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Letter  and Inspection Report

Nitrogen +, Oxygen +, Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 50.65 +, 10 CFR 71.5 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.72#b3vD +, 10 CFR 50.54#q2 +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b16 +  and 10 CFR 20.1902#b +

P. Summers +, E. Bates +, S. Bono +, K. Bronson +, M. McAndrew +, J. Paul +, B. Tidwell +, L. Hughes +, M. Oliver +, L. Slizewski +, M. Kirschenheiter +, R. Guthrie +, M. Lawson +, H. Smith +, M. Acker +, P. Campbell +, L. Holland +, Q. Leonard +, D. Campbell +, J. Polickoski +, C. Whitworth +, R. Loggins +, J. Lacasse +, Diane Jackson +  and James Smith +

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

05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +

05000260/FIN-2016001-01 +, 05000296/FIN-2016001-06 +, 05000260/FIN-2015004-05 +, 05000260/FIN-2015004-06 +  and 05000296/FIN-2016001-02 +

Alan Blamey +  and Reactor Projects Region 2 Branch 6 +

IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +, IR 05000296/2016001 +...

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.08 +, 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 71111.07, Heat Sink Performance +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609 Appendix H +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0609/Appendix A +

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71124.08 +, IP 71111.13 +, IP 71111.08 +, IP 71124.05 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.07, Heat Sink Performance +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000259/2016001 +  and IR 05000296/2016001 +

05000296/LER-2014-003, Regarding Primary Containment Isolation Valve Inoperable for Longer than Allowed by Technical Specifications +, 05000259/LER-2015-005, Regarding Inboard Main Steam Isolation Valve Actuators Inoperable for Longer than Allowed by Technical Specifications +, 05000296/LER-2015-005, Regarding Automatic Actuation of 30 Diesel Generator Due to 4kV Shutdown Board Trip During Testing +  and 05000296/LER-2015-002, Regarding Switch Failure Rendered Automatic Startup of Some Emergency Core Cooling System Pumps Inoperable Longer than Allowed by Technical Specifications +

NUREG-1608 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and 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 +

1e-7 +  and 1e-6 +

Tennessee +  and Washington +

Reactor Coolant System +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Main Steam +

TS-3.5.1 +, TS-3.3.5.1 +, TS-3.3.6.1 +, TS-3.7.1 +, TS-3.6.1.3 +, TS-3.6.3.1 +, TS-3.0.6 +, TS-5.5.6 +, TS-5.4.1 +, TS-5.4.1.a +, TS-5.7.1 +  and TS-3.3.1.6 +

Tennessee Valley Authority +  and James Shea +

Safe Shutdown +, Time of Discovery +, Packing leak +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Stroke time +, Enforcement Discretion +, Functionality Assessment +, Locked High Radiation Area +, Condition Adverse to Quality +, Significance Determination Process +, Job Performance Measure +, Local Leak Rate Testing +, Foreign Material Exclusion +, Process Control Program +, Operability Determination +, Liquid penetrant +, Fire Watch +, Substantial potential for overexposure +, Downpower +  and Overexposure +

WO 115569837 +, WO 116930078 +, WO 117608777 +, WO 117638683 +, WO 116617043 +, WO 117494970 +, WO 116617149 +, WO 116617273 +, WO 115949599 +  and WO 117530716 +