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Letter  and Inspection Report

10 CFR 55 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 55.21 +, 10 CFR 55.45 +, 10 CFR 55.46 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q +, 10 CFR 50.54#t +, 10 CFR 55.53#e +, 10 CFR 55.59#a2 +, 10 CFR 55.59#c +, 10 CFR 50.65#a3 +, 10 CFR 55.46#c +, 10 CFR 50.47#b +  and 10 CFR 50.47#b10 +

M. Satorius +, J. McCarthy +, R. Davenport +, P. Smith +, P. Louden +, L. Peterson +, H. Chernoff +, G. Sherwood +, B. Cole +, R. Ladd +, S. Forsha +, R. Amundson +, B. Kopetsky +, J. Strharsky +, T. Kendall +, F. Flentje +, C. Sizemore +, J. Schweitzer +, C. Jilek +, T. Gemskie +, G. Corell +, D. Koehl +, G. Packard +, A. Capristo +, G. Casadonte +, D. Schuelke +, M. Lorek +, K. Kappelman +, N. Stuart +, D. Shannon +...

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

05000266  +, 05000301  +, 00266  +  and 00301  +

Technical Support Center +  and Emergency Operations Facility +

05000266/FIN-2003007-05 +, 05000266/FIN-2003007-04 +, 05000266/FIN-2005010-01 +, 05000301/FIN-2005010-01 +, 05000266/FIN-2005010-02 +, 05000301/FIN-2005010-02 +, 05000266/FIN-2005010-03 +, 05000301/FIN-2005010-03 +, 05000301/FIN-2003007-04 +  and 05000301/FIN-2003007-05 +

Satorius M +  and Division Reactor Projects III +

IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +, IR 05000266/2005010 +...

3.587963e-4 d (0.00861 hours, 5.125661e-5 weeks, 1.17955e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71114.03 +, IP 71114.02 +, IP 71111.19 +, IP 71151 +, IP 71114.05 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.14 +, IP 71111.17A +, IP 71111.12B +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0350 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +  and IMC 0305, Operating Reactor Assessment Program +

IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +  and IP 71121.03 +

IR 05000266/2003007 +, IR 05000266/2005010 +, IR 05000266/2004007 +, IR 05000266/2005009 +, IR 05000030/2005009 +  and IR 05000030/2019004 +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

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 +

AOP +  and Emergency Plan +

1P-15A +, 1A-05 +, 1A-06 +, 2AF-4000 +, 2AF-4001 +, 1B52-329H +, 1RE-127 +  and 2RE-109 +

DPR-24 +  and DPR-27 +

Washington +  and Wisconsin +

Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +  and Control Rod +

TS-3.8.1 +, TS-3.3.4 +, TS-3.8.1.E +  and TS-5.4.1 +

Nuclear Management Co +  and Koehl D +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Fire Barrier +, Stroke time +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Locked High Radiation Area +, Condition Adverse to Quality +, Significance Determination Process +, Job Performance Measure +, Shift Technical Advisor +, Loss of Offsite Power +, Through-Wall Leak +, Through-Wall Leakage +, Downpower +  and Siren +