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Letter  and Inspection Report

AR 01101063 +, AR 01241371 +, AR 01139601 +, AR 01146236 +, AR 01235063 +  and AR 01234657 +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 20.1501 +, 10 CFR 50.75 +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +  and 10 CFR 50.75#g +

Ann Marie Stone +, Kenneth Riemer +, Billy Dickson +, C. Wilson +, J. Bauer +, J. Fiesel +, J. Houston +, P. Karaba +, J. Washko +, W. Trafton +, H. Vinyard +, S. Shields +, J. Kutches +, B. Maze +, J. Vergara +, K. Lyons +, K. Hedgspeth +, D. Rhoades +  and T. Simpkin +

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

05000373  +, 05000374  +, 00373  +  and 00374  +

05000373/FIN-2010006-01 +, 05000373/FIN-2011004-01 +, 05000373/FIN-2010006-05 +, 05000374/FIN-2010006-05 +, 05000374/FIN-2011004-01 +, 05000374/FIN-2010006-01 +, 05000373/FIN-2010003-01 +, 05000374/FIN-2010003-01 +, 05000373/FIN-2011003-02 +, 05000374/FIN-2011003-02 +, 05000373/FIN-2011001-00 +, 05000373/FIN-2011002-00 +, 05000373/FIN-2011003-00 +  and 05000374/FIN-2011003-00 +

Kenneth Riemer +  and NRC/RGN-III/DRP/B2 +

IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +, IR 05000373/2011004 +...

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.21 +, IP 71114.06 +, IP 71111.19 +, IP 71151 +, 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 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +, IP 71111.05Q +, IP 71111.12Q +, IP 71124.07, Radiological Environmental Monitoring Program +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.22 +, IP 71111.21 +, IP 71151 +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, 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 71114.06-05 +, IP 71151-05 +, IP 71152-05 +, IP 71111.06-05 +, IP 71124.06-05 +, IP 71124.07-05 +  and IP 71153-05 +

IR 05000373/2010006 +  and IR 05000373/2011004 +

05000373/LER-2011-01 +, 05000373/LER-2011-003, Regarding Secondary Containment Inoperable +  and 05000373/LER-2010-003, Regarding Standby Liquid Control Test Tank Seismic Analysis +

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-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +

Regulatory Guide 1.21 +, Regulatory Guide 1.109 +  and Regulatory Guide 1.23 +

Illinois +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, High Pressure Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +  and Control Rod +

TS-3.6.4.1 +  and TS-3.4.5 +

Pacilio M +  and Exelon +

High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Probabilistic Risk Assessment +, Temporary Modification +, High Energy Line Break +, Significance Determination Process +, Design basis earthquake +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Operability Determination +, Annual Radiological Effluent Release Report +, Pressure Boundary Leakage +, Fire Protection Program +, Downpower +, Power Uprate +  and Measurement Uncertainty Recapture +