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Letter, Inspection Report  and Notice of Violation

ASME Section XI +, ASME Section IV +, ASME Section V +  and ASME Section VII +

Magnesium +  and Iron +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.9 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#b5 +, 10 CFR 55.59#a2 +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +  and 10 CFR 50.65#a4 +

T. Marlow +, K. Polson +, S. Bono +, M. McAndrew +, J. Colvin +, G. Doyle +, J. Morris +, K. Groom +, S. Austin +, P. Donahue +, M. Rasmussen +, T. Albright +, W. Baker +, P. Chase +, M. Durr +, J. Emens +, J. Boyer +, W. Byrne +, M. Ellet +, R. King +, R. Norris +, A. Feltman +, S. Kelly +, J. Underwood +, S. Walton +, O. Brooks +, N. Gannon +, D. Malinowski +, W. Nurnberger +, W. Pearce +...

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

H.7 +, P.2 +  and P.3 +

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

05000296/FIN-2010003-03 +, 05000259/FIN-2010005-01 +, 05000296/FIN-2010003-02 +, 05000296/FIN-2010005-03 +  and 05000259/FIN-2010005-02 +

Croteau R +  and Division Reactor Projects II +

IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +, IR 05000259/2010005 +...

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 0.00109 d (0.0261 hours, 1.554233e-4 weeks, 3.5767e-5 months)  +, 0.00405 d (0.0972 hours, 5.787037e-4 weeks, 1.33175e-4 months)  +  and 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 310 +, NRC Inspection Manual 609, Appendix G +, NRC Inspection Manual 609, Appendix I +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.11B +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 92702 +, IP 71111.08B +, IP 711114.07 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000259/2010005 +  and IR 05000259/2010003 +

05000260/LER-2010-003, Regarding Reactor Scram Due to Closure of the Main Steam Isolation Valves and Subsequent Invalid RPS Scram from the Intermediate Range Monitoring System +, 05000296/LER-2009-003, Brown Ferry, Unit 3 Re Reactor Core Isolation Cooling System Inoperable Longer than Allowed by the Technical Specifications +  and 05000260/LER-2010-001, For Browns Ferry, Unit 2 Regarding Condition Prohibited by Technical Specifications When Two Emergency Core Cooling Systems, Loops I and II of the Residual Heat Removal System Low Pressure Coolant Injection System, Become Inope +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

Manual Scram +  and Automatic Scram +

Tennessee +, Washington +  and Alabama +

Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, 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 +, Control Rod +  and Low Pressure Coolant Injection +

TS-3.0.3 +, TS-3.5.1 +, TS-3.5.3 +, TS-3.0.4 +, TS-3.6.2.3 +  and TS-5.4.1.a +

Tennessee Valley Authority +  and Rod Krich +

Safe Shutdown +, Reactor Vessel Water Level +, Mission time +, Fire Barrier +, Weld Overlay +, Internal Flooding +, Past operability +, Nondestructive Examination +, Temporary Modification +, Condition Adverse to Quality +, Tornado Generated Missile +, Significance Determination Process +, Job Performance Measure +, Notice of Violation +, Foreign Material Exclusion +, Integrated leak rate test +, Opportunity to foresee and correct +, Power change +  and Downpower +