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Letter  and Inspection Report

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#a2iB +, 10 CFR 50.54#q2 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b4 +  and 10 CFR 50.9#a +

CR-IP3-2015-00898 +, CR-IP3-2015-02128 +, CR-IP2-2014-02564 +, CR-IP2-2014-04905 +, CR-IP3-2015-00084 +, CR-IP3-2015-02437 +, CR-IP2-2015-01859 +, CR-IP2-2015-02139 +, CR-IP2-2015-02620 +, CR-IP3-2015-03427 +, CR-IP3-2013-00869 +, CR-IP2-2013-00398 +, CR-IP2-2014-00321 +, CR-IP2-2013-00039 +, CR-IP3-2015-00113 +, CR-IP3-2015-03761 +  and CR-IP2-2013-00113 +

Arthur Burritt +, J. Kirkpatrick +, L. Coyle +, T. Chan +, R. Burroni +, J. Ferrick +, B. McCarthy +, N. Azevedo +, S. Bianco +, T. Cramer +, L. Glander +, F. Kich +, N. Lizzo +, S. Stevens +, M. Tesoriero +, M. Troy +, R. Walpole +, K. Baumbach +, D. Dewey +, R. Drake +, D. Gagnon +, F. Mitchell +, E. Mullek +, J. Dinelli +, D. Mayer +, R. Dolanksy +  and R. Tambori +

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

05000247  +, 05000286  +, 00247  +  and 00286  +

ENS 51060 +  and ENS 51156 +

EC-57837 +  and EC-38536 +

EN-OP-115 +  and EN-TQ-125 +

Turbine Trip +  and Reactor Trip +

05000286/FIN-2015002-01 +, 05000286/FIN-2015002-02 +  and 05000286/FIN-2015002-03 +

Arthur Burritt +  and Reactor Projects Region 1 Branch 2 +

IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +, IR 05000247/2015002 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.0203 d (0.486 hours, 0.00289 weeks, 6.65875e-4 months)  +, 0.0232 d (0.557 hours, 0.00332 weeks, 7.629025e-4 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, IP 71124.02 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11Q +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.04Q +, IP 71111.07A +, 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 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 +

05000286/LER-2015-001, Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Level Alarms Due to Freezing of the Level Instrument Sensing Lines Caused by a Failed Strip Heater +  and 05000286/LER-2015-002, Regarding Technical Specification Prohibited Condition Caused by Three Main Steam Safety Valves Outside Their As-Found Lift Set Point Test Acceptance Criteria +

LIC-921 +  and LIC-910 +

PFP +, PFP-388 +, PFP-207 +, PFP-160A +, PFP-351 +, PFP-353 +  and PFP-356 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +

Entergy +  and Larry Coyle +

Time of Discovery +, High Radiation Area +, Fire Barrier +, Water Inventory Control +, Internal Flooding +, Enforcement Discretion +, Temporary Modification +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Shift Technical Advisor +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Maintenance Rule Program +, Scaffolding +, Power change +, Loss of condenser vacuum +  and Reactive Inspection +