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Letter  and Inspection Report

Boron +, Iodine +, Carbon +  and Hydrogen +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b2 +, 10 CFR 50.47#b5 +, 10 CFR 50.55a#g6iiD +  and 10 CFR 50.75#g +

C. Fletcher +, D. Barker +, T. Simril +, L. Keller +, T. Arlow +, E. Benfield +, T. Jenkins +, A. Keller +, K. Henderson +, C. Cauthen +, K. Phillips +, P. Simbrat +, D. Cantrell +, C. Kamilaris +, W. Suslick +, B. Callaway +, D. Tollison +, James Smith +, Stephanie West +  and Bryan Leonard +

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

05000413  +, 05000414  +, 00413  +  and 00414  +

Frank Ehrhardt +  and Division Reactor Projects II +

IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +, IR 05000413/2015001 +...

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

IP 71114, Reactor Safety Emergency Preparedness +  and IP 71152, Problem Identification and Resolution (PI&R) +

NUREG-1608 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0133, Informs That Rev 3 to Offsite Dose Calculation Manual (ODCM) Uses Documented & Approved Methods Consistent W/Methodology & Guidelines in NUREG-0133 & Acceptable.Revised ODCM Containing Simplified Block Diagrams Requested +  and NUREG-0654, Changes to the Emergency Action Level Scheme +

Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.15 +  and Regulatory Guide 1.23 +

1CF-42 +, 1AD-2 +, 2NC74-16 +, 2ND40-5 +, 2ND40-6 +  and 2ND41-16 +

NPF-52 +  and NPF-35 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Residual Heat Removal +, Decay Heat Removal +  and Containment Spray +

TS-5.7 +, TS-5.0 +  and TS-5.4.1 +

Duke Energy +  and Henderson K +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Probabilistic Risk Assessment +, Functionality Assessment +, Locked High Radiation Area +, FLEX +, Annual Radiological Environmental Operating Report +, Process Control Program +, Stress corrosion cracking +, Operability Determination +, Siren +, Measurement Uncertainty Recapture +  and Operational leakage +