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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

Carbon +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 55.25 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.54#q +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b2 +, 10 CFR 50.47#b4 +, 10 CFR 50.47#b14 +  and 10 CFR 50.75#g +

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

H.11 +  and P.2 +

05000390  +, 05000391  +, 00390  +  and 00391  +

Turbine Trip +  and Reactor Trip +

05000390/FIN-2008005-01 +, 05000390/FIN-2008005-02 +, 05000390/FIN-2008005-03 +, 05000390/FIN-2007007-01 +  and 05000390/FIN-2008005-04 +

Heather Gepford +  and Reactor Projects Region 2 Branch 6 +

ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +, ML090440261 +  and ML090440261 +

TI 2515/175 +  and TI 2525/175 +

NRC Inspection Manual 0609 +  and NRC Inspection Manual 0609/Appendix F +

IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71114, Reactor Safety Emergency Preparedness +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000390/2008003 +, IR 05000390/2008005 +  and IR 05000390/2008004 +

05000390/LER-2008-005, Inoperability of Radiation Monitor Due to Non-Conservative Setpoint +, 05000390/LER-2008-004, Automatic Reactor Trip in Response to Opening of Exciter Field Breaker +, 05000390/LER-2008-002, Manual Reactor Trip in Response to Start of Feedwater Heater Isolation +  and 05000390/LER-2008-003, Automatic Start of Auxiliary Feedwater Unavailable During Startup Entry Into Modes 2 and 1 +

Information Notice 92-28 +  and Information Notice 2005-24, Nonconservatism in Leakage Detection Sensitivity +

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +

2B-B +, 1A-A +, 2A-A +  and 2B-1B +

Manual Scram +  and Automatic Scram +

Tennessee +, Georgia +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Auxiliary Building Gas Treatment System +, Stator Water Cooling +, Circulating Water System +, Main Steam Line +  and Containment Spray +

TS-3.3.2 +, TS-3.4.15 +, TS-5.2.2.3 +  and TS-2.0.3 +

Tennessee Valley Authority +  and Swafford P +

Safe Shutdown +, Offsite Dose Calculation Manual +, Fire Barrier +, Past operability +, Enforcement Discretion +, Significance Determination Process +, Job Performance Measure +, Annual Radioactive Effluent Release Report +, Feedwater Heater +, Loss of Offsite Power +, Pressure boundary leak +, Fire Protection Program +, Downpower +, Leak-Before-Break +  and Spill +