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Letter  and Inspection Report

10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion V +  and 10 CFR 2.390#d1 +

Christine Lipa +, R. Anderson +, D. Passehl +, G. Pry +, R. Nelson +, Marlone Davis +, D. Curtland +, B. Murrell +, P. Hansen +, G. Hawkins +, R. Wheaton +, K. Kleinheinz +, K. Peveler +, S. Catron +  and A. Julka +

Emergency Preparedness +, Initiating Events +  and Mitigating Systems +

05000331  +  and 00331  +

05000331/FIN-2013010-01 +  and 05000331/FIN-2013002-01 +

O'Brien K +  and Division Reactor Projects III +

IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +, IR 05000331/2013010 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

IP 71111.12 +  and IP 71111.12Q +

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

IR 05000331/2009009 +  and IR 05000331/2013010 +

NUREG/CR-6890 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG/CR-5496, Issues Final Rept,Evaluation of Loss of Offsite Power Events at Nuclear Power Plants 1980-1996,NUREG/CR-5496.Observations & Findings of Study Listed.Without Encl +, NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +  and NUREG-1953, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom +

High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Residual Heat Removal +  and Residual Heat Removal Service Water +

NextEra Energy +  and Richard Anderson +

Safe Shutdown +, Mission time +, Past operability +, Probabilistic Risk Assessment +, Significance Determination Process +, Notice of Violation +, Large early release frequency +, Loss of Offsite Power +, Earthquake +, Preliminary White Finding +  and Regulatory Conference +