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Letter  and Inspection Report

ASME Section XI +  and ASME Section V +

10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 65#a1 +, 10 CFR 55.59#a2 +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +  and 10 CFR 50.65#a4 +

John Dixon +, S. Douglas +, J. Lewis +, D. Madison +, M. Ajluni +, R. Varnadore +, J. Hammonds +, M. Googe +  and Jacqueline Thompson +

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

05000321  +, 05000366  +, 00321  +  and 00366  +

Scott Shaeffer +  and NRC/RGN-II/DRP/RPB2 +

IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +, IR 05000321/2006002 +...

05000366/LER-2005-002, Unit 2 Re Secondary Containment Bypass Leakage Requirements Exceeded +  and 05000321/LER-2005-001, Regarding Failure to Use an Appendix J, Option B, Type C Tested Component to Isolate Primary Containment Penetration +

1R22-S003 +, 1B31-1RC-12B +, 42SV-TET-001-0 +, 1P70-N003 +, 34GO-OPS-066-0 +, 34SV-E51-002-1 +, 1B31-1RC-28B-9 +, 1B21-1FW-12A +, 90AC-OAM-002-0 +, 34SV-R43-002-1 +, 10AC-MGR-019-0 +, 34SV-C11-003-2 +, 40AC-ENG-018-0 +, 52PM-E11-009-1 +, 1B31-1RC-28B-1 +, 1E11-1RHR-24A-R-13 +, 1B21-1FW-18A-15 +, 1N11-TBH-22 +, 34AB-E11-001-0 +, 34SV-E11-002-2 +  and 52SV-E41-003-0 +

Georgia +  and Washington +

Reactor Coolant System +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Circulating Water System +, Residual Heat Removal Service Water +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Southern Nuclear +  and Summer H +

Shutdown Margin +, Weld Overlay +, Nondestructive Examination +, Temporary Modification +, Significance Determination Process +, Feedwater Heater +, Liquid penetrant +, Operability Assessment +  and Overspeed trip +