inservice Inspection) Program Relief Request +, L-02-055, 60-Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-02-054, Reply to Request for Information Concerning Beaver Valley Power Station Responses to NRC Bulletins 2001-01 & 2002-01 +, L-02-040, Supplemental Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-02-021, Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles +, L-01 +  and L-02-032, Equivalent Usage Factor for Equipment Qualification +

05000334  +, 05000412  +, 00334  +  and 00412  +

Bezilla M +  and FirstEnergy +

ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +, ML030280081 +  and ML030280081 +

L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003 +, L-02-121, Updated Information Regarding Bulletin 2001-01 & Bulletin 2002-01 +, L-01-136 +, L-02-066, Risk-Informed Inservice Inspection Program Plans, ISI (Inservice Inspection) Program Relief Request +, L-02-055, 60-Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-02-054, Reply to Request for Information Concerning Beaver Valley Power Station Responses to NRC Bulletins 2001-01 & 2002-01 +, L-02-040, Supplemental Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-02-021, Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles +, L-01 +  and L-02-032, Equivalent Usage Factor for Equipment Qualification +

NRC Bulletin 02-01 +  and NRC Bulletin 01-01 +

2OST-6 +, 1OST-6 +  and 20ST-6 +

Beaver Valley +  and NPF-73 +

Washington +  and Ohio +

Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Non-Destructive Examination +, VT-2 +, Stress corrosion cracking +, Pressure Boundary Leakage +, Pressure boundary leak +, Dissimilar Metal Weld +, Unidentified leakage +  and Unidentified leak +