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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20274A038  + (Re Re Re Repairs to Leak at the Elbow Sownstream of 1CC-0277 CS PMP 1-011-03 SL Clr CCW Ret)
• ML042310120  + (Re Re-Schedule of Initial Operator License Re-Take Examination)
• ML041200575  + (Re Re-scheduling of Initial Operator License Examinations)
• 05000454/LER-2004-001, Re Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication  + (Re Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication)
• 05000400/LER-2001-004, Re Reactor Coolant Loops Made 4 Technical Specification Violation  + (Re Reactor Coolant Loops Made 4 Technical Specification Violation)
• 05000293/LER-2003-006, Re Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation  + (Re Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation)
• ML033370097  + (Re Reactor Coolant Pump Leakage - Letter to Individual)
• ML033370070  + (Re Reactor Coolant Pump Leakage - Letter to Mr. Gunter of Reactor Watchdog Project, Nuclear Information and Resource Service)
• 05000369/LER-2005-001, Re Reactor Coolant System Leakage Detection Instrumentation Inoperable  + (Re Reactor Coolant System Leakage Detection Instrumentation Inoperable)
• 05000414/LER-2004-001, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators  + (Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators)
• 05000482/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines  + (Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines)
• 05000336/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve  + (Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve)
• 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications  + (Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications)
• 05000318/LER-2013-001, Re Reactor Coolant System Pressure Boundary Leakage in Valve Leakoff Line Weld  + (Re Reactor Coolant System Pressure Boundary Leakage in Valve Leakoff Line Weld)
• 05000373/LER-2005-002, Re Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum Pump Discharge Check Valve 1E51-F028 Failed Local Leak Rate Test  + (Re Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum Pump Discharge Check Valve 1E51-F028 Failed Local Leak Rate Test)
• 05000373/LER-2003-003, Re Reactor Core Isolation Cooling High Steam Flow Isolation Differential Pressure Switches Failed Due to Torn Diaphragm  + (Re Reactor Core Isolation Cooling High Steam Flow Isolation Differential Pressure Switches Failed Due to Torn Diaphragm)
• 05000325/LER-2005-002, Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown  + (Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown)
• 05000529/LER-2006-005, Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component  + (Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component)
• 05000423/LER-2007-003, Re Reactor Head Vent Valve Circuits Not Isolated from Control Room During Fire Scenario  + (Re Reactor Head Vent Valve Circuits Not Isolated from Control Room During Fire Scenario)
• 05000331/LER-2003-003, Re Reactor Mode Change with LCO in Effect in Violation of Technical Specification 3.0.4  + (Re Reactor Mode Change with LCO in Effect in Violation of Technical Specification 3.0.4)
• 05000454/LER-2011-002, Re Reactor Pressure Vessel Head Penetration Nozzle Weld Flaws Attributed to Primary Water Stress Corrosion Cracking  + (Re Reactor Pressure Vessel Head Penetration Nozzle Weld Flaws Attributed to Primary Water Stress Corrosion Cracking)
• 05000255/LER-2006-004, Re Reactor Protection System Actuation  + (Re Reactor Protection System Actuation)
• 05000483/LER-2002-004, Re Reactor Protection System Actuation While Performing Main Turbine Shell Warming in Mode 4  + (Re Reactor Protection System Actuation While Performing Main Turbine Shell Warming in Mode 4)
• 05000260/LER-2005-003, Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown  + (Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown)
• 05000443/LER-2005-005, Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6  + (Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6)

• 05000249/LER-2002-006, Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure  + (Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure)

• 05000265/LER-2001-001-01, Re Reactor Scram Due to Failure of Main Power Transformer  + (Re Reactor Scram Due to Failure of Main Power Transformer)
• 05000416/LER-2002-003, Re Reactor Scram Due to Loss of Service Transformer 21  + (Re Reactor Scram Due to Loss of Service Transformer 21)
• 05000397/LER-2007-004, Re Reactor Scram Due to Tripped Condensate Booster Pump  + (Re Reactor Scram Due to Tripped Condensate Booster Pump)
• 05000397/LER-2009-001, Re Reactor Scram Due to Turbine Control System Trip Header Depressurization  + (Re Reactor Scram Due to Turbine Control System Trip Header Depressurization)
• 05000397/LER-2005-004, Re Reactor Scram During Plant Startup Due to Reactor Feedwater Pump Trip  + (Re Reactor Scram During Plant Startup Due to Reactor Feedwater Pump Trip)
• 05000387/LER-2006-004-01, Re Reactor Scram During Transfer of RPS Power Supplies  + (Re Reactor Scram During Transfer of RPS Power Supplies)
• 05000293/LER-2007-005, Re Reactor Scram Resulting from Low Vacuum Turbine Trip  + (Re Reactor Scram Resulting from Low Vacuum Turbine Trip)
• 05000260/LER-2004-002, Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2  + (Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2)
• 05000219/LER-2001-001, Re Reactor Shutdown Completion Required by Technical Specifications  + (Re Reactor Shutdown Completion Required by Technical Specifications)
• 05000265/LER-2002-003, Re Reactor Shutdown Due to Failure of Reactor Steam Dryer Form Flow-Induced Vibrations as a Result of Extended Power Uprate  + (Re Reactor Shutdown Due to Failure of Reactor Steam Dryer Form Flow-Induced Vibrations as a Result of Extended Power Uprate)
• 05000266/LER-2004-003, Re Reactor Shutdown Required by Containment Penetration Tsac 3.6.3.C  + (Re Reactor Shutdown Required by Containment Penetration Tsac 3.6.3.C)
• 05000305/LER-2005-001, Re Reactor Thermal Power Eight-Hour Average Limit Exceeded  + (Re Reactor Thermal Power Eight-Hour Average Limit Exceeded)
• 05000382/LER-2002-002, Re Reactor Trip Circuit Breakers Rendered Inoperable During Response Time Testing  + (Re Reactor Trip Circuit Breakers Rendered Inoperable During Response Time Testing)
• 05000528/LER-2006-006, Re Reactor Trip Due to Core Protection Calculator Generated Low Departure from Nuclear Boiling Ratio (DNBR) Trip Signal  + (Re Reactor Trip Due to Core Protection Calculator Generated Low Departure from Nuclear Boiling Ratio (DNBR) Trip Signal)
• 05000397/LER-2005-003, Re Reactor Trip Due to Digital Electro-Hydraulic (DEH) Control System Failure  + (Re Reactor Trip Due to Digital Electro-Hydraulic (DEH) Control System Failure)
• 05000317/LER-2006-004, Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System  + (Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System)
• 05000424/LER-2001-001-01, Re Reactor Trip Due to Loss of Generator Excitation  + (Re Reactor Trip Due to Loss of Generator Excitation)
• 05000317/LER-2002-003, Re Reactor Trip Due to Loss of Reactor Coolant Pump Motor Oil  + (Re Reactor Trip Due to Loss of Reactor Coolant Pump Motor Oil)
• 05000400/LER-2002-001, Re Reactor Trip Due to Main Feedwater Regulating Valve Bypass Valve Failure  + (Re Reactor Trip Due to Main Feedwater Regulating Valve Bypass Valve Failure)
• 05000457/LER-2005-002, Re Reactor Trip Due to Main Generator C Phase Bushing Failure Due to Overheating  + (Re Reactor Trip Due to Main Generator C Phase Bushing Failure Due to Overheating)
• 05000318/LER-2003-003, Re Reactor Trip Due to Main Turbine Governor Valves Closing  + (Re Reactor Trip Due to Main Turbine Governor Valves Closing)
• 05000311/LER-2001-008, Re Reactor Trip Due to Pressurizer Spray Valve 2PS3 Failure  + (Re Reactor Trip Due to Pressurizer Spray Valve 2PS3 Failure)
• 05000338/LER-2007-001, Re Reactor Trip Due to Steam Generator Low Level Coincident with a Steam Flow Feed Flow Mismatch  + (Re Reactor Trip Due to Steam Generator Low Level Coincident with a Steam Flow Feed Flow Mismatch)
• 05000311/LER-2007-002, Re Reactor Trip Due to a Breach in the Condensate System  + (Re Reactor Trip Due to a Breach in the Condensate System)
• 05000311/LER-2004-006, Re Reactor Trip Due to a Malfunction of Main Feedwater Regulating Valve (21 BF1 9)  + (Re Reactor Trip Due to a Malfunction of Main Feedwater Regulating Valve (21 BF1 9))