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Letter  and Inspection Report

IWC-3000 +  and IWB-3000 +

ASME Section XI +  and ASME Section V +

Iodine +  and Germanium +

10 CFR 50.73 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 20.1703 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#a2 +, 10 CFR 50.73#a2vD +, 10 CFR 55.59#a2 +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +  and 10 CFR 50.65#a4 +

CY 2004 +  and CY 2003 +

J. Steele +, F. Froscello +, D. Matherly +, A. Feltman +, A. Elms +, R. Marsh +, E. Scillian +, F. Leonard +, R. Marks +, C. Sherman +, W. Crouch +, R. DeLong +, J. Corey +, B. OGrady +, J. DeDimenico +, A. Fletcher +, D. Sanchez +, J. Sparks +, B. Aukland +, D. Nye +, C. Ottenfeld +, L. Meyer +, K. Welch +, Jeffrey Mitchell +  and Rosalyn Jones +

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

CY 2004 +  and CY 2003 +

05000259  +, 05000260  +, 05000296  +, 00259  +, 00296  +  and 00260  +

Turbine Trip +  and Reactor Trip +

05000260/FIN-2006002-01 +, 05000260/FIN-2006002-02 +  and 05000260/FIN-2006002-03 +

Widmann M +  and Reactor Projects Region 2 Branch 6 +

IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +, IR 05000259/2006002 +...

0.011 d (0.265 hours, 0.00158 weeks, 3.62997e-4 months)  +  and 0.0111 d (0.265 hours, 0.00158 weeks, 3.633775e-4 months)  +

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

IP 71151 +, IP 71122.01 +, IP 71153, Event Followup +, IP 71121.01 +, IP 71121.03 +, IP 71122.03 +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000259/2006002 +, IR 05000260/2005002 +, IR 05000260/2004004 +, IR 05000259/2005004 +  and IR 05000259/2005003 +

05000260/LER-2005-005, Regarding Primary to Secondary Containment Leakage Via the Residual Heat Removal System in Excess of Analyzed Limits +, 05000260/LER-2005-003, Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown +  and 05000260/LER-2005-007, Brown Ferry Nuclear, Unit 2, Regarding Reactor Scram Due to Low Reactor Water Level Caused by Loss of Feedwater Pumps +

Information Notice 85-92 +  and Information Notice 2006-01, Torus Cracking in a BWR Mark-I Containment +

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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Regulatory Guide 1.97 +, Regulatory Guide 1.33 +, Regulatory Guide 1.21 +, Regulatory Guide 8.38 +  and Regulatory Guide 8.15 +

5E-7 +, 5E-6 +  and N4D-NV +

Tennessee +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Decay Heat Removal +, Main Steam Line +, Reactor Water Recirculation +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +

TS-5.4 +, TS-5.7 +  and TS-5.5.4 +

Tennessee Valley Authority +  and Singer K +

Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Internal Flooding +, Nondestructive Examination +, Temporary Modification +, Locked High Radiation Area +, Significance Determination Process +, Foreign Material Exclusion +, Feedwater Heater +, Scram Discharge Volume +, Annual Radiological Environmental Operating Report +, Fast acting solenoid valve +, EVT-1 +, Downpower +  and Unidentified leakage +