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Letter  and Inspection Report

10 CFR 50 +, 10 CFR 2.390 +  and 10 CFR 50 Appendix B Criterion XVI +

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

05000482  +  and 00482  +

05000482/FIN-2016008-02 +, 05000482/FIN-2016008-01 +, 05000482/FIN-2015002-01 +, 05000482/FIN-2014005-02 +  and 05000482/FIN-2016001-00 +

Troy Pruett +  and NRC/RGN-IV/DRP +

ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +, ML16235A132 +  and ML16235A132 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 8.796296e-4 d (0.0211 hours, 1.256614e-4 weeks, 2.8918e-5 months)  +, 0.00113 d (0.0272 hours, 1.62037e-4 weeks, 3.7289e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0410 +, NRC Inspection Manual 0308 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0609/Appendix F +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IR 05000482/2016008 +  and IR 05000482/2015002 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +

16E-002 +, 16B-003 +, 28A-100 +  and 20E-001 +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Auxiliary Feedwater +  and Remote shutdown +

TS-5.4.1.a +  and TS-3.8.1 +

Wolf Creek +  and Heflin A +

Safe Shutdown +, High winds +, Mission time +, Enforcement Discretion +, Probabilistic Risk Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Notice of Violation +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Preliminary White Finding +, Thermography +  and Regulatory Conference +