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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

10 CFR 50 Appendix R +, 10 CFR 50.72 +, 10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +  and 10 CFR 50.65#a4 +

S. Bono +, L. Hughes +, P. Chadwell +, D. Robinson +, J. Emens +, M. Floyd +, R. Givens +, M. Palmer +, A. Feltman +, J. Underwood +, B. Pierce +, E. Quinn +, J. Randich +, P. Sawyer +, S. Berry +, J. Black +, M. Button +, F. Godwin +, J. McCarthy +, R. Rogers +, R. West +, T. Brumfield +, M. Cantrell +, D. Feldman +, S. Cephus +, E. Frevold +, A. Elms +, R. Nacoste +  and Jeffrey Mitchell +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +  and Mitigating Systems +

H.14 +  and P.2 +

05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +

Turbine Trip +  and Reactor Trip +

05000259/FIN-2009002-02 +, 05000259/FIN-2009002-03 +, 05000259/FIN-2009002-04 +, 05000259/FIN-2007004-01 +, 05000259/FIN-2007005-01 +  and 05000260/FIN-2009002-04 +

Eugene Guthrie +  and Reactor Projects Region 2 Branch 6 +

IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +, IR 05000259/2009002 +...

NRC Inspection Manual 0609 +  and IMC 0305, Operating Reactor Assessment Program +

IP 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000259/2009002 +, IR 05000259/2008005 +, IR 05000259/2007004 +  and IR 05000259/2007005 +

05000259/LER-2008-003, Regarding Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure +, 05000259/LER-2008-002, ASME Code Class 1 Pressure Boundary Leak on an Instrument Line Connected to the Reactor Vessel +, 05000260/LER-2008-001, Regarding Automatic Turbine Trip and Reactor Scram Resulting from a Failure of the Design Change Process +, 05000259/LER-2007-007, Regarding Automatic Reactor Scram from a Neutron Monitoring Trip Signal +  and 05000259/LER-2007-002, Regarding Manual Scram Due to an Unisolable EHC Leak +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +

Manual Scram +  and Automatic Scram +

Tennessee +, Georgia +, Washington +  and Alabama +

Reactor Coolant System +, Secondary containment +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Stator Cooling Water +, Emergency Equipment Cooling Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +  and Main Steam +

05000498/TS-3.4.3 +, 05000498/TS-5.4.1 +  and 05000498/TS-3.4.4.a +

Tennessee Valley Authority +  and Swafford P +

Safe Shutdown +, Reactor Vessel Water Level +, Packing leak +, Fire Barrier +, Weld Overlay +, Nondestructive Examination +, Condition Adverse to Quality +, Corrosion bonding +, Significance Determination Process +, Intergranular Stress Corrosion Cracking +, Pressure boundary leak +, Through Wall Leak +, Downpower +  and Unidentified leakage +