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Letter  and Inspection Report

ANSI N13.1-1969 +  and ANSI/ANS-2.5-1984 +

IWC-3000 +  and IWB-3000 +

ASME Section XI +, ASME Section IV +  and ASME Section V +

Boron +, Iodine +, Cobalt +, Germanium +  and Carbon +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix B +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 19.12 +, 10 CFR 20.1802 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.73#a2iB +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +  and 10 CFR 20.1703#e +

CY 2004 +  and CY 2003 +

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

CY 2004 +  and CY 2003 +

05000369  +, 05000370  +, 07200038  +, 00369  +  and 00370  +

05000369/FIN-2005002-08 +, 05000369/FIN-2005002-09 +, 05000370/FIN-2005002-01 +, 05000370/FIN-2005002-04 +, 05000369/FIN-2004008-02 +  and 05000369/FIN-2004008-002 +

Ernstes M +  and NRC/RGN-II/DRP/RPB1 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +

IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +, IR 05000369/2005002 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 6.018519e-4 d (0.0144 hours, 8.597884e-5 weeks, 1.9786e-5 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0609/Appendix A +  and NRC Inspection Manual 0609/Appendix F +

IP 71111.05 +, IP 71111.08 +  and IP 71152, Problem Identification and Resolution (PI&R) +

05000369/LER-2004-02 +  and 05000369/LER-2004-002, Regarding Main Steam Isolation Valve Inoperable +

NRC Bulletin 04-01 +  and NRC Bulletin 02-01 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

SAP +, CP +, Emergency Plan +  and CP-189 +

Regulatory Guide 1.45 +, Regulatory Guide 1.33 +, Regulatory Guide 1.21 +, Regulatory Guide 4.15 +, Regulatory Guide 8.15 +  and Regulatory Guide 3.54 +

SR-3.0.3 +, SR-3.4.13.1 +, SR-3.4.15.2 +, SR-3.4.15.3 +, SR-3.4.15.4 +  and SR-3.4.15.5 +

1SM-1 +, 1SM-7 +, 1SM-3 +, 2SM-1 +, 1CA-42B +, 2EMF-51A +, 2PZR-W3SE +, 2PZR-W4ASE +, 2PZR-W4BSE +, 2PZR-W4CSE +, 2PZR-W2SE +, 1EMF-38L +, 2PZR-W11 +, 2MCR-NC-4791 +, 2NV-217 +, 2SGC-INLET +, 2SGC-OUTLET +, 2RPV-CRDM-71 +, 2PZR-W13C +, 2RPV-W01 +, 2RPV-W18 +, 2MCA-ND-5503 +, 2KF-114 +, 1NI-144B +, 2ND-19A +, 2ND-4B +, 1EMF-9 +, 2NI-76A +, 2HM-23 +, 2HM-113 +...

Mcguire +  and McGuire +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Moisture Separator Reheater +, Control Rod +  and Main Steam +

TS-3.7.2 +, TS-5.7.2 +, TS-3.4.13 +, TS-1.1 +, TS-3.4.15 +, TS-5.0 +, TS-5.4.1 +, TS-5.5 +, TS-5.4.1.a +, TS-5.4.1.d +, TS-5.4 +  and TS-5.5.5 +

Duke Energy +  and Gordon Peterson +

Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Grab sample +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Nondestructive Examination +, Temporary Modification +, VT-2 +, High Energy Line Break +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Flow Accelerated Corrosion +, Large early release frequency +, Eddy Current Testing +, Operability Determination +, Liquid penetrant +, Pressure Boundary Leakage +, Through Wall Leak +, Fire Protection Program +, Downpower +, Flow Induced Vibration +, Operability Assessment +, Unidentified leakage +, Overexposure +  and Operational leakage +

WO 98691893 +, WO 98690669 +  and WO 98690668 +