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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
- 05000482/LER-2017-002 +
- 05000458/LER-2017-008 +
- 05000446/LER-2017-002 +
- 05000440/LER-2017-001 +
- 05000416/LER-2017-001, Regarding High Pressure Core Spray Jockey Pump Trip +
- 05000391/LER-2017-006, Regarding Manual Reactor Trip in Response to Indication of Multiple Dropped Control Rods +
- 05000390/LER-2017-009 +
- 05000388/LER-2017-009 +
- 05000388/LER-2017-007 +
- 05000388/LER-2017-006 +
- 05000388/LER-2017-005 +
- 05000388/LER-2017-004 +
- 05000388/LER-2017-003 +
- 05000388/LER-2017-001 +
- 05000366/LER-2017-004 +
- 05000366/LER-2017-001 +
- 05000331/LER-2017-001, Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage +
- 05000325/LER-2017-004 +
- 05000325/LER-2017-002 +
- 05000325/LER-2017-001 +
- 05000259/LER-2017-001 +
- 05000254/LER-2017-001, Regarding Secondary Containment Interlock Doors Opened Simultaneously +
- 05000387/LER-2017-010-02, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches +
- 05000528/LER-2017-002, Emergency Diesel Generator Inoperable Due to Fuel Oil Transfer Pump Testing +
- 05000416/LER-2017-003-02, Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown +
- 05000353/LER-2017-004-01, Degraded Condition Due to RPV Instrument Nozzle Leakage +
- 05000416/LER-2017-008, Failure to Perform/Document Diesel Generator Common Mode Failure Evaluations +
- 05000387/LER-2017-008, Core Spray Inoperable Due to Not Meeting Seismic Requirements as a Result of a Human Performance Error +
- 05000333/LER-2017-004-01, Regarding Safety Relief Valves Out of Tolerance +
- 05000416/LER-2017-009, Regarding Reactor Core Isolation Cooling System Inoperability Due to Lockout Circuit Settings +
- 05000353/LER-2017-008-01, Eog Inoperable for Greater than 30 Days Resulting in Condition Prohibited by TS +
- 05000315/LER-2017-001, For Donald C. Cook Unit 1 Regarding Unit 1 Turbine Driven Auxiliary Feedwater Pump Inoperable Longer than Allowed by Technical Specifications +
- 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage +
- 05000390/LER-2017-016, Regarding System Actuations Due to Opening of Feeder Breaker to the 1B-B 6.9 Kv Shutdown Board +
- 05000387/LER-2017-009-01, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan +
- 05000219/LER-2017-004-01, 1 for Oyster Creek Nuclear Generating Station Regarding Reactor Protection System Channel Disabled During Test Box Use +
- 05000440/LER-2017-007, For Perry Nuclear Power Plant Regarding High Pressure Core Spray Inoperability Due to System Leak +
- 05000458/LER-2017-002, Regarding Loss of Safety Function of Onsite Electrical Distribution Due to Malfunction of Control Building HVAC System +
- 05000387/LER-2017-004, Regarding Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors +
- 05000416/LER-2017-002, Regarding Loss of Secondary Containment and Inoperability of the Standby Gas Treatment System +
- 05000461/LER-2017-001, Regarding Failure of the 138 Kv Offsite Power Source Results in a Loss of Secondary Containment Vacuum +
- 05000260/LER-2017-002, Regarding Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications +
- 05000454/LER-2017-001, Regarding Volumetric and Surface Examinations of Reactor Pressure Vessel Head Penetration Nozzles Identify Indications Attributed to Primary Water Stress Corrosion Cracking and Minor Subsurface Void Enlargement from +
- 05000374/LER-2017-004, Regarding Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test +
- 05000334/LER-2017-001, Regarding Inadequate Tornado Missile Protection Identified Due to Nonconforming Design Conditions +
- 05000260/LER-2017-001, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse +
- 05000373/LER-2017-003, Regarding Automatic Reactor Scram Due to Main Generator Trip on Differential Current During Back-Feed Operations +
- 05000387/LER-2017-002, Regarding Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors +
- 05000373/LER-2017-004, Regarding Secondary Containment Inoperable Due to Interlock Doors Open +
- 05000387/LER-2017-003, Regarding Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors +