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Letter  and Inspection Report

Cobalt +  and Lead +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 20 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 20.1204 +, 10 CFR 20.1501 +, 10 CFR 20.1601 +, 10 CFR 20.1602 +, 10 CFR 50.9 +, 10 CFR 50.65 +, 10 CFR 50.74 +, 10 CFR 55.45 +, 10 CFR 55.46 +, 10 CFR 55.49 +, 10 CFR 55.53 +, 10 CFR 61.55 +, 10 CFR 71.137 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 20.1201#c +, 10 CFR 55.53#i +, 10 CFR 55.59#a2 +, 10 CFR 55.59#c +, 10 CFR 55.59#c4 +, 10 CFR 55.46#c +, 10 CFR 20.1101#c +  and 10 CFR 50.75#g +

James Anderson +, Marlone Davis +, M. Walter +, P. Huffman +, J. Sorensen +, M. Carlson +, M. Wadley +, T. Ouret +, T. Allen +, M. Agen +, M. Kent +, P. Wiltse +  and F. Forrest +

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

H.8 +  and P.3 +

05000282  +, 05000306  +, 00282  +  and 00306  +

Technical Support Center +  and Emergency Operations Facility +

05000282/FIN-2007005-01 +, 05000306/FIN-2007005-01 +, 05000306/FIN-2007005-02 +, 05000282/FIN-2007006-01 +, 05000282/FIN-2007003-04 +, 05000282/FIN-2007005-03 +, 05000306/FIN-2007005-03 +, 05000282/FIN-2007005-04 +, 05000306/FIN-2007005-04 +, 05000306/FIN-2007003-04 +, 05000282/FIN-2007003-05 +, 05000306/FIN-2007003-05 +, 05000282/FIN-2007003-01 +  and 05000306/FIN-2007006-01 +

Richard Skokowski +  and Region 3 Branch 3 +

IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +, IR 05000282/2007005 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.17 +, IP 71111.05 +, IP 71111.13 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, 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 71111.23 +, 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 +  and NRC Inspection Manual 0609/Appendix C, Occupational Radiation Safety Significance Determination Process +

IP 71122.02 +, IP 71122.01 +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71121.02 +, IP 71121.01 +, IP 71122.03 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000282/2007005 +, IR 05000282/2007004 +, IR 05000282/2007006 +, IR 05000282/2007003 +  and IR 05000282/2006002 +

Tritium +  and Cesium 137 +

05000282/LER-2007-003, Regarding Unanalyzed Condition Due to Breached Fire Barrier +  and 05000282/LER-2007-001, Re Unit 1 Train B ECCS Inoperable Longer than Allowed by Technical Specifications Due to Inoperable Breaker +

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 +

Regulatory Guide 1.33 +  and Regulatory Guide 8.38 +

Wolf Creek +  and Prairie Island +

Minnesota +  and Washington +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Safety Relief Valve +, Main Steam +  and Containment Spray +

TS-3.5.2 +, TS-3.8.1.b +  and TS-5.4.1 +

Nuclear Management Co +  and Wadley M +

Unanalyzed Condition +, High Radiation Area +, Fire Barrier +, Past operability +, Probabilistic Risk Assessment +, Temporary Modification +, Zebra Mussel +, Locked High Radiation Area +, Significance Determination Process +, Job Performance Measure +, Process Control Program +, Loss of Offsite Power +, Operability Determination +, Through-Wall Leak +  and Overexposure +