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Letter  and Inspection Report

Iodine +, Carbon +  and Lead +

10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.65#a4 +, 10 CFR 50.59#d1 +  and 10 CFR 20.1301#d +

James Anderson +, T. Palmisano +, S. Brown +, G. Park +, S. Thomas +, P. Huffman +, S. Northard +, J. Kivi +, S. Redner +, J. Wren +, J. LeClair +, F. Forrest +, W. Collins +, R. Cooper +, S. Hansen +, C. Koehler +, F. Ortiz +  and C. Sprout +

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

05000282  +, 05000306  +, 00282  +  and 00306  +

ML032681205 +  and IR 05000282/2005004 +

05000282/FIN-2006003-01 +, 05000306/FIN-2006003-01 +, 05000282/FIN-2006003-02 +, 05000306/FIN-2006003-02 +, 05000282/FIN-2006003-03 +, 05000306/FIN-2006003-03 +, 05000282/FIN-2006002-01 +, 05000306/FIN-2006002-01 +, 05000282/FIN-2006003-05 +, 05000306/FIN-2006003-05 +, 05000282/FIN-2006003-04 +, 05000306/FIN-2006003-04 +  and 05000306/FIN-2005004-07 +

Richard Skokowski +  and NRC/RGN-III/DRP/RPB3 +

NRC Generic Letter 04-02 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +

IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +, IR 05000282/2006003 +...

2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.08 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, IP 71111.02 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.07, Heat Sink Performance +, IP 71111.23 +, IP 71111.14 +, IP 71007 +, 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 D +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix C, Occupational Radiation Safety Significance Determination Process +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.08 +, IP 71122.01 +, IP 71121.02 +, IP 71121.01 +, IP 71007 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000282/2006003 +  and IR 05000282/2005004 +

NUREG-012 +, NUREG-1774 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +

Regulatory Guide 1.33 +  and Regulatory Guide 1.187 +

2FI-411 +, 1SI-12X +  and 1SI-22X +

Wolf Creek +  and Prairie Island +

Minnesota +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

TS-5.4.1.a +, TS-5.7.1 +, TS-5.5.1 +, TS-5.7.1.a +  and TS-5.5.4 +

Nuclear Management Co +  and Thomas J. Palmisano +

Safe Shutdown +, Boric Acid +, High winds +, Packing leak +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Internal Flooding +, Nondestructive Examination +, Temporary Modification +, Zebra Mussel +, Locked High Radiation Area +, Significance Determination Process +, Foreign Material Exclusion +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Code Reconciliation +, Control of Heavy Loads +, Liquid penetrant +, Pressure Boundary Leakage +, Power change +, Siren +  and Overexposure +