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Letter  and Inspection Report

ASME Section IV +  and ASME Section XI +

Iodine +, Carbon +  and Lead +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.54#q2 +, 10 CFR 50.34#a +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b4 +, 10 CFR 50.55a#f1 +  and 10 CFR 50.75#g +

J. Gaines +, Daniel Schroeder +, D. Moore +, J. Wynn +, M. Flaherty +, H. Daman +, J. Gines +, B. Wright +, G. Gellrich +, C. Blue +, B. Erdman +, J. York +, D. Lauver +, B. Pickett +, W. Lang +, A. Ball +, T. Baummer +, C. Birke +, F. Copsey +, H. Enoch +, T. Hunkle +, P. Jones +, M. Leno +, M. McMahon +, R. Nelson +, Jessie Delgado +  and Beth Brown +

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

05000317  +, 05000318  +, 00317  +  and 00318  +

Reactor Trip +  and Circulating water pump trip +

05000318/FIN-2014003-02 +  and 05000318/FIN-2014003-01 +

Ho Nieh +  and Division Reactor Projects I +

IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +, IR 05000317/2014003 +...

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0.00347 d (0.0833 hours, 4.960317e-4 weeks, 1.1415e-4 months)  +  and 0.00469 d (0.113 hours, 6.696429e-4 weeks, 1.541025e-4 months)  +

IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71124.05 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11Q +, IP 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.04Q +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix B +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.07, Heat Sink Performance +, IP 71111.07T +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000317/2014003 +, IR 05000317/2014002 +  and IR 05000317/2013003 +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AOP +, EOP-4 +, EOP-0 +, Emergency Operating Procedure +  and AOP-7K +

Regulatory Guide 1.1 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.1 +  and Regulatory Guide 4.15 +

Steam Generator +, Reactor Coolant System +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Control Room Emergency Ventilation +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Main Steam +  and Containment Spray +

Exelon +  and George Gellrich +

Safe Shutdown +, Boric Acid +, High winds +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Internal Flooding +, Nondestructive Examination +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Notice of Violation +, Flow Accelerated Corrosion +, Shift Technical Advisor +, Eddy Current Testing +, Main Steam Line Radiation Monitor +, Operability Determination +, Reasonable doubt of operability +, Maintenance Rule Program +, Preliminary White Finding +, Operability Assessment +, Water hammer +, Regulatory Conference +  and Reactive Inspection +