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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
- 05000387/LER-2018-005-02, (SSES) Unit 1 Re Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches +
- 05000247/LER-2018-003-01, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap +
- 05000387/LER-2018-005-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches +
- 05000254/LER-2018-005-01, Loss of Safety Bus and Automatic Actuation of a Safety System During Undervoltage Relay Surveillance +
- 05000237/LER-2018-001, Cancellation: LER 2018-001-00 for Dresden Nuclear Power Station, Units 2 and 3, Non-Conformances to Design for Tornado Missile Protection +
- 05000446/LER-2018-001-01, For Comanche Peak Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to Turbine Trip +
- 05000313/LER-2018-004-01, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus +
- 05000416/LER-2018-001-01, Grand Gulf. Nuclear Station, Unit 1, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes +
- 05000416/LER-2018-009-01, Reactor Manual Shutdown Due to Feedwater Level Control Changes +
- 05000255/LER-2018-003-01, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations +
- 05000446/LER-2018-002-01, Automatic Actuation of Auxiliary Feedwater System +
- 05000416/LER-2018-010-01, Reactor Manual Scram Due to Main Steam Bypass Stop and Control Valve Drifting Open +
- 05000461/LER-2018-005-02, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux +
- 05000265/LER-2018-001-01, Two Main Steam Isolation Valves (Msivs) Closure Times Exceeded +
- 05000323/LER-2018-001-01, Automatic Reactor Trip of Unit 2 Following a Load Rejection +
- 05000259/LER-2018-002-01, Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition +
- 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications +
- 05000461/LER-2018-005-01, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux +
- 05000254/LER-2018-004-01, Reactor Scram Due to Turbine-Generator Load Reject +
- 05000277/LER-2018-002-01, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications +
- 07200041/LER-2018-002, 0 for San Onofre Nuclear Generating Station ISFSI Re Spent Nuclear Fuel Transport Conveyance Vehicle Operated Outside Obstacle Clearance Limit +
- 05000346/LER-2018-001, Borated Water Storage Tank Level Transmitter Out of Tolerance Due to Reaching End of Expected Life +
- 05000263/LER-2018-002, C Outboard Main Steam Line Isolation Valve Delayed Closure Due to Foreign Material in the Air Valve +
- 05000313/LER-2018-004, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus +
- 05000317/LER-2018-001-01, Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Damaged Internals +
- 05000259/LER-2018-007, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints +
- 05000461/LER-2018-003-01, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability +
- 05000390/LER-2018-006, Containment Air Return Fan Inoperable for a Time Period Longer than Allowed by Technical Specifications Due to an Inadequate Post Maintenance Test +
- 05000263/LER-2018-001, Cancellation of LER 2018-001-00 for Monticello Re Non-Fully Closed Check Valves Resulted in a Potential Pathway Outside of Secondary Containment and Follow-up to Interim Part 21 Report of a Deviation or Failure to Comply +
- 05000341/LER-2018-007, Reactor Building to Suppression Chamber Vacuum Breaker Condition Prohibited by Technical Specifications +
- 05000416/LER-2018-010, Reactor Manual Scram Due to Main Turbine Bypass Valve Drifting Open +
- 05000333/LER-2018-001, Secondary Containment Differential Pressure Exceeded the Technical Specification Surveillance Requirement +
- 05000446/LER-2018-002, Automatic Actuation of Auxiliary Feedwater System +
- 05000397/LER-2018-001-01, Automatic Reactor Scram Due to Main Transformer Trip +
- 05000323/LER-2018-001, Automatic Reactor Trip of Unit 2 Following a Load Rejection +
- 05000336/LER-2018-001, Regarding Loss of Both Trains of Control Room Emergency Ventilation Resulting in the Loss of Safety Function +
- 05000483/LER-2018-006, Inoperability of SSCs Due to Improper Environmental Qualification Classification +
- 05000280/LER-2018-003, Regarding Auto-Start of Emergency Diesel Generators Due to Pilot Wire Lockout on C Reserve Station Service Transformer +
- 05000259/LER-2018-004-01, Hiqh Pressure Coolant Injection Declared Inoperable Due to Steam Supply Valve Isolation +
- 05000327/LER-2018-002, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable +
- 05000458/LER-2018-010, Reactor Scram Due to Turbine Control Valve Failure +
- 05000458/LER-2018-011, For River Bend Station, Unit 1, Condition Prohibited by Technical Specifications Due to Inadequate Design Change of Under Voltage Relay Trip Set Point Range +
- 05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown +
- 05000261/LER-2018-001, Valid Actuation of Emergency Diesel Generator +
- 05000255/LER-2018-003, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations +
- 05000458/LER-2018-009, Inadvertent Initiation of Reactor Core Isolation Cooling Due to Personnel Error +
- 05000269/LER-2018-002, Loss. of Condenser Vacuum Results in a Main Turbine Trip and a Manual Reactor Trip +
- 05000335/LER-2018-001, Feedwater Heater Level Control Malfunctions Resulted in Lowering Steam Generator Water Level and Manual Reactor Trip +
- 05000530/LER-2018-001-01, Reactor Trip on Low Steam Generator Level +
- 05000247/LER-2018-003, For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap +