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Letter  and Inspection Report

Hydrogen +, Lead +  and Silicon +

10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.49#l +, 10 CFR 50.65#a4 +  and 10 CFR 50.75#g +

Arthur Burritt +, T. White +, K. OBrien +, B. Sullivan +, J. Gerety +, A. Zelie +, B. Chenard +, G. Flynn +, P. Harizi +, D. Labun +, P. Miner +, D. Noyes +, P. Beabout +, M. Romeo +, D. Calabrese +, B. Rancourt +, G. Blankenbiller +, P. Leavitt +, N. Reece +, F. McGinnis +, J. Keene +, N. Eisenmann +, R. Pitts +, Mike Williams +, R. Ho +, J. Kritzer +, C. Perkins +, M. Powers +  and K. Whippie +

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

05000293  +  and 00293  +

EN-OP-115 +, EN-DC-153 +, EN-DC-324 +, EN-LI-102 +, EN-DC-335 +  and EN-CY-111 +

05000293/FIN-2017001-01 +, 05000293/FIN-2017001-1 +, 05000293/FIN-2017003-01 +, 05000293/FIN-2017003-02 +, 05000293/FIN-2017003-04 +, 05000293/FIN-2017003-05 +, 05000293/FIN-2017003-07 +, 05000293/FIN-2017003-03 +  and 05000293/FIN-2017003-06 +

Arthur Burritt +  and Projects Branch 5 +

IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +, IR 05000293/2017003 +...

4.861111e-4 d (0.0117 hours, 6.944444e-5 weeks, 1.5981e-5 months)  +, 0.00106 d (0.0256 hours, 1.521164e-4 weeks, 3.5006e-5 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 6.365741e-4 d (0.0153 hours, 9.093915e-5 weeks, 2.09275e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

IP 71111.04 +, IP 71111.22 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11Q +, IP 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +, IP 71111.04S +, IP 71111.12Q +, IP 05000 +, IP 71124.07, Radiological Environmental Monitoring Program +  and IP 71152, Problem Identification and Resolution (PI&R) +

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

IP 71152, Problem Identification and Resolution (PI&R) +  and IP 71111.05Q +

IR 05000293/2017001 +, IR 05000293/2017002 +, IR 05000293/2017405 +  and IR 05000293/2017003 +

05000293/LER-1916-010-01, Re MSIV Inoperability +  and 05000293/LER-1917-003-01, Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +  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) +

AOP +  and Emergency Plan +

Regulatory Guide 1.33 +  and Regulatory Guide 1.89 +

1E-7 +  and 6E-7 +

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

TS-3.7.A +, TS-3.5.A +, TS-4.7.A +, TS-5.4.1 +, TS-5.4.1.a +  and TS-3.5.H +

Entergy +  and Brian Sullivan +

Packing leak +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Enforcement Discretion +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Local Leak Rate Testing +, Annual Radiological Environmental Operating Report +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Downpower +, Flow Induced Vibration +, Operability Assessment +, Overspeed trip +, Overspeed +, Water hammer +  and Reactive Inspection +