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Letter  and Inspection Report

AR 00158155 +, AR 00158158 +, AR 00199697 +, AR 00199700 +, AR 00159414 +, AR 00208859 +  and AR 00165873 +

ASME Section XI +  and ASME Section V +

Environmental Protection Agency +, South Carolina Department of Health and Environmental Control +  and York County Emergency Management +

Boron +, Carbon +  and Hydrogen +

10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion X +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.55a#g4 +  and 10 CFR 50.71#e +

CR-CNS-12-00074 +  and CR-CNS-11-00044 +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +  and Mitigating Systems +

H.11 +, H.13 +  and P.2 +

05000413  +, 05000414  +, 00413  +, 00414  +  and 00369  +

Turbine Trip +  and Reactor Trip +

05000414/FIN-2007005-02 +, 05000414/FIN-2007005-03 +, 05000413/FIN-2007003-00 +, 05000414/FIN-2007001-00 +  and 05000413/FIN-2007004-00 +

NRC/RGN-II/DRP/RPB1 +  and Moorman J +

NRC Generic Letter 04-02 +, NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +, IR 05000413/2007005 +...

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +

TI 2515/166 +  and TI 2515/150 +

NRC Inspection Manual 0609 +  and NRC Inspection Manual 0609 Appendix K +

05000414/LER-2007-001, Regarding Failure to Comply with Action Statement in Technical Specification (TS) 3.3.1 for Loss of a Channel of the Solid State Protection System +, 05000413/LER-06-002 +, 05000413/LER-2007-004 +, 05000413/LER-2007-002 +, 05000413/LER-06-003 +, 05000413/LER-07-001 +, 05000413/LER-07-002 +, 05000414/LER-07-001 +, 05000413/LER-2007-003, Undervoltage Condition Resulted in the Actuation of the Emergency Diesel Generator +  and 05000413/LER-2006-001, Regarding Loss of Offsite Power Event Resulted in Reactor Trip of Both Catawba Units from 100% Power +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +, NEI 02-01 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0954, Advises That 860619 Submittal Summarizing Results of Survey Quantifying Insulation in Containment by Type & Location Complies W/Guidance in Generic Ltr 85-22 & Sser 2 (NUREG-0954) +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +  and NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +

PNO-II-07-012A, Update - Onsite Ground Water Tritium Contamination at the Catawba Nuclear Station Site, Units 1 & 2 +  and PNO-II-07-012, Catawba Nuclear Station Units 1 & 2, Onsite Ground Water Tritium Contamination +

4.16kV +  and 600V +

1ETA-18 +, 4A-A +, 2NC8-3V +, 2NB-503 +, 2KF-19 +, 2FW-53 +, 2FW-27A +, 2FW-55B +, 2VI-79 +, 2VI-312A +, 2VI-77B +, 1RFA-64 +, 2SM59-01 +, 2NC-52-6 +, 2RN-838 +, 2CRA-C-1 +, 1CRA-C-1 +  and 2EOC-15-IRT +

NPF-52 +  and NPF-35 +

Washington +  and Alabama +

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

TS-3.0.3 +, TS-3.8.1 +, TS-3.8.2 +, TS-3.3.1 +  and TS-3.6.14.c +

Morris J +  and Duke Energy +

Safe Shutdown +, Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Internal Flooding +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Coatings +, Fire impairment +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Condition Adverse to Quality +, Significance Determination Process +, Foreign Material Exclusion +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Integrated leak rate test +, Eddy Current Testing +, License Renewal +, Control of Heavy Loads +, Fuel cladding +, Liquid penetrant +  and Pressure Boundary Leakage +

WCAP-8110 +, WCAP-16406-P +, WCAP-13493 +  and WCAP-9404 +

WCAP-8110 +, WCAP-16406-P +, WCAP-13493 +  and WCAP-9404 +

WO 01780921 +, WO 01748147 +, WO 01726965 +, WO 1782004 +, WO 1782004#01 +, WO 01118529 +, WO 01723595 +, WO 01731978 +, WO 01779183 +, WO 1013458 +, WO 01731046#01 +, WO 98775894 +  and WO 98775902 +