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Letter  and Inspection Report

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 50.65#a4 +, 10 CFR 50.48#c +, 10 CFR 50.48#b1 +  and 10 CFR 2.390#d1 +

K. Polson +, E. Bates +, J. Paul +, C. Vaughn +, L. Hughes +, M. Oliver +, R. Guthrie +, V. Schiavone +, P. Campbell +, D. Campbell +, J. Lacasse +, M. Roy +, D. Green +, A. Yarborough +, P. Donahue +, T. Mingus +, S. Samaras +, S. Norris +, J. Emens +, J. Boyer +, W. Byrne +, A. Gallegos +, S. Wentzel +, Diane Jackson +, Michael Webb +, Donna Ford +  and Lugo Soly Soto +

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

H.8 +  and P.2 +

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

Turbine Trip +  and Reactor Trip +

05000296/FIN-2013004-04 +  and 05000260/FIN-2013003-03 +

Croteau R +  and Division Reactor Projects II +

IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +, IR 05000259/2013004 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00465 d (0.112 hours, 6.646825e-4 weeks, 1.52961e-4 months)  +  and 0.0152 d (0.365 hours, 0.00217 weeks, 4.995965e-4 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix A +, NRC Inspection Manual 0609/Appendix F +, IMC 0305, Operating Reactor Assessment Program +  and IMC 0310, Aspects within the Cross-Cutting Areas +

05000259/LER-2013-002, Regarding Manual Reactor Shutdown Due to Decreasing Condenser Vacuum +, 05000260/LER-2013-001, Regarding Inoperable Stop-Check Valve Results in Condition Prohibited by Technical Specifications and Reactor Shutdown Required by Technical Specifications +  and 05000296/LER-2013-003, Regarding Automatic Reactor Shutdown Due to an Actuation of the Reactor Protection System from a Turbine Trip +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

Tennessee +  and Washington +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Main Condenser +  and Low Pressure Coolant Injection +

TS-3.7.1 +, TS-5.4.1.a +  and TS-3.7.1.C +

Tennessee Valley Authority +  and James Shea +

Hot Short +, Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Past operability +, Enforcement Discretion +, Probabilistic Risk Assessment +, Operator Manual Action +, Functionality Assessment +, Significance Determination Process +, Feedwater Heater +, Excess Flow Check Valve +, Operability Determination +, Fuel cladding +, Fire Protection Program +, Downpower +  and Loss of condenser vacuum +

WO 114863764 +, WO 114844701 +, WO 114422086 +, WO 114087239 +, WO 114395313 +, WO 114500098 +, WO 114489624 +  and WO 113809831 +