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Letter  and Inspection Report

10 CFR 55 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 55.4 +, 10 CFR 55.45 +, 10 CFR 55.46 +, 10 CFR 55.49 +, 10 CFR 55.53 +, 10 CFR 55.59 +, 10 CFR 50.73#a2iB +, 10 CFR 50.73#a2iiB +, 10 CFR 50.73#a2ivA +, 10 CFR 50.73#a2vA +, 10 CFR 50.72#b2ivB +, 10 CFR 50.72#b3ivA +, 10 CFR 50.54#q +, 10 CFR 55.53#e +, 10 CFR 55.53#I +, 10 CFR 55.59#c +, 10 CFR 55.59#a +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +  and 10 CFR 50.65#a3 +

Jamnes Cameron +, B. Matty +, B. Howard +, T. Brown +, G. Michael +, T. Gaydosik +, W. OMalley +, K. Zellers +, G. Wolf +, B. Boles +, D. Noble +, J. Sturdavant +, J. Vetter +, D. Imlay +, M. Brasile +, R. Oesterle +, A. Dawson +, G. Laird +, P. McCloskey +, K. Byrd +, J. Cuff +, J. Cunnings +, D. Hartnett +, T. Henline +, R. Patrick +, L. Thomas +, L. Willis +, B. Needham +  and Carol Gallagher +

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

05000346  +  and 00346  +

IR 05000346/2016003 +, IR 05000346/2016001 +, IR 05000346/2016409 +, IR 05000346/2016002 +, IR 05000346/2015001 +, IR 05000346/2015003 +, IR 05000346/2015004 +, IR 05000346/2014008 +, IR 05000346/2015002 +, ML1607A600 +  and ML13172A144 +

ENS 52232 +, ENS 52247 +  and ENS 52010 +

05000346/FIN-2016004-01 +, 05000346/FIN-2016004-02 +, 05000346/FIN-2016002-01 +, 05000346/FIN-2016009-00 +, 05000346/FIN-2016006-00 +  and 05000346/FIN-2016007-00 +

Jamnes Cameron +  and Reactor Projects Region 3 Branch 4 +

IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +, IR 05000346/2016004 +...

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, IP 71124.02 +, IP 71111.11B +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.11Q +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.05Q +, IP 71111.11A +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, 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, Power Reactor Inspection Reports +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.22 +, IP 71111.11B +, IP 71153, Event Followup +, IP 71111.11Q +, IP 71152, Problem Identification and Resolution (PI&R) +, IP 71111.04-05 +, IP 71111.05-05 +, IP 71111.12-05 +, IP 71111.13-05 +, IP 71111.15-05 +, IP 71111.19-05 +, IP 71151-05 +, IP 71152-05 +, IP 71111.01-05 +, IP 71111.11-05 +, IP 71124.01-05 +, IP 71124.02-05 +, IP 71153-05 +  and IP 71114.06-06 +

IR 05000346/2016003 +, IR 05000346/2016001 +, IR 05000346/2016409 +, IR 05000346/2016004 +, IR 05000346/2016002 +, IR 05000346/2015001 +, IR 05000346/2015003 +, IR 05000346/2015004 +, IR 05000346/2014008 +, IR 05000346/2015002 +  and IR 05000346/2013405 +

AR 02016004 +  and AR 02016501 +

05000346/LER-2016-009, Regarding Reactor Trip Due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level +  and 05000346/LER-2016-006, Potential to Trip Emergency Diesel Generator on High Crankcase Pressure +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Shield Building +, Stator Water Cooling +, Emergency Core Cooling System +  and Main Steam Line +

TS-3.4.1 +, TS-3.4.10 +  and TS-3.8.9 +

FirstEnergy +  and Boles B +

Unanalyzed Condition +, High Radiation Area +, Offsite Dose Calculation Manual +, Past operability +, Enforcement Discretion +, Temporary Modification +, Cyber Security +, Functionality Assessment +, Significance Determination Process +, Job Performance Measure +, Shift Technical Advisor +, Operability Determination +, Maintenance Rule Program +, Fire Protection Program +  and Downpower +