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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
- 05000530/LER-2010-002, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Obstruction +
- 05000530/LER-2010-001 +
- 05000528/LER-2010-001, For Palo Verde, Unit 1 Re Automatic Reactor Trip Due to a Loss of a Non-Class 13.8 Kv (Calvert) Bus +
- 05000483/LER-2010-003, Regarding Safety System Actuation After Loss of a Switchyard Bus +
- 05000482/LER-2010-012, Regarding Reactor Trip Due to Operators Inability to Control Steam Generator Level Oscillations at Low Power +
- 05000482/LER-2010-011 +
- 05000482/LER-2010-005, Regarding Reactor Trip Due to Low Steam Generator Level from Trip of Main Feedwater Pump +
- 05000482/LER-2010-004, Regarding Positive Reactivity Addition in Mode 2 with One Source Range Neutron Flux Channel Inoperable +
- 05000482/LER-2010-002, Regarding Turbine Trip Function of Reactor Trip P-4 Interlock Defeated During Entry Into and in Mode 3 +
- 05000461/LER-2010-004, For Clinton Power Station, Unit 1, Regarding OPDRV Requirements Not Met During Control Rod Drive Mechanism Replacements +
- 05000458/LER-2010-003, Regarding High Pressure Core Spray System Declared Inoperable Due to Failure of Pump Room Cooler +
- 05000456/LER-2010-007, Regarding Potential Loss of Residual Heat Removal System Safety Function in Mode 4 When Aligned for Shutdown Cooling Due to Potential for Flashing or Voiding of Coolant During a Shutdown Loss of Coolant Accident +
- 05000456/LER-2010-005, Incorrect Methodology Used in Calculations in 1999 Resulted in Non-Conservative Control Room Outside Air Intake Monitor Alarm Setpoints +
- 05000456/LER-2010-003, Regarding Through-weld Leak of the Line from the 1B Seal Injection Filter to the Vent Valve +
- 05000446/LER-2010-001 +
- 05000445/LER-2010-001, Loss of XST1 Due to Breakers 7030 and 7040 Opening as a Result of a B-Phase to Ground Fault +
- 05000400/LER-2010-001, Unit 1 Regarding Clearance Error Results in Required Equipment Becoming Inoperable +
- 05000389/LER-2010-002, Regarding Manual Reactor Trip Due to Moisture Separator Re-heater Safety Valve Lift +
- 05000389/LER-2010-001, Regarding Control Room Habitability Impacted by General Atomics Model RM-80 Radiation Monitoring System Firmware Anomaly +
- 05000387/LER-2010-001, Regarding Secondary Containment Bypass Leakage Exceeded +
- 05000219/LER-2010-001, Regarding Automatic Start of Emergency Diesel Generator Due to Unexpected Trip of the Id Bus Normal Feed Beaker +
- 05000313/LER-2010-001, Regarding Main Steam Safety Valves Not within Limits Due to Seat Bonding and Transient-Induced Drift Resulting in a Condition Prohibited by Technical Specifications +
- 05000311/LER-2010-003 +
- 05000301/LER-2010-001, Regarding Manual Reactor Trip Following Automatic Turbine Trip Due to Generator Lockout +
- 05000293/LER-2010-002, For Pilgrim Nuclear Power Station, Regarding Standby Gas Treatment Declared Inoperable After Discovery of Open Demister Door +
- 05000286/LER-2010-002, Regarding Manual Reactor Trip Due to a Cooling Water Leak in the Main Generator Exciter Air Cooler +
- 05000272/LER-2010-005 +
- 05000272/LER-2010-001, Regarding Automatic Start of the 1C Emergency Diesel Generator (EDG) +
- 05000263/LER-2010-004, Regarding Secondary Containment Briefly Inoperable Due to Simultaneous Opening of Airlock Doors +
- 05000261/LER-2010-009 +
- 05000261/LER-2010-008 +
- 05000260/LER-2010-003, Regarding Reactor Scram Due to Closure of the Main Steam Isolation Valves and Subsequent Invalid RPS Scram from the Intermediate Range Monitoring System +
- 05000259/LER-2010-002, Drywell Pressure Instrument Channel Inoperability Due to Improper Tubing Slope +
- 05000250/LER-2010-006, Regarding Manual Reactor Trip and Auxiliary Feedwater Actuation in Response to Loss of Circulating Water Pump +
- 05000247/LER-2010-005, For Indian Point, Unit 2, Regarding Technical Specification Prohibited Condition Due to an Inoperable Control Room Ventilation System Caused by a Closed Normally Open Damper +
- 05000341/LER-2010-004, High Pressure Coolant Injection System Inoperable Due to Inoperable Minimum Flow Valve +
- 05000338/LER-2010-004, For North Anna Power Station, Unit 1, Regarding Manual Reactor Trip Due to Malfunction of the Rod Control In-Hold-Out Selector Switch +
- 05000338/LER-2010-001, Regarding Non-Functional Fire Barrier Penetrations Containing Aluminum Conduit Due to Configuration +
- 05000336/LER-2010-003 +
- 05000336/LER-2010-001, For Millstone Power Station, Unit 2, Regarding Reactor Trip +
- 05000331/LER-2010-006, Regarding Standby Liquid Control Test Tank Seismic Analysis +
- 05000327/LER-2010-003, Regarding Manual Reactor Trip as a Result of a Fire in the Main Generator Neutral Bushing Bus Duct Housing +
- 05000323/LER-2010-002 +
- 05000323/LER-2010-001 +
- 05000321/LER-2010-002, Regarding Degraded Plant Service Water Cooling to Main Control Room Air Conditioner Results in Loss of Function +
- 05000318/LER-2010-002, For Calvert Cliffs, Unit 2, Regarding Reactor Coolant System Pressure Boundary Leakage in Valve Leakoff Line Weld +
- 05000316/LER-2010-002 +
- 05000316/LER-2010-001 +
- 05000387/LER-2010-004, Regarding D Outboard Main Steam Isolation Valve Leakage - 2010 +
- 05000285/LER-2010-003, Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable +