Browse wiki

Letter  and Inspection Report

ASME Section XI +, ASME Section III +  and ASME Section V +

Boron +, Carbon +  and Lead +

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

R. Reynolds +, R. Bernhard +, B. Dungan +, N. Thomas +, D. Bodine +, J. Adams +, R. Douet +, Z. Kitts +, S. Tuthill +, J. Proffitt +, K. Wilkes +, G. Morris +, J. Whitaker +, D. Kulisek +, T. Niessen +, K. Parker +, R. Bruno +, J. Epperson +, J. Goulart +, M. A. Palmer +, M. H. Palmer +, J. Reisenbuechler +, D. Pickett +  and Kenneth Jones +

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

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

05000328/FIN-2006005-02 +  and 05000328/FIN-2006005-05 +

NRC/RGN-I/DRP/PB6 +  and Widmann M +

NRC Generic Letter 04-02 +  and NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +

IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +, IR 05000327/2006005 +...

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

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

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) +

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

NUREG-011 +, 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-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +  and NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +

AOP-N.08 +  and AOP-C.04 +

1A-A +, 2A-A +, 2A-S +, 1B1-B +, 07-72-034 +, 13SIF-142 +  and 07-62-527 +

Tennessee +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  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 +, Fire Barrier +, 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 +, Fire Protection Program +, Unidentified leakage +, Manual Operator Action +  and Loss of condenser vacuum +