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Letter  and Inspection Report

Lead +  and Platinum +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50.71 +, 10 CFR 50.90 +, 10 CFR 55.46 +, 10 CFR 73.54 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50.73#a2iB +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 50.65#a4 +, 10 CFR 55.46#c1 +, 10 CFR 55.46#ci +, 10 CFR 55.46#cii +, 10 CFR 50.71#e +  and 10 CFR 50.71#e4 +

K. Polson +, E. Bates +, S. Bono +, J. Paul +, L. Hughes +, M. Oliver +, L. Slizewski +, M. Kirschenheiter +, R. Guthrie +, R. Cox +, P. Campbell +, J. Kulisek +, D. Campbell +, J. Lacasse +, M. Roy +, W. Ball +, S. Brooks +, R. Robertson +, P. Steele +, J. Stone +, Z. Taylor +, L. Vandiver +, James Smith +, Alexandra Smith +  and Donna Ford +

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

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

ML14227A671 +, ML13224A263 +, ML15098A114 +  and CNL-14-127, Response to Request for Additional Information Related to Potential Loss of Spent Fuel Pool Cooling +

05000296/FIN-2015001-04 +, 05000296/FIN-2015001-06 +, 05000296/FIN-2015001-05 +  and 05000296/FIN-2013004-04 +

Mark King +  and Reactor Projects Region 2 Branch 6 +

NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +, IR 05000259/2015001 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 0.0152 d (0.365 hours, 0.00217 weeks, 4.995965e-4 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IR 05000259/2015001 +  and IR 05000296/2014009 +

05000260/LER-2014-001 +, 05000259/LER-2014-006, Regarding Main Steam Relief Valves Lift Settings Outside Technical Specifications Required Setpoint +, 05000296/LER-2013-003, Regarding Automatic Reactor Shutdown Due to an Actuation of the Reactor Protection System from a Turbine Trip +  and 05000259/LER-2013-001, Brown Ferry Nuclear Plant, Units 1, 2 and 3 Regarding Latent Design Input Inconsistencies Adversely Affect Probable Maximum Flood Analysis +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +

4kV +  and 4.16kV +

Tennessee +  and Washington +

Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Control Room Emergency Ventilation +, Fuel Pool Cooling and Cleanup +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

TS-3.8.1 +, TS-3.3.6.1 +, TS-3.6.1.3 +  and TS-3.4.3 +

Tennessee Valley Authority +  and James Shea +

Safe Shutdown +, Unanalyzed Condition +, Fire Barrier +, Time to boil +, Past operability +, Temporary Modification +, Functionality Assessment +, Corrosion bonding +, Significance Determination Process +, Design basis earthquake +, Foreign Material Exclusion +, Feedwater Heater +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Maintenance Rule Program +, Downpower +, Manual Operator Action +  and Loss of condenser vacuum +

WO 115875966 +, WO 113952175 +, WO 115375784 +, WO 115566455 +, WO 116591672 +, WO 11509348 +, WO 115668682 +, WO 115364501 +, WO 115613637 +, WO 115638091 +, WO 116399821 +, WO 116374283 +, WO 115753498 +, WO 115754799 +, WO 116003799 +, WO 115624029 +  and WO 115698548 +