Search by property

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

• 05000346/LER-1997-004-01, Regarding Reactor Coolant Pump Motor Oil Piping Not Protected from Leakage as Required Per 10CFR50, Appendix R  + (Regarding Reactor Coolant Pump Motor Oil Piping Not Protected from Leakage as Required Per 10CFR50, Appendix R)
• 05000395/LER-2003-004, Regarding Reactor Coolant Pump Seal Injection Nozzle Leakage  + (Regarding Reactor Coolant Pump Seal Injection Nozzle Leakage)
• 05000443/LER-2014-002, Regarding Reactor Coolant Pump Undervoltage Time Delay Relays Exceed Acceptance Criteria  + (Regarding Reactor Coolant Pump Undervoltage Time Delay Relays Exceed Acceptance Criteria)
• 05000250/LER-2007-004-01, Regarding Reactor Coolant System Boundary Leakage  + (Regarding Reactor Coolant System Boundary Leakage)
• 05000250/LER-2007-004, Regarding Reactor Coolant System Boundary Leakage  + (Regarding Reactor Coolant System Boundary Leakage)
• 05000346/LER-2016-004, Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation  + (Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation)
• 05000354/LER-2005-003, Regarding Reactor Coolant System Leak from Check Valve Position Indicator  + (Regarding Reactor Coolant System Leak from Check Valve Position Indicator)
• 05000321/LER-2016-003, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage  + (Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage)
• 05000302/LER-2003-003, Regarding Reactor Coolant System Pressure Boundary Leakage Limit Exceeded Due to Pressurizer Instrument Tap Nozzle Cracks  + (Regarding Reactor Coolant System Pressure Boundary Leakage Limit Exceeded Due to Pressurizer Instrument Tap Nozzle Cracks)
• 05000317/LER-2014-007, Regarding Reactor Coolant System Pressure Boundary Leakage in Reactor Coolant Pump Differential Pressure Transmitter Tubing  + (Regarding Reactor Coolant System Pressure Boundary Leakage in Reactor Coolant Pump Differential Pressure Transmitter Tubing)
• 05000317/LER-2007-001, Regarding Reactor Coolant System Pressure Boundary Leakage in Pump Cover Heat Exchanger  + (Regarding Reactor Coolant System Pressure Boundary Leakage in Pump Cover Heat Exchanger)
• 05000250/LER-2014-002, Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld  + (Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld)
• 05000313/LER-2010-002, Regarding Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of Pressurizer Level Instrument Tap Resulted in Degradation of a Principal Safety Barrier  + (Regarding Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of Pressurizer Level Instrument Tap Resulted in Degradation of a Principal Safety Barrier)
• 05000289/LER-2003-003, Regarding Reactor Coolant System Pressure Boundary Leakage Due to Degradation of an Alloy 600 Pressurizer Heater Bundle Diaphragm Plate  + (Regarding Reactor Coolant System Pressure Boundary Leakage Due to Degradation of an Alloy 600 Pressurizer Heater Bundle Diaphragm Plate)
• 05000306/LER-1917-002, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect  + (Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect)
• 05000333/LER-2011-001, Regarding Reactor Core Isolation Cooling System Inoperable Longer than Allowed by Technical Specifications  + (Regarding Reactor Core Isolation Cooling System Inoperable Longer than Allowed by Technical Specifications)
• 05000325/LER-2010-001, Regarding Reactor Core Isolation Cooling (RCIC) Manually Started to Maintain RPV Level Following Pre-planned Scram  + (Regarding Reactor Core Isolation Cooling (RCIC) Manually Started to Maintain RPV Level Following Pre-planned Scram)
• 05000397/LER-2004-008, Regarding Reactor Core Isolation Cooling Isolation Due to Inadvertent Closure of Containment Isolation Valve  + (Regarding Reactor Core Isolation Cooling Isolation Due to Inadvertent Closure of Containment Isolation Valve)
• 05000410/LER-2013-001, Regarding Reactor Core Isolation Cooling System Isolation Due to a Temperature Switch Unit Failure  + (Regarding Reactor Core Isolation Cooling System Isolation Due to a Temperature Switch Unit Failure)
• 05000373/LER-2017-001, Regarding Reactor Core Isolation Cooling System Inoperable Longer than Allowed by the Technical Specifications Due to Low Suction Pressure Trips  + (Regarding Reactor Core Isolation Cooling System Inoperable Longer than Allowed by the Technical Specifications Due to Low Suction Pressure Trips)
• 05000397/LER-2003-009, Regarding Reactor Core Isolation Cooling Rendered Inoperable Due to a 250 Vdc Battery Cell Not Meeting TS Requirements  + (Regarding Reactor Core Isolation Cooling Rendered Inoperable Due to a 250 Vdc Battery Cell Not Meeting TS Requirements)
• 05000416/LER-2017-009, Regarding Reactor Core Isolation Cooling System Inoperability Due to Lockout Circuit Settings  + (Regarding Reactor Core Isolation Cooling System Inoperability Due to Lockout Circuit Settings)
• 05000341/LER-2013-002, Regarding Reactor Core Isolation Cooling Isolation Instrumentation Misconfigured Wiring  + (Regarding Reactor Core Isolation Cooling Isolation Instrumentation Misconfigured Wiring)
• 05000249/LER-1975-005, Regarding Reactor Feed Pump 3C Pump Casing Vent Line Weld Break  + (Regarding Reactor Feed Pump 3C Pump Casing Vent Line Weld Break)
• 05000529/LER-2005-001, Regarding Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component  + (Regarding Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component)

• 05000388/LER-2005-003, Regarding Reactor Manual Scram Due to Loss of Main Transformer Cooling  + (Regarding Reactor Manual Scram Due to Loss of Main Transformer Cooling)

• 05000354/LER-2009-001, Regarding Reactor Manual Scram Due to Turbine Runback  + (Regarding Reactor Manual Scram Due to Turbine Runback)
• 05000397/LER-2004-006, Regarding Reactor Manual Scram During Plant Startup Due to High Water Level in the Pumped Drain Tank, and LER 04-006-00 Regarding Reactor Manual Scram During Reactor Startup Due to Improper Restoration of  + (Regarding Reactor Manual Scram During Plant Startup Due to High Water Level in the Pumped Drain Tank, and LER 04-006-00 Regarding Reactor Manual Scram During Reactor Startup Due to Improper Restoration of)
• 05000285/LER-2014-002, Regarding Reactor Manual Trip Due to Control Rod Misalignment  + (Regarding Reactor Manual Trip Due to Control Rod Misalignment)
• 05000483/LER-2008-008, Regarding Reactor Manually Tripped Due to B Condensate Pump Tripping Due to a Motor Ground Fault  + (Regarding Reactor Manually Tripped Due to B Condensate Pump Tripping Due to a Motor Ground Fault)
• 05000483/LER-2008-005, Regarding Reactor Manually Tripped Due to B Main Feed Pump Tripping on Low Lube Oil Pressure  + (Regarding Reactor Manually Tripped Due to B Main Feed Pump Tripping on Low Lube Oil Pressure)
• 05000414/LER-2010-001, Regarding Reactor Mode Change with Limiting Condition for Operation 3.6.6 Not Met in Violation of Limiting Condition for Operation 3.0.4  + (Regarding Reactor Mode Change with Limiting Condition for Operation 3.6.6 Not Met in Violation of Limiting Condition for Operation 3.0.4)
• 05000353/LER-1917-007, Regarding Reactor Mode Switch Change During RCIC Testing  + (Regarding Reactor Mode Switch Change During RCIC Testing)
• 05000278/LER-1917-001, Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line  + (Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line)
• 05000373/LER-2013-004, Regarding Reactor Pressure Exceeded 150 Psig with Reactor Core Isolation Cooling Inoperable  + (Regarding Reactor Pressure Exceeded 150 Psig with Reactor Core Isolation Cooling Inoperable)
• NL-11-0771, Regarding Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Nondestructive Examination Results -Spring 2011 Outage (2R21)  + (Regarding Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Nondestructive Examination Results -Spring 2011 Outage (2R21))
• 05000455/LER-2014-004, Regarding Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Attributed to Primary Water Stress Corrosion Cracking  + (Regarding Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Attributed to Primary Water Stress Corrosion Cracking)
• 05000456/LER-2012-002, Regarding Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Attributed to Primary Water Stress Corrosion Cracking  + (Regarding Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Attributed to Primary Water Stress Corrosion Cracking)
• 05000287/LER-2001-001-01, Regarding Reactor Pressure Vessel Head Leakage Due to Stress Corrosion Cracks Found in Nine Control Rod Drive Nozzle Penetrations  + (Regarding Reactor Pressure Vessel Head Leakage Due to Stress Corrosion Cracks Found in Nine Control Rod Drive Nozzle Penetrations)
• 05000400/LER-2013-003, Regarding Reactor Pressure Vessel Head Penetration Nozzle 37 Indication Attributed to Primary Water Stress Corrosion Cracking  + (Regarding Reactor Pressure Vessel Head Penetration Nozzle 37 Indication Attributed to Primary Water Stress Corrosion Cracking)
• 05000400/LER-2013-001, Regarding Reactor Pressure Vessel Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking  + (Regarding Reactor Pressure Vessel Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking)
• 05000397/LER-2015-005, Regarding Reactor Pressure Vessel Level Indication Switch Failures  + (Regarding Reactor Pressure Vessel Level Indication Switch Failures)
• 05000416/LER-2013-005, Regarding Reactor Pressure Vessel Pressure Less than 0 Psig During Six Plant Startups Resulting in a Violation of Technical Specification 3.4.11, RCS Pressure and Temperature (Pff) Limits  + (Regarding Reactor Pressure Vessel Pressure Less than 0 Psig During Six Plant Startups Resulting in a Violation of Technical Specification 3.4.11, RCS Pressure and Temperature (Pff) Limits)
• 05000333/LER-2008-002, Regarding Reactor Pressure Vessel Recirculation Inlet Nozzle Axial Flaw Indication Discovered During Refueling Outage Consistent with Inter-Granular Stress Corrosion Cracking  + (Regarding Reactor Pressure Vessel Recirculation Inlet Nozzle Axial Flaw Indication Discovered During Refueling Outage Consistent with Inter-Granular Stress Corrosion Cracking)
• 05000374/LER-2004-001, Regarding Reactor Protection Bus B Trip and Inoperable Automatic Depressurization Valves Due to Equipment Failure  + (Regarding Reactor Protection Bus B Trip and Inoperable Automatic Depressurization Valves Due to Equipment Failure)
• 05000219/LER-2013-005, Regarding Reactor Protection System (RPS) Actuation with the Reactor in Hot Shutdown  + (Regarding Reactor Protection System (RPS) Actuation with the Reactor in Hot Shutdown)
• 05000255/LER-1917-002, Regarding Reactor Protection System Actuation While the Reactor Was Shutdown  + (Regarding Reactor Protection System Actuation While the Reactor Was Shutdown)
• 05000354/LER-2016-005, Regarding Reactor Protection System Actuation While the Reactor Was Shutdown  + (Regarding Reactor Protection System Actuation While the Reactor Was Shutdown)
• 05000416/LER-2013-001, Regarding Reactor Protection System Actuation Due to a Main Turbine Generator Trip  + (Regarding Reactor Protection System Actuation Due to a Main Turbine Generator Trip)
• 05000416/LER-2012-008, Regarding Reactor Protection System Actuation Due to a Main Turbine Generator Trip  + (Regarding Reactor Protection System Actuation Due to a Main Turbine Generator Trip)
• 05000287/LER-1917-001, Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout  + (Regarding Reactor Protection System Actuation - Reactor Trip Due to Turbine Trip from Generator Lockout)