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Letter  and Inspection Report

Boron +, Iodine +, Xenon +  and Lead +

10 CFR 50 Appendix B +, 10 CFR 50.65 +, 10 CFR 50.71 +, 10 CFR 2.790 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 20.1101#c +  and 10 CFR 50.71#e +

Ann Marie Stone +, D. Palmer +, S. Kerr +, B. Barton +, R. McBride +, B. Youman +, D. Sible +, B. Adams +, D. Thompson +, D. Goldsmith +, D. Hoots +, W. Grundmann +, M. Snow +, D. Combs +, N. Vakili +, S. Stimac +, N. Valos +, J. Young +, S. Kuczynski +, K. Hansing +, R. Kolo +, S. Leach +, Sheila Ray +, James Smith +  and S. Koernshild +

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

05000454  +, 05000455  +, 00454  +  and 00455  +

EC-340158 +  and EC-345559 +

MA-AA-716-012 +, LS-AA-105 +, ER-AA-310 +, OP-AA-103-102 +, OP-AA-103-103 +, OP-AA-104-101 +, ER-AA-600 +, CC-AA-112 +, WC-AA-101 +, ER-AP-335-1012 +, OP-AA-101-111 +, CC-AA-404 +, OP-AA-103-104 +, OP-AA-108-109 +  and EE-AA-111 +

05000454/FIN-2003007-02 +, 05000454/FIN-2003007-01 +, 05000455/FIN-2003007-01 +, 05000455/FIN-2003007-02 +, 05000454/FIN-2003003-00 +, 05000455/FIN-2003003-00 +  and 05000454/FIN-2003004-00 +

Ann Marie Stone +  and NRC/RGN-III/DRP/RPB3 +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +

IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +, IR 05000454/2003007 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.00971 d (0.233 hours, 0.00139 weeks, 3.192395e-4 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

TI 2515/150 +, TI 2515/152 +  and TI 2515/153 +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.17 +, IP 71111.05 +, IP 71111.13 +, IP 71111.08 +, 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 71111.23 +, IP 71111.14 +, IP 71111.16 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +  and NRC Inspection Manual 0612, Power Reactor Inspection Reports +

IP 71111.08 +, IP 71121.02 +, IP 71121.01 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000454/2003007 +, IR 05000454/2003009 +  and IR 05000454/2003008 +

NRC Bulletin 03-01 +, NRC Bulletin 01-01 +  and NRC Bulletin 03-02 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +

ES-0.1 +, ES-1.3 +  and EP-MW-114-100 +

Regulatory Guide 1.45 +  and Regulatory Guide 1.160 +

Byron +  and NPF-66 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.13 +, TS-3.7.1 +, TS-3.7.a +  and TS-3.4.15 +

Exelon +  and Skolds J +

Boric Acid +, High winds +, High Radiation Area +, Fire Barrier +, Past operability +, Probabilistic Risk Assessment +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Condition Adverse to Quality +, Significance Determination Process +, Foreign Material Exclusion +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Pressure Boundary Leakage +, Core Exit Thermocouple +, Unidentified leakage +, Eddy Current Test +, Temporary Leak Repair +  and Leak Before Break +