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Letter  and Inspection Report

Hydrogen +, Lead +  and Helium +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 55.59 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#a2iC +, 10 CFR 50.54#q +, 10 CFR 50.54#q3 +, 10 CFR 50.54#q5 +  and 10 CFR 50.65#a4 +

Arthur Burritt +, J. Taylor +, J. Dent +, E. Perkins +, E. Sanchez +, R. Morris +, K. Woods +, J. Cox +, M. Jacobs +, J. Gerety +, C. Baker +, D. King +, J. MacDonald +, A. Zelie +, L. Johnson +, G. Flynn +, D. Noyes +, R. Byrne +, J. Falconieri +, K. Kampschneider +, C. McMorrow +, G. Sterling +, D. Calabrese +, S. Asplin +, G. Blankenbiller +, M. Dagnello +, R. Metthe +, J. ODonnell +, J. Ohrenberger +, N. Reece +...

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

05000293  +, 07201044  +  and 00293  +

IR 05000293/2015004 +, ML14198A157 +, ML16286A592 +  and IR 05000293/2015005 +

EN-WM-104 +, EN-OP-115 +, EN-DC-153 +, EN-LI-102 +, EN-OP-104 +, EN-LI-118 +, EN-WM-102 +  and EN-OP-119 +

Turbine Trip +  and Reactor Trip +

05000293/FIN-2016004-01 +, 05000293/FIN-2016004-02 +, 05000293/FIN-2016004-03 +, 05000293/FIN-2016004-04 +  and 05000293/FIN-2016004-05 +

Arthur Burritt +  and Projects Branch 5 +

IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +, IR 05000293/2016004 +...

1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71124.05 +, IP 71111.19 +, IP 71151 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.12Q +, IP 07622 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix K +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.04 +, IP 95003 +, IP 71111.11Q +, IP 71111.05Q +, IP 71111.11A +  and IP 71152, Problem Identification and Resolution (PI&R) +

AR 02016004 +  and AR 02016001 +

05000293/LER-2016-005, Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable +  and 05000293/LER-2016-002, Regarding Online Maintenance Test Configuration Prohibited by Technical Specifications +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1765, NSP000017-Revised Testimony of Steven Skoyen-NUREG-1765 Excerpts +  and NUREG/CR-7110, Official Exhibit - ENT000457-00-BD01 - NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) +

4kV +  and 345kV +

1E-6 +, 1E-11 +, 1E-5 +, 1E-7 +  and 4E-7 +

Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Core Spray +, Residual Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Main Steam +

TS-3.7.A +  and TS-3.9.B +

Entergy +  and Dent J +

Packing leak +, High Radiation Area +, Ultimate heat sink +, Fire Barrier +, Stroke time +, Internal Flooding +, Past operability +, Enforcement Discretion +, Probabilistic Risk Assessment +, Temporary Modification +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Commercial Grade +, Maintenance Rule Program +, Fuel cladding +, Fire Watch +, Incremental Core Damage Probability Deficit +  and Downpower +