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Letter  and Inspection Report

Boron +, Carbon +  and Hydrogen +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 72.48 +, 10 CFR 50.54 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b2 +, 10 CFR 50.47#b5 +  and 10 CFR 50.55a#g6iiD +

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

05000327  +, 05000328  +, 00327  +  and 00328  +

Alan Blamey +  and Reactor Projects Region 2 Branch 6 +

NRC Generic Letter 07-01 +, 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 +

ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +, ML16043A261 +  and ML16043A261 +

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

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71124.08 +, IP 71111.13 +, IP 71111.08 +, IP 71111.19 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71114, Reactor Safety Emergency Preparedness +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

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

AOP-N.03 +, Emergency Plan +  and AOP-M.03 +

3R-C +  and 07-14-215 +

Tennessee +, Georgia +  and Washington +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam +  and Containment Spray +

Tennessee Valley Authority +  and James Shea +

Boric Acid +, Health Physics Network +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, Temporary Modification +, Functionality Assessment +, Locked High Radiation Area +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Foreign Material Exclusion +, Process Control Program +, Operability Determination +, Coast down +, Unidentified leakage +, Siren +  and Thermal fatigue +

WO 115428320 +, WO 114039093 +, WO 112732423 +, WO 115801465 +, WO 114971023 +, WO 117105469 +, WO 117303798 +, WO 117063755 +, WO 117406963 +, WO 115901948 +, WO 116398040 +, WO 117352715 +, WO 117173071 +  and WO 115796111 +