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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-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip +
- 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater +
- 05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate +
- 05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode Change +
- 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications +
- 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum +
- 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function +
- 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications +
- 05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String +
- 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications +
- 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications +
- 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water +
- 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer +
- 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables +
- 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram +
- 05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam +
- 05000391/LER-2023-003-01, Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control +
- 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications +
- 05000461/LER-2023-002, Reactor Core Isolation Cooling System Inoperable Prior to Mode Change +
- 05000270/LER-2023-001, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee +
- 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function +
- 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground +
- 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram +
- 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement +
- 05000458/LER-2023-006, Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard +
- 05000423/LER-2023-005, Oil Leakage from C RSS Pump Motor Challenged Meeting Its Mission Time Resulting in a Condition Prohibited by Technical Specifications +
- 05000498/LER-2023-004, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water +
- 05000259/LER-2023-003, Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage +
- 05000528/LER-2023-003, Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start +
- 05000528/LER-2023-001-02, Reactor Trip Following a Main Turbine Trip +
- 05000499/LER-2023-002, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus +
- 05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation +
- 05000458/LER-2023-005, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String +
- 05000499/LER-2023-001, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function +
- 05000339/LER-2023-001, Reactor Coolant Pressure Boundary Leak Due to Poor Weld Workmanship +
- 05000498/LER-2023-003, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function +
- 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum +
- 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing +
- 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 +
- 05000458/LER-2023-004, Drywall Post Accident Radiation Monitor Inoperable Due to Unrecognized Surveillance Failure +
- 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications +
- 05000443/LER-2023-005, Auxiliary Feedwater System Inoperable +
- 05000423/LER-2023-004, For Millstone Power Station, Unit 3 Regarding Reactor Coolant System Pressure Isolation Valves Operational Leakage Exceeded the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications +
- 05000278/LER-2023-002, Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit +
- 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing +
- 05000315/LER-2023-002, Failure of Unit 1 West Auxiliary Feedwater Pump to Restart During Load Sequencer Testing +
- 05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level +
- 05000423/LER-2023-003, RCS Temperature Detector Exceeded Time Response Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications +
- 05000528/LER-2023-002, Reactor Coolant System Degraded Pressure Boundary +
- 05000348/LER-2023-003, Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak +