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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
- 05000318/LER-2022-001, Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure +
- 05000458/LER-2022-004-01, High Pressure Core Spray Inoperable Due to Transformer Failure +
- 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator +
- 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low +
- 05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking +
- 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure +
- 05000483/LER-2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications +
- 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability +
- 05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level +
- 05000374/LER-2022-003-02, Manual Scram Due to Lsophase Bus Duct Fire Followed by 2A RPS Normal Power Supply Trip +
- 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open +
- 05000315/LER-2022-003-01, Automatic Trip on Losss of Flow Due to Reactor Coolant Pump Trip +
- 05000382/LER-2022-001-02, Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors +
- 05000346/LER-2022-002, Strong Winds Result in Ultimate Heat Sink Low Water Level +
- 05000416/LER-2022-003, Manual Reactor Scram Due to Trip of the a Reactor Feedwater Pump +
- 05000298/LER-2022-004, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open +
- 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation +
- 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line +
- 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus +
- 05000298/LER-2022-003, Actuation of Reactor Protection System Initiates a Full Reactor Scram +
- 05000316/LER-2022-001, Automatic Reactor Trip Due to Steam Generator High-High Level +
- 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors +
- 05000373/LER-2022-004, Both Trains of Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Compressor Trips +
- 05000382/LER-2022-005, Engineered Safety Features Actuation System Relay Failure Results in Reactor Trip and Emergency Feedwater Actuation +
- 05000410/LER-2022-002-01, Reactor Protection System Actuation While Shutdown +
- 05000414/LER-2022-003, Manual Reactor Trip and Auxiliary Feedwater System Actuation +
- 05000373/LER-2022-003-02, Supplement to Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures +
- 05000269/LER-2022-001, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary +
- 05000323/LER-2022-001, Reactor Coolant System Pressure Boundary Degradation +
- 05000483/LER-2022-003, Submittal of Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications +
- 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability +
- 05000400/LER-2022-007, Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus +
- 05000296/LER-2022-002, Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate +
- 05200025/LER-2022-002, Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes +
- 05000400/LER-2022-008, Automatic Actuation of Auxiliary Feedwater System +
- 05000416/LER-2022-002, Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage +
- 05000298/LER-2022-002, Manual Core Spray Injection to Restore Skimmer Surge Tank Level +
- 05000387/LER-2022-003, Inoperable 13.8kV Startup Transformer Due to Misaligned Load Tap Charger Local/Remote Control Switch +
- 05200025/LER-2022-003, Unborated Water Flowpath Not Secured Per Technical Specification 3.9.2 Due to Inadequate Procedure Change +
- 05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault +
- 05000277/LER-2022-002, Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Degraded +
- 05000327/LER-2022-002, Turbine Trip Function Inoperable Due to Slow to Close Turbine Throttle Valve +
- 05000352/LER-2022-001, Regarding HPCI Inoperable Due to Inadvertent Isolation Signal +
- 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator +
- 05000414/LER-2022-002, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination +
- 05000387/LER-2022-002-01, Automatic Reactor Scram Due to Reactor Protection System Actuation on High Reactor Vessel Pressure Signal Following Inadvertent Closure of Inboard Main Steam Isolation Valve +
- 05200025/LER-2022-001, Automatic Reactor Trip Signal Due to Inadequate Procedure Guidance Causing Incorrect Opening of Division B DC Supply Breaker +
- 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low +
- 05000456/LER-2022-001, Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation +
- 05000400/LER-2022-005-01, Manual Reactor Trip Due to B Condensate Pump Motor Failure +