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Letter  and Inspection Report

Boron +, Iodine +  and Lead +

10 CFR 50.72 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50.68 +, 10 CFR 50.75 +, 10 CFR 50 Appendix I +, 10 CFR 50.55a +, 10 CFR 50.54#q +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.75#g +  and 10 CFR 50.35#a +

CR-IP2-2013-00721 +, CR-IP2-2012-07140 +, CR-IP3-2013-00507 +, CR-IP3-2011-03960 +, CR-IP3-2012-03369 +, CR-IP2-2012-01019 +  and CR-IP2-2012-07272 +

Arthur Burritt +, J. Kirkpatrick +, M. Woodby +, L. Coyle +, T. Cole +, T. Chan +, B. McCarthy +, N. Azevedo +, M. Tesoriero +, M. Troy +, R. Walpole +, D. Dewey +, R. Drake +, D. Gagnon +, J. Dinelli +, D. Mayer +, W. Wittich +, R. Dolanksy +, J. Ventosa +, T. McCaffrey +, P. Conroy +, R. Tagliamonte +, S. Manzione +, D. King +  and J. Lijoi +

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

05000247  +, 05000286  +, 00247  +  and 00286  +

ML130230023 +, ML12355A156 +  and ML13046A029 +

Technical Support Center +  and Emergency Operations Facility +

EN-HU-104 +  and EN-WM-101 +

Turbine Trip +  and Reactor Trip +

Arthur Burritt +  and Reactor Projects Region 1 Branch 2 +

IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +, IR 05000247/2013002 +...

IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71124.05 +, IP 71114.06 +, 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 71111.11Q +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.08P +, 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 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix M, Significance Determination Process Using Qualitative Criteria +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71124.02 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000247/2013002 +, IR 05000247/2011005 +  and IR 05000247/2010005 +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

PFP +, PFP-258 +, PFP-354 +, PFP-259 +  and PFP-254 +

Regulatory Guide 8.38 +, Regulatory Guide 1.109 +, Regulatory Guide 8.8 +  and Regulatory Guide 8.10 +

Manual Scram +  and Automatic Scram +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, Main Turbine +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Condenser +, Control Rod +  and Containment Spray +

TS-5.5.8.d +  and TS-3.7.13 +

Entergy +  and Ventosa J +

Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Water Inventory Control +, Probabilistic Risk Assessment +, Nondestructive Examination +, Functionality Assessment +, Significance Determination Process +, Foreign Material Exclusion +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Eddy Current Testing +, Operability Determination +, Annual Radiological Effluent Release Report +, Liquid penetrant +, Dissimilar Metal Weld +, Substantial potential for overexposure +, Power change +, Eddy Current Test +  and Reactive Inspection +