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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

Iodine +, Cobalt +, Cesium +, Iron +, Nickel +, Carbon +, Xenon +, Zinc +, Manganese +  and Tin +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 20.2206 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 55.59#a2 +, 10 CFR 50.65#a4 +  and 10 CFR 50.75#g +

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

NL-05-1672 +, NL-08-0667, Unit 1 Pressurizer Nozzle Full Structural Weld Overlay Evaluation and Nondestructive Examination Results, Spring 2008 Outage (1R14) +, NL-07-0859, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12) - Revision 1 +, NL-07-1260, Unit 2, Results of Reactor Pressure Vessel Head Inspections Required by First Revised Order EA-03-009 +, NL-07-0803, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12) +, NL-07-0837, Pressurizer Nozzle Full Structural Weld Overlay Evaluation +, NL-05-0990, Response to NRC Request for Additional Information Regarding Relaxation from First Revised NRC Order EA-03-009 +, NL-05-0923, Results of Inspections Required by NRC BL-04-001 and First Revised NRC Order EA-03-009 +, NL-04-1948, and Vogtle Electric Generating Plant - Response to NRC Questions Regarding Southern Nuclear Operating Company Response to NRC Bulletin 2004-01 +  and NL-04-1150, 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations & Steam Space Piping Connections at Pressurized-Water Reactors +

05000424  +, 05000425  +, 00424  +  and 00425  +

Scott Shaeffer +  and NRC/RGN-II/DRP/RPB2 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +, ML090200064 +  and ML090200064 +

IP 71122.02 +, IP 71121.02 +, IP 71121.01 +  and IP 71152, Problem Identification and Resolution (PI&R) +

Co-60 +, Cs-137 +  and Mn-54 +

Westinghouse +  and Cutler-Hammer +

NL-05-1672 +, NL-08-0667, Unit 1 Pressurizer Nozzle Full Structural Weld Overlay Evaluation and Nondestructive Examination Results, Spring 2008 Outage (1R14) +, NL-07-0859, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12) - Revision 1 +, NL-07-1260, Unit 2, Results of Reactor Pressure Vessel Head Inspections Required by First Revised Order EA-03-009 +, NL-07-0803, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12) +, NL-07-0837, Pressurizer Nozzle Full Structural Weld Overlay Evaluation +, NL-05-0990, Response to NRC Request for Additional Information Regarding Relaxation from First Revised NRC Order EA-03-009 +, NL-05-0923, Results of Inspections Required by NRC BL-04-001 and First Revised NRC Order EA-03-009 +, NL-04-1948, and Vogtle Electric Generating Plant - Response to NRC Questions Regarding Southern Nuclear Operating Company Response to NRC Bulletin 2004-01 +  and NL-04-1150, 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations & Steam Space Piping Connections at Pressurized-Water Reactors +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1608 +

Regulatory Guide 8.13 +  and Regulatory Guide 8.8 +

2X3D-AA-A01A +, 2PV-0507A +, 1HV-11817 +, 1X3D-AA-A01A +, 1X3D-AA-M04A +, 1HV-1669A +, 07-07-019 +, 07-06-007 +, 07-08-008 +, 2K5-1202-006-02 +, 2K5-1202-006-01 +, 2K3-1202-036-01 +, 2K3-1203-026-01 +, 2K3-1202-099-01 +, 2K3-1203-026-02 +, 1PT-11741 +, 1PT-11742 +, 22X3D-BG-D03B +, 1X3D-AA-E12A +, 1X3D-AA-E20A +, 1X3D-AA-E26A +, 1X3D-AA-E28A +, 1X3D-AA-E30A +, 1X3D-BD-KO4F +, 1X3D-BD-KO5W +, 1X3D-BD-K05X +, 1HV-1669B +, 2K3-1202-406-01 +, 2X3D-AA-E03A +, 2X3D-AA-E04A +...

Vogtle +  and NPF-68 +

Georgia +  and Washington +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Decay Heat Removal +  and Containment Spray +

TS-3.8.5 +, TS-3.8.4 +, TS-3.8.6 +, TS-5.4 +  and TS-5.7.1 +

Southern Nuclear +  and Tynan T +

Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Weld Overlay +, Temporary Modification +, Locked High Radiation Area +, Missed surveillance +, Significance Determination Process +, Job Performance Measure +, Annual Radioactive Effluent Release Report +, Process Control Program +, Eddy Current Testing +, Fire Protection Program +, Scaffolding +, Substantial potential for overexposure +, Overexposure +, Thermography +  and Water hammer +

WO 2081126401 +, WO 2071889201 +, WO 1081701001 +, WO 1081751501 +, WO 2080253001 +, WO 1080381901 +, WO 1081073801 +, WO 00567352 +, WO 1060607902 +, WO 1060607903 +, WO 1060607904 +, WO 1060607905 +, WO 1060607906 +  and WO 1060607907 +