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Letter  and Inspection Report

AR 00952261 +  and AR 01184096 +

Iron +, Copper +, Nitrogen +  and Lead +

10 CFR 50 Appendix B +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +  and 10 CFR 2.790 +

D. Warfel +, M. Gallagher +, G. Krueger +, J. McLaughlin +, J. Hallenbeck +, A. Javorik +, E. Kriner +, M. Hochreiter +, S. Beck +, D. Weaver +, W. Coyle +, W. Dalton +, J. Gyrath +, A. Hegedus +, D. Keene +  and J. Liddy +

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

05000277  +, 05000278  +, 00277  +  and 00278  +

Technical Support Center +  and Emergency Operations Facility +

05000277/FIN-2003013-01 +, 05000278/FIN-2003013-02 +, 05000278/FIN-2003013-03 +, 05000278/FIN-2003013-04 +  and 05000277/FIN-2003013-05 +

Division of Reactor Safety I +  and Crlenjak R +

IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +, IR 05000277/2003013 +...

1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0612 Appendix B +  and NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG/CR-5496, Issues Final Rept,Evaluation of Loss of Offsite Power Events at Nuclear Power Plants 1980-1996,NUREG/CR-5496.Observations & Findings of Study Listed.Without Encl +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

ST-J-080-940-3 +  and Emergency Operating Procedure +

Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +  and Main Steam +

TS-5.4.1 +  and TS-5.5.5 +

Exelon +  and Skolds J +

Reactor Vessel Water Level +, Packing leak +, Mission time +, Stroke time +, Condition Adverse to Quality +, Significance Determination Process +, Notice of Violation +, Large early release frequency +, Loss of Offsite Power +, Preliminary White Finding +  and Regulatory Conference +