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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
- 05000237/LER-2013-002, Movement of Control Rods with Control Rod Block Monitor Inoperable +
- 05000237/LER-2013-007, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously +
- 05000247/LER-2013-004, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Essential Service Water (SW) Header as a Result of Pin Hole Leaks in Code Class 3 SW Piping +
- 05000250/LER-2013-004, Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position +
- 05000250/LER-2013-005, Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves +
- 05000250/LER-2013-006, Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps +
- 05000255/LER-2013-001, Regarding Technical Specification Required Shutdown Due to a Component Cooling Water System Leak +
- 05000255/LER-2013-003, Regarding Both Control Room Ventilation Filtration Trains Declared Inoperable +
- 05000261/LER-2013-003, Regarding Reactor Trip on 4KV Bus Undervoltage During Load Transfer +
- 05000263/LER-2013-001, E SRV Low-Low Set Tailpipe Dp Root Valve Found Closed +
- 05000266/LER-2013-002, Regarding Condition Prohibited by Technical Specifications +
- 05000282/LER-2013-001, Regarding Control Room Envelope Inoperable +
- 05000286/LER-2013-002, Regarding Safety System Functional Failure and Common Cause Inoperability of the Emergency Core Cooling System Due to Violation of Containment Sump Debris Barrier Integrity +
- 05000293/LER-2013-003, Regarding Loss of Off-Site Power Events Due to Winter Storm Nemo +
- 05000293/LER-2013-008, Manual Scram - Reactor Feed Pump Trip +
- 05000327/LER-2013-003, Regarding Limiting Conditions for Operation Exceeded for Emergency Core Cooling System +
- 05000328/LER-2013-001, Manual Reactor Trip Due to Loss of Hotwell Level +
- 05000333/LER-2013-006, Regarding Loss of HPCI Safety Function Due to Failure of B CST Level Switches +
- 05000336/LER-2013-002, Regarding Turbine Driven Auxiliary Feedwater Pump HELB Door Left Open During Surveillance Test +
- 05000339/LER-2013-001, Regarding Manual Reactor Trip Due to Increased Vibrations on Main Turbine/Generator Bearing Number 9 +
- 05000339/LER-2013-002, Regarding Manual Reactor Trip Due to Closure of 2-FW-MOV-250C and Auto-Start of 2-FW-P-1B +
- 05000346/LER-2013-002, Regarding Leak from Reactor Coolant Pump Seal Piping Socket Weld Due to High Cycle Fatigue +
- 05000348/LER-2013-001, Unit 1, Automatic Reactor Trip and B-Train Loss of Off-Site Power Caused by the Failure of a Startup Transformer Lightning Arrester +
- 05000348/LER-2013-002, For Joseph M. Farley Nuclear Plant, Unit 1, Regarding 1B Emergency Diesel Generator in a Condition Prohibited by Technical Specifications Due to an Unreliable Mechanism Operated Cell Switch +
- 05000352/LER-2013-001, Regarding High Pressure Coolant Injection System Pressure Switch Lubricating Oil Leak +
- 05000353/LER-2013-001, Regarding Valid Manual Actuation of the Reactor Protection System During Refuel Outage Testing +
- 05000354/LER-2013-005, Regarding Low-Low Set Safety/Relief Valve Pilot Solenoid Operated Valve Failed As-Found Testing +
- 05000366/LER-2013-002, Regarding Performance of Operations with Potential for Draining the Reactor Vessel (OPDRV) Without Operable Secondary Containment +
- 05000368/LER-2013-002 +
- 05000369/LER-2013-002, Regarding Inoperable Auxiliary Feedwater Components Resulting in Technical Specification Prohibited Operation or Condition +
- 05000373/LER-2013-007, Regarding Secondary Containment Inoperable Due to Interlock Doors Open +
- 05000382/LER-2013-004, Regarding Tech Spec Violation During Operation in Lower Mode with Reduced Channels of Excore Nuclear Instrumentation +
- 05000388/LER-2013-004, Regarding RHR Pump Room Flooding +
- 05000389/LER-2013-004, Regarding Manual Trip Following Spurious Closure of Main Feedwater Isolation Valve (Mfiv) and Lowering of Steam Generator Levels +
- 05000390/LER-2013-002, Regarding Two Trains of Emergency Gas Treatment System Inoperable +
- 05000400/LER-2013-002, Regarding Main Steam Safety Valve Setpoint Drift +
- 05000410/LER-2013-003, Regarding Unanalyzed Condition Caused by Unfused Control Room DC Ammeters +
- 05000412/LER-2013-001, Gas Void in Emergency Core Cooling System Pump Suction Header Results in a Condition Prohibited by Technical Specifications +
- 05000413/LER-2013-001, 0 for Catawba Nuclear Station, Unit 1 and 2 Regarding Each Diesel Generator Was Determined to Be Unknowingly Inoperable During Its Monthly Surveillance Test Due to Technical Specification Surveillance Requirement 3.8.1.17 Not B +
- 05000443/LER-2013-001, Regarding Failure to Enter Technical Specification Following Discovery of SW Leak +
- 05000446/LER-2013-002, Regarding Unit 2 Reactor Trip Due to Relay Actuation +
- 05000456/LER-2013-002, Re Liquid Penetrant Indications in Embedded Flaw Repair of Control Rod Drive Mechanism Penetration 69 During Refueling Outage +
- 05000461/LER-2013-006, Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1 +
- 05000461/LER-2013-007, Regarding Failed to Enter Tech Spec Action for Exceeding Reactor Coolant Heatup Rate +
- 05000482/LER-2013-001, Regarding Broken Cylinder Head Stud Causes Inoperable Diesel Generator Longer than Technical Specification Completion Time +
- 05000483/LER-2013-001, Re Violation of Technical Specification 3.0.3 Due to Class 1E Electrical Equipment AC Unit Inoperability +
- 05000483/LER-2013-009, Regarding Appendix R Unanalyzed Condition - Direct Current Ammeter Circuits Without Overcurrent Protection +
- 05000498/LER-2013-003, Regarding Unanalyzed Condition - Direct Current Ammeter Circuits Without Overcurrent Protection +
- 05000528/LER-2013-001, Unanalyzed Condition Due to Spent Fuel Pool Criticality Analysis of Record Not Updated for Power Uprate +
- 05000528/LER-2013-002, Regarding Inoperable Systems Due to Defective Relays Reported Under Part 21 +