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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

• 05000316/LER-2003-005, Regarding Reactor Trip Due to Steam Flow/Feed Flow Mismatch  + (Regarding Reactor Trip Due to Steam Flow/Feed Flow Mismatch)
• 05000339/LER-2006-001, Regarding Reactor Trip Due to Steam Generator Low Level Coincident with a Steam Flow Feed Flow Mismatch  + (Regarding Reactor Trip Due to Steam Generator Low Level Coincident with a Steam Flow Feed Flow Mismatch)
• 05000317/LER-2014-001, Regarding Reactor Trip Due to Turbine Control System Reboot  + (Regarding Reactor Trip Due to Turbine Control System Reboot)
• 05000483/LER-2008-006, Regarding Reactor Trip Due to Turbine Trip During Power Reduction Following Loss of C Condensate Pump  + (Regarding Reactor Trip Due to Turbine Trip During Power Reduction Following Loss of C Condensate Pump)
• 05000334/LER-1917-003, Regarding Reactor Trip Due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System  + (Regarding Reactor Trip Due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System)
• 05000272/LER-2003-002, Regarding Reactor Trip Due to Turbine Trip Caused by a 500KV Switchyard Breaker Trip  + (Regarding Reactor Trip Due to Turbine Trip Caused by a 500KV Switchyard Breaker Trip)
• 05000395/LER-2004-001, Regarding Reactor Trip Due to Valve Failure During Forced Shutdown  + (Regarding Reactor Trip Due to Valve Failure During Forced Shutdown)
• 05000456/LER-2010-001, Regarding Reactor Trip Due to Water Intrusion in Breakers Causing Circulating Water Pump Trips and Resulting in Loss of Condenser Vacuum  + (Regarding Reactor Trip Due to Water Intrusion in Breakers Causing Circulating Water Pump Trips and Resulting in Loss of Condenser Vacuum)
• 05000317/LER-2010-001, Regarding Reactor Trip Due to Water Intrusion Into Switchgear Protective Circuitry  + (Regarding Reactor Trip Due to Water Intrusion Into Switchgear Protective Circuitry)
• 05000261/LER-2010-007, Regarding Reactor Trip Due to a Degraded Connection on a Circuit Board in the Electro-Hydraulic Control Cabinet  + (Regarding Reactor Trip Due to a Degraded Connection on a Circuit Board in the Electro-Hydraulic Control Cabinet)
• 05000261/LER-2011-002, Regarding Reactor Trip Due to a Failed Relay Coil on RCP-3-X(B) and Actuation of Auxiliary Feedwater System  + (Regarding Reactor Trip Due to a Failed Relay Coil on RCP-3-X(B) and Actuation of Auxiliary Feedwater System)
• 05000334/LER-2006-004, Regarding Reactor Trip Due to a Failed Universal Logic Board in the Solid State Protection System  + (Regarding Reactor Trip Due to a Failed Universal Logic Board in the Solid State Protection System)
• 05000306/LER-2016-001, Regarding Reactor Trip Due to a Ground Fault Resulting in a Generator Trip  + (Regarding Reactor Trip Due to a Ground Fault Resulting in a Generator Trip)
• 05000261/LER-2014-001, Regarding Reactor Trip Due to a Two-out-of-Three Logic Signal from Steam Generator Water Level Protection Train B Logic Matrix  + (Regarding Reactor Trip Due to a Two-out-of-Three Logic Signal from Steam Generator Water Level Protection Train B Logic Matrix)
• 05000289/LER-2012-004, Regarding Reactor Trip During Downpower Due to Condensate Booster Pump Trip  + (Regarding Reactor Trip During Downpower Due to Condensate Booster Pump Trip)
• 05000346/LER-2016-001, Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level  + (Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level)
• 05000318/LER-2006-001, Regarding Reactor Trip During Performance of Maintenance Clearance Order  + (Regarding Reactor Trip During Performance of Maintenance Clearance Order)
• 05000251/LER-2010-004, Regarding Reactor Trip During Replacement of Degraded Relay in the Reactor Protection System  + (Regarding Reactor Trip During Replacement of Degraded Relay in the Reactor Protection System)
• 05000317/LER-2004-001, Regarding Reactor Trip During Scheduled Maintenance  + (Regarding Reactor Trip During Scheduled Maintenance)
• 05000281/LER-2015-001, Regarding Reactor Trip During Turbine Testing  + (Regarding Reactor Trip During Turbine Testing)
• 05000305/LER-2007-001, Regarding Reactor Trip During Turbine Trip Mechanism Testing  + (Regarding Reactor Trip During Turbine Trip Mechanism Testing)
• 05000261/LER-2016-004, Regarding Reactor Trip During the Performance of a Visual Inspection of the Main Turbine Trip Block  + (Regarding Reactor Trip During the Performance of a Visual Inspection of the Main Turbine Trip Block)
• 05000315/LER-2005-001, Regarding Reactor Trip Following Intermediate Range High Flux Signal  + (Regarding Reactor Trip Following Intermediate Range High Flux Signal)
• 05000443/LER-2003-002, Regarding Reactor Trip Following the Loss of a Main Feed Pump  + (Regarding Reactor Trip Following the Loss of a Main Feed Pump)
• 05000391/LER-2016-008, Regarding Reactor Trip Resulting from Failure of 2B Main Bank Transformer  + (Regarding Reactor Trip Resulting from Failure of 2B Main Bank Transformer)

• 05000251/LER-2015-002, Regarding Reactor Trip Resulting from Generator Differential Lockout  + (Regarding Reactor Trip Resulting from Generator Differential Lockout)

• 05000251/LER-2010-002, Regarding Reactor Trip Resulting from Steam Generator Feedwater Pump Trip  + (Regarding Reactor Trip Resulting from Steam Generator Feedwater Pump Trip)
• 05000335/LER-2015-001, Regarding Reactor Trip While Performing Reactor Protection System Logic Matrix Test  + (Regarding Reactor Trip While Performing Reactor Protection System Logic Matrix Test)
• 05000483/LER-2005-001, Regarding Reactor Trip While Replacing RP043 Control Cabinet Power Supply  + (Regarding Reactor Trip While Replacing RP043 Control Cabinet Power Supply)
• 05000261/LER-2016-005, Regarding Reactor Trip and Automatic System Actuation Due to Weather-Related Loss of Offsite Power  + (Regarding Reactor Trip and Automatic System Actuation Due to Weather-Related Loss of Offsite Power)
• 05000457/LER-2003-004, Regarding Reactor Trip and Auxiliary Feedwater Emergency Safeguards Actuation Due to Cascading Feedwater Pump Trips Caused by a Lack of Preventative Maintenance  + (Regarding Reactor Trip and Auxiliary Feedwater Emergency Safeguards Actuation Due to Cascading Feedwater Pump Trips Caused by a Lack of Preventative Maintenance)
• 05000400/LER-2016-004, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power  + (Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power)
• 05000391/LER-2016-004, Regarding Reactor Trip and Safety Injection Actuation Caused by Turbine Governor Valve Failure  + (Regarding Reactor Trip and Safety Injection Actuation Caused by Turbine Governor Valve Failure)
• 05000327/LER-2011-005, Regarding Reactor Trip as a Result of Reactor Coolant Pump Bus Undervoltage  + (Regarding Reactor Trip as a Result of Reactor Coolant Pump Bus Undervoltage)
• 05000327/LER-2011-003-01, Regarding Reactor Trip as a Result of Turbine Control Card Failure - Supplement 1  + (Regarding Reactor Trip as a Result of Turbine Control Card Failure - Supplement 1)
• 05000305/LER-2006-012, Regarding Reactor Trip from Loss of Instrument Bus  + (Regarding Reactor Trip from Loss of Instrument Bus)
• 05000305/LER-2006-013, Regarding Reactor Trip from Nuclear Instrumentation Low Range-High Flux Trip Caused by Blind Relay Contact Failure  + (Regarding Reactor Trip from Nuclear Instrumentation Low Range-High Flux Trip Caused by Blind Relay Contact Failure)
• 05000457/LER-2009-001, Regarding Reactor Trip in Over Temperature Delta Temperature Due to a Signal Spike on One Channel with Another Channel Placed in the Tripped Condition for Surveillance Testing  + (Regarding Reactor Trip in Over Temperature Delta Temperature Due to a Signal Spike on One Channel with Another Channel Placed in the Tripped Condition for Surveillance Testing)
• 05000261/LER-2013-003, Regarding Reactor Trip on 4KV Bus Undervoltage During Load Transfer  + (Regarding Reactor Trip on 4KV Bus Undervoltage During Load Transfer)
• 05000280/LER-2011-001, Regarding Reactor Trip on Both Units Due to Loss of Offsite Power  + (Regarding Reactor Trip on Both Units Due to Loss of Offsite Power)
• 05000498/LER-2004-001, Regarding Reactor Trip on High Steam Generator Levels Initiated by Failure of Inverter 1201  + (Regarding Reactor Trip on High Steam Generator Levels Initiated by Failure of Inverter 1201)
• 05000336/LER-2010-002, Regarding Reactor Trip on Low Condenser Vacuum  + (Regarding Reactor Trip on Low Condenser Vacuum)
• 05000499/LER-2011-002, Regarding Reactor Trip on Main Generator Lockout  + (Regarding Reactor Trip on Main Generator Lockout)
• 05000335/LER-2012-005-01, Regarding Reactor Trip on Turbine Trip  + (Regarding Reactor Trip on Turbine Trip)
• 05000529/LER-2003-001, Regarding Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve  + (Regarding Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve)
• 05000400/LER-2015-003, Regarding Reactor Vessel Head Nozzle Repairs  + (Regarding Reactor Vessel Head Nozzle Repairs)
• 05000395/LER-2012-003, Regarding Reactor Vessel Head Penetrations Not Meeting Requirements of 10 CFR50.55(g)(6)(ii)(D)  + (Regarding Reactor Vessel Head Penetrations Not Meeting Requirements of 10 CFR50.55(g)(6)(ii)(D))
• 05000395/LER-2014-002, Regarding Reactor Vessel Head Penetration Weld Indications Attributed to Primary Water Stress Corrosion Cracking  + (Regarding Reactor Vessel Head Penetration Weld Indications Attributed to Primary Water Stress Corrosion Cracking)
• 05000254/LER-2013-003, Regarding Reactor Vessel Head Vent Line Leak Due to Weld Defect  + (Regarding Reactor Vessel Head Vent Line Leak Due to Weld Defect)
• 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event  + (Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event)
• 05000410/LER-2011-004, Regarding Reactor Water Cleanup System Automatic Isolation Function Disabled During Troubleshooting  + (Regarding Reactor Water Cleanup System Automatic Isolation Function Disabled During Troubleshooting)