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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
- 05000529/LER-2007-004 +
- 05000529/LER-2007-002, Regarding Condition Prohibited by Technical Specification - CEA Insertion Limit Exceeded +
- 05000528/LER-2007-006 +
- 05000461/LER-2007-002, Regarding Improper Installation of Stanchions in Containment Pool Swell Zone +
- 05000456/LER-2007-003 +
- 05000423/LER-2007-003, Re Reactor Head Vent Valve Circuits Not Isolated from Control Room During Fire Scenario +
- 05000423/LER-2007-002, Regarding Loss of Offsite Power Caused by Transmission System Operator While Defueled +
- 05000416/LER-2007-003, Regarding Reactor Scram Due to Decreasing Reactor Vessel Water Level +
- 05000400/LER-2007-004 +
- 05000397/LER-2007-005, Regarding Inoperable Diesel Generator Due to Inadequate Procedure That Caused Potential Transformer Fuses to Clear During Shut Down of the Diesel +
- 05000369/LER-2007-003, Re Inoperable Source Range Neutron Flux Monitors During Mode 6 and Core Alterations +
- 05000369/LER-2007-001, Re Completion Time of Technical Specification 3.8.4 Condition a Was Exceeded on May 12, 2005 +
- 05000366/LER-2007-006, Regarding Corrosion Induced Bonding Results in Safety Relief Valve Lift Setpoint Drift +
- 05000366/LER-2007-005, Regarding High Pressure Coolant Injection System Inoperabe Due to Water Intursion Into the Oil System +
- 05000366/LER-2007-003, Re Excessive Leakage on Secondary Containment Bypass Valves Due to Foreign Material +
- 05000339/LER-2007-001, Regarding Damper Leak-by During Preacs Testing Results in Unanticipated Power Reduction +
- 05000321/LER-2007-001, Unit 1, Re High Pressure Coolant Injection Inoperable Due to Component Failures +
- 05000316/LER-2007-001-01, Regarding As-found Local Leak Rate Tests Not Performed +
- 05000315/LER-2007-002 +
- 05000315/LER-2007-001, Unit 1 Automatic Reactor Trip +
- 05000298/LER-2007-002, Re Technical Specification Prohibited Operation Due to Safety Relief Valve Test Failure +
- 05000293/LER-2007-004, Target Rock Relief Valves Test Pressure Exceeded Limit Due to Corrosion Bonding and Setpoint Variance +
- 05000293/LER-2007-003, Regarding Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation +
- 05000293/LER-2007-002, Emergency Diesel Generator Kilowatt (Kw) Power Oscillations +
- 05000285/LER-2007-005 +
- 05000275/LER-2007-003, Emergency Diesel Generator Actuation Due to a Transient Undervoltage Condition +
- 05000275/LER-2007-002, From Diablo Canyon, Unit 1, Manual Reactor Trip in Mode 3 During Control Rod Testing +
- 05000275/LER-2007-001, Re Emergency Diesel Generator Auto-Start on Loss of Offsite 230kV Startup Power +
- 05000272/LER-2007-002, Manual Reactor Trips Due to Degraded Condenser Heat Removal +
- 05000244/LER-2007-002, Regarding Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip +
- 05000237/LER-2007-003, Re Unit 2 High Pressure Coolant Injection System Declared Inoperable +
- 05000457/LER-2007-001, Unit 2 Manual Reactor Trip Due to High Condenser Backpressure Resulting from Circulating Water Pump Trips +
- 05000455/LER-2007-001, From Byron Station Unit 2, Re Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Due to an Initial Constructive Weld Defect Allowing the Initiation of Primary Water Stress Corrosion Crac +
- 05000440/LER-2007-006, Regarding Loss of Safety Function and Condition Prohibited by Technical Specifications Due to Annulus Exhaust Gas Treatment System Inoperability +
- 05000425/LER-2007-002 +
- 05000414/LER-2007-001, Regarding Failure to Comply with Action Statement in Technical Specification (TS) 3.3.1 for Loss of a Channel of the Solid State Protection System +
- 05000413/LER-2007-004 +
- 05000413/LER-2007-002 +
- 05000388/LER-2007-001, Regarding U2 Secondary Containment Bypass Leakage Exceeded +
- 05000361/LER-2007-005, For San Onofre, Unit 2 Regarding Loose Electrical Connection Results in Inoperable Pump Room Cooler +
- 05000354/LER-2007-003, Regarding Grab Samples Not Performed as Required by Technical Specification 3.3.7.1 +
- 05000348/LER-2007-001, From Joseph M. Farley Nuclear Plant - Unit 1, Re Technical Specification 3.8.1 Violation Due to Failure of Breaker/Mechanism-Operated Cell (MOC) Switch +
- 05000346/LER-2007-002, Regarding Decay Heat Removal Discharge Piping Void Due to Inadequate Procedure for Venting Following Maintenance +
- 05000346/LER-2007-001 +
- 05000335/LER-2007-003 +
- 05000331/LER-2007-009, Loss of Essential Bus Resulted in a Loss of Safety Function +
- 05000331/LER-2007-003, Re Linear Indications Found During UT Examination of Safe-End to Nozzle Welds +
- 05000325/LER-2007-002 +
- 05000325/LER-2007-001 +
- 05000318/LER-2007-001, Re Channel C Linear Range Nuclear Instrument Inoperable During Startup +