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Letter  and Inspection Report

AR 01397127 +  and AR 00 +

ASME Section XI +, ASME Section I +  and ASME Section IX +

National Institute for Occupational Safety and Health +  and Pennsylvania Bureau of Radiation Protection +

10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 71 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 2.790 +, 10 CFR 50.54#q +, 10 CFR 50.65#a4 +, 10 CFR 50.65#a3 +, 10 CFR 50.47#b +  and 10 CFR 20.1703#a +

James Anderson +, J. Stone +, R. Rogers +, R. West +, W. Scott +, T. Lee +, K. Langdon +, J. Mallon +, P. Davison +, E. Anderson +, C. Fritz +, J. Karkoska +, A. Charles +, J. Schwarz +, C. Goff +, B. Norris +, G. Stathes +, C. Arnone +, H. McCrory +, C. Crabtree +, D. Foss +, P. Rau +, M. Ruff +, T. Veale +, C. Behrend +, C. Jordan +, W. Trump +, C. Rogers +, E. Eilola +, G. McCarty +...

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

05000277  +, 05000278  +, 00277  +  and 00278  +

Turbine Trip +  and Reactor Trip +

LS-AA-105 +, OP-MA-109-101 +, ER-AA-310 +, CC-AA-11 +  and NF-AB-702 +

05000278/FIN-2003005-02 +, 05000278/FIN-2003005-03 +, 05000277/FIN-2003004-00 +, 05000277/FIN-2003004-03 +, 05000277/FIN-2003005-01 +, 05000278/FIN-2003005-01 +  and 05000277/FIN-2003005-04 +

Shanbaky M +  and Reactor Projects Region 1 Branch 4 +

IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +, IR 05000277/2003005 +...

IP 71111.12 +, IP 71111.04 +, IP 71111.22 +, IP 71151 +, IP 71153, Event Followup +  and IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609 Appendix H +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.22 +, IP 71111.13 +, IP 71111.08 +, IP 71111.19 +, IP 71111.11B +, IP 71122.02 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71111.11Q +, IP 71114, Reactor Safety Emergency Preparedness +, IP 71121.02 +, IP 71121.01 +, IP 71111.23 +, IP 71111.14 +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.04Q +, IP 71111.12B +, IP 71121.03 +, IP 71111.16 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000277/2003013 +  and IR 05000277/2003005 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +

Emergency Plan +  and RT-F-101-922-2 +

1E-1 +  and 23-2TE20-2 +

Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control rod blade +, Main Condenser +, Control Rod +  and Main Steam +

Exelon +  and Crane C +

Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Hydrostatic +, Nondestructive Examination +, Condition Adverse to Quality +, Significance Determination Process +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Moisture barrier +, License Renewal +, Liquid penetrant +, Scaffolding +, Substantial potential for an overexposure +, Downpower +, Power Uprate +, Overexposure +, Water hammer +  and Unplanned intake +