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Letter  and Inspection Report

Boron +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.54#q +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 50.65#a4 +  and 10 CFR 20.1501#a +

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

H.4 +, H.5 +, H.13 +, H.14 +, P.2 +  and P.3 +

05000482  +  and 00482  +

FP-293 +  and FP-211 +

Turbine Trip +  and Reactor Trip +

05000482/FIN-2009005-15 +, 05000482/FIN-2011002-01 +, 05000482/FIN-2011002-02 +, 05000482/FIN-2011002-03 +, 05000482/FIN-2011002-04 +, 05000482/FIN-2011002-05 +, 05000482/FIN-2011002-07 +, 05000482/FIN-2011002-08 +, 05000482/FIN-2011002-09 +, 05000482/FIN-2011002-10 +, 05000482/FIN-2011002-11 +, 05000482/FIN-2010002-05 +, 05000482/FIN-2009005-05 +, 05000485/FIN-2011002-01 +  and 05000485/FIN-2011002-06 +

Geoffrey Miller +  and NRC/RGN-IV/DRP/RPB-B +

ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +, ML111290768 +  and ML111290768 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-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)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +  and 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609 Appendix M +, NRC Inspection Manual 0608 +, NRC Inspection Manual 8571 +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.12 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71114.06 +, IP 71124.03 +, IP 71111.19 +, IP 71124.02 +, 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 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.07, Heat Sink Performance +, IP 71111.20, Refueling and Other Outage Activities +, IP 71152, Problem Identification and Resolution (PI&R) +, IP 71111.04-05 +, IP 71111.05-05 +, IP 71111.12-05 +, IP 71111.19-05 +, IP 71111.22-05 +, IP 71151-05 +, IP 71152-05 +, IP 71111.15-04 +, IP 71111.07-05 +, IP 71111.06-05 +  and IP 71111.20-05 +

IR 05000482/2010008 +, IR 05000482/2009004 +, IR 05000482/2009005 +, IR 05000482/2011002 +  and IR 05000482/2010002 +

Westinghouse +  and Limitorque +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-0881, Safety Evaluation Accepting Licensee Submittals & Addl Info on Environ Qualification & Design for Instrumentation,Per Reg Guide 1.97 +

Regulatory Guide 1.137 +, Regulatory Guide 1.33 +  and Regulatory Guide 1.160 +

SR-4.8.1.1 +  and SR-3.3.2 +

1E-7 +, 26C-004 +, 21G-001 +, 21E-001 +, 07-02-004 +, 22C-003 +, 23M-050 +, 29B-003 +, 25B-100 +, 25A-401 +, 25A-410 +, 25B-300 +, 21B-003 +, 19B-001 +, 19D-100 +, 25A-001 +, 25A-200 +, 25A-700 +, 25B-600 +, 25A-800 +, 26A-2007 +, 26C-005 +  and I3R-03 +

Texas +, Kansas +  and Washington +

Steam Generator +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Residual Heat Removal +, Emergency Core Cooling System +  and Decay Heat Removal +

TS-3.0.3 +, TS-3.8.1 +, TS-3.0.4 +, TS-3.4.12 +, TS-3.3.2 +, TS-3.0 +, TS-3.0.4.b +  and TS-5.4.1.a +

Wolf Creek +  and Matthew Sunseri +

Safe Shutdown +, High Radiation Area +, Ultimate heat sink +, Water Inventory Control +, Probabilistic Risk Assessment +, Coatings +, Fire impairment +, Temporary Modification +, Functionality Assessment +, Locked High Radiation Area +, Condition Adverse to Quality +, Missed surveillance +, Significance Determination Process +, Shift Technical Advisor +, Large early release frequency +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Biofouling +, Scaffolding +, Grace period +, Substantial potential for overexposure +, Substantial potential for an overexposure +, Power change +  and Overexposure +