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Letter  and Inspection Report

ANSI/ANS 3.1-1987 +  and ANSI/ANS-3.5-1985 +

ASME Section XI +  and ASME Section V +

Boron +, Carbon +  and Lead +

10 CFR 55 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 19.12 +, 10 CFR 50.65 +, 10 CFR 55.53 +, 10 CFR 72.48 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 48 +, 10 CFR 55.59#a2 +, 10 CFR 50.65#a1 +  and 10 CFR 50.65#a4 +

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

05000327  +, 05000328  +, 07200034  +, 00327  +  and 00328  +

Turbine Trip +  and Reactor Trip +

Widmann M +  and Reactor Projects Region 2 Branch 6 +

NRC Generic Letter 04-02 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +, ML070300881 +  and ML070300881 +

TI 2515/166 +, TI 2515/169 +  and TI 2515/150 +

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

IP 71111.08 +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71121.01 +  and IP 71152, Problem Identification and Resolution (PI&R) +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 96-07 +

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

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 +  and NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +

AOP +, ES-0.1 +, ES +, ES-1.3 +, AOP-N.08 +  and AOP-I.08 +

Regulatory Guide 1.187 +  and Regulatory Guide 3.72 +

1B-B +, 2B-B +, 1A-A +, 2A-A +, 2A-S +, 2A1-A +, 1B1-B +, 07-72-034 +, 13SIF-142 +, 07-62-527 +, 06SQN-12-ENG +, 20LCV-62-1 +  and 21GB-06001 +

Tennessee +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Containment Spray +

TS-3.8.1.1 +, TS-6.8.1 +  and TS-6.11 +

Tennessee Valley Authority +  and Singer K +

Safe Shutdown +, Boric Acid +, Packing leak +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Nondestructive Examination +, VT-2 +, Locked High Radiation Area +, Significance Determination Process +, Job Performance Measure +, Foreign Material Exclusion +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Integrated leak rate test +, Eddy Current Testing +, Liquid penetrant +, Unidentified leakage +  and Loss of condenser vacuum +