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Letter  and Inspection Report

ASME Section XI +  and ASME Section VIII +

Cobalt +, Carbon +, Chloride +  and Lead +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.65 +, 10 CFR 71.5 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50.73#a2iB +, 10 CFR 20.1406#c +  and 10 CFR 50.65#a4 +

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

WO 306297 +, WO 378015 +, WO 377771 +  and NRC 95002 +

05000293  +  and 00293  +

EN-OP-115 +, EN-LI-102 +  and EN-OP-104 +

05000293/FIN-2015002-01 +, 05000293/FIN-2015002-02 +, 05000293/FIN-2015002-03 +, 05000293/FIN-2015002-04 +  and 05000293/FIN-2015002-05 +

Raymond Mckinley +  and Projects Branch 5 +

IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +, IR 05000293/2015002 +...

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, 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 71111.04S +, IP 71111.12Q +, IP 71111.08G +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0609, Appendix D +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609 Appendix G +, 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 71124.08 +, IP 71111.05Q +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000293/2015007 +, IR 05000293/2014008 +  and IR 05000293/2015002 +

05000293/LER-2015-001, Regarding Loss of 345KV Power Resulting in Automatic Reactor Scram During Winter Storm Juno +  and 05000293/LER-2015-002, Regarding Main Steam Safety Relief Valves Determined to Be Inoperable Following Evaluation +

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-0041, Request Addl Info Re Requested Clarifications/Exceptions to NUREG-0041,respiratory Protection Program.Nrc Comments Encl +

4.16kV +  and 345kV +

Regulatory Guide 8.38 +, Regulatory Guide 8.15 +, Regulatory Guide 8.25 +, Regulatory Guide 8.8 +  and Regulatory Guide 8.10 +

SR-4.5.F.1 +  and SR-4.9.A.1 +

10R-IA-3 +, 2R-N1B-1 +  and 2R-A +

Manual Scram +  and Automatic Scram +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Reactor Building Closed Loop Cooling +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

TS-3.5.E +  and TS-3.5.F +

Entergy +  and Dent J +

Time of Discovery +, High Radiation Area +, Non-Destructive Examination +, Mission time +, Fire Barrier +, Water Inventory Control +, Internal Flooding +, Enforcement Discretion +, Temporary Modification +, Functionality Assessment +, Locked High Radiation Area +, Significance Determination Process +, Local Leak Rate Testing +, Flow Accelerated Corrosion +, Feedwater Heater +, Scram Discharge Volume +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Operability Determination +, License Renewal +, Liquid penetrant +, Through-Wall Leak +, Offsite Circuit +, Dissimilar Metal Weld +, Scaffolding +, Power change +, Overspeed +  and Reactive Inspection +

WO 306297 +, WO 378015 +  and WO 377771 +