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Letter  and Inspection Report

ASME Section XI +  and ASME Section V +

Boron +, Carbon +, Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.9 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.65#b +, 10 CFR 50.65#a4 +  and 10 CFR 50.75#g +

R. Bernhard +, B. Dungan +, M. Palmer +, N. Thomas +, T. Cleary +, Kelly Clayton +, D. Bodine +, C. Church +, B. Moroney +, Z. Kitts +, T. Marshall +, A. Little +, J. Proffitt +, K. Wilkes +, D. Boone +, L. Cross +, G. Morris +, K. Parker +, James Smith +  and Kenneth Jones +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

05000327  +, 05000328  +, 00327  +  and 00328  +

Nease R +  and Reactor Projects Region 2 Branch 6 +

NRC Generic Letter 04-02 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +

IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +, IR 05000327/2007005 +...

0.0116 d (0.278 hours, 0.00165 weeks, 3.805e-4 months)  +  and 0.00463 d (0.111 hours, 6.613757e-4 weeks, 1.522e-4 months)  +

TI 2515/166 +  and TI 2515/150 +

NRC Inspection Manual 0609 +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71151 +, IP 71122.02 +, IP 71122.01 +, IP 71121.02 +, IP 71121.01 +  and IP 71152, Problem Identification and Resolution (PI&R) +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1608 +

1B-B +  and 1A-A +

Tennessee +  and Washington +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Main Condenser +  and Control Rod +

Tennessee Valley Authority +  and Campbell W +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Locked High Radiation Area +, Significance Determination Process +, Foreign Material Exclusion +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Integrated leak rate test +, Eddy Current Testing +, Control of Heavy Loads +, Fuel cladding +, Through-Wall Leakage +, Grace period +  and Unidentified leakage +