CNL-14-065, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-491)
CNL-13-122, Service List Update for Documents Containing Official Use Only and Safeguards Information
L-90-009, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief 1-ISI-18, Examination and Testing of Snubbers
L-90-017, Technical Specifications (TS) Change 437 - Scram Discharge Volume Water Level Setpoint
05000260/LER-1999-007, :on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With
05000296/LER-1995-007-02, :on 951108,unplanned Esfa Occurred Following Transfer of 480V Rmov Board 3B to Normal Power Supply After Temporary Normal Supply Breaker Was Replaced.Caused by Faulty Amptector Trip Actuator
05000296/LER-2008-002, Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure
05000296/LER-2007-005, Automatic Reactor Scram Due to Main Generator Load Reject
05000296/LER-2007-004, Re Manual Isolation of High Pressure Core Injection Due to Steam Leak
05000259/LER-2007-009, Invalid High Level in Moisture Separator Results in Turbine Trip and Reactor Scram
05000296/LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe
05000259/LER-2007-008, For Browns Ferry, Unit 1, Manual Reactor Scram Due to an Electro Hydraulic Control System Leak
05000259/LER-2007-007, Regarding Automatic Reactor Scram from a Neutron Monitoring Trip Signal
05000296/LER-2007-002, Regarding Unplanned Inoperability of the Unit 3 High Pressure Coolant Injection System Due to Loss of 120 Vac Instrument Power
05000259/LER-2007-006, Regarding Inoperable Reactor Core Isolation Cooling Primary Containment Isolation Instrumentation for a Period Longer than Allowed by the Plants Technical Specifications
05000259/LER-2007-005, Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank
05000259/LER-2007-004, Regarding Turbine Control Valve Fast Closure Turbine Scram Function Inoperable for a Period Longer than Allowed by the Plants TSs
05000260/LER-2007-002, Re Main Steam Relief Valve as Found Setpoint Exceeded Technical Specifications Lift Pressure
05000259/LER-2007-001, Regarding Average Power Range Monitors Inoperable in Excess of Technical Specification Allowable Outage Time in Mode 2
05000259/LER-2007-002, Regarding Manual Scram Due to an Unisolable EHC Leak
05000296/LER-2006-001, Re Main Steam Relief Valve Inoperability LCO Exceeded as a Result of Lift Setpoint Drift
05000296/LER-2005-003, Regarding Reactor Scram from Main Turbine Trip During Switching Operation
05000296/LER-2005-002, Reactor Scram from Main Turbine Trip on Low Condenser Vacuum
05000260/LER-2005-007, Brown Ferry Nuclear, Unit 2, Regarding Reactor Scram Due to Low Reactor Water Level Caused by Loss of Feedwater Pumps
05000260/LER-2005-005, Regarding Primary to Secondary Containment Leakage Via the Residual Heat Removal System in Excess of Analyzed Limits
05000260/LER-2005-006, Re Low Voltage on Shutdown Battery Cells Results in Condition Prohibited by Technical Specifications
05000260/LER-2005-003, Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown
05000260/LER-2005-004, Regarding Primary to Secondary Leakage in Residual Heat Removal Heat Exchanger in Excess of Analyzed Limits
05000260/LER-2005-002, Regarding Primary Containment Isolation Valve Inoperable in Excess of Technical Specifications Allowable Outage Time
05000296/LER-2005-001, Regarding Automatic Reactor Scram Due to False Main Transformer Differential Signal
05000260/LER-2005-001, Regarding Loss of High Pressure Coolant Injection (HPCI) Discharge Piping Keep-Fill
05000260/LER-2004-003, Regarding Inoperability of Turbine Control Valve Fast Closure Pressure Switches Beyond TS Allowable Outage Time
05000260/LER-2004-002, Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2
05000260/LER-2003-004, Regarding Cable Separations Design Error Related to Appendix Requirements
05000259/LER-2007-003, Regarding Main Steam Line High Flow Instrument Inoperable in Excess of Technical Specification Allowable Outage Time