Search by property
Jump to navigation
Jump to search
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
- 05000461/LER-1917-010, Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram +
- 05000289/LER-1917-004, Regarding Items Nonconforming to Design for Tornado Missile Protection +
- 05000416/LER-1917-007, Regarding Engineered Safety Feature System Actuations Due to the Loss of Engineered Safety Features Transformer 11 +
- 05000446/LER-1917-003, Regarding Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps +
- 05000293/LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years +
- 05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches +
- 05000446/LER-1917-001, Regarding Auxiliary Feedwater System Actuation During Unit 2 Turbine Trip +
- 05000391/LER-1917-005, Regarding Unplanned Emergency Core Cooling System Injection Into the Reactor Coolant System Due to Personnel Error +
- 05000498/LER-1917-002, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil +
- 05000333/LER-1917-004, Regarding Safety Relief Valves Out of Tolerance +
- 05000263/LER-1917-006, Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture +
- 05000364/LER-1917-005, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector +
- 05000306/LER-1917-003, Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4 +
- 05000219/LER-1917-005, Regarding Failure of the Emergency Diesel Generator 2 During Surveillance Testing Due to a Broken Electrical Connector +
- 05000390/LER-1917-015, Regarding Failure to Enter Limiting Condition of Operation Action Statement Results in a Condition Prohibited by Technical Specifications +
- 05000272/LER-1917-001, Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications +
- 05000334/LER-1917-003, Regarding Reactor Trip Due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System +
- 05000461/LER-1917-009, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 Kv Offsite Source +
- 05000254/LER-1917-004, For Quad Cities Nuclear Power Station, Unit 1 Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid +
- 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits +
- 05000286/LER-1917-004, Regarding Reactor Trip Due to Main Generator Loss of Field +
- 05000395/LER-1917-005, V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip +
- 05000483/LER-1917-003, Regarding Violation of Technical Specification 3.6.3, Containment Isolation Check Valve Found in Open Position +
- 05000296/LER-1917-002, Regarding 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses +
- 05000278/LER-1917-001, Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line +
- 05000364/LER-1917-004, Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications +
- 05000364/LER-1917-003, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits +
- 05000390/LER-1917-014, Regarding Main Control Room Boundary Door Left Open Leading to a Loss of Safety Function +
- 05000364/LER-1917-002, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits +
- 05000389/LER-1917-004, Regarding Automatic Reactor Trip Due to Turbine Control System Malfunction +
- 05000389/LER-1917-003, Regarding Improper System Realignment Resulted in Loss of Steam Driven Auxiliary Feedwater Pump Flow Indication +
- 05000395/LER-1917-006, Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor +
- 05000261/LER-1917-002, Regarding Plant Vital Area Security Vulnerability Discovered Without Compensatory Security Measures +
- 05000266/LER-1917-003, Regarding Degraded Condition +
- 05000266/LER-1917-002, Regarding Operation or Condition Prohibited by Technical Specifications +
- 05000410/LER-1917-002, Regarding Secondary Containment Inoperable Due to Wind Conditions +
- 05000306/LER-1917-002, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect +
- 05000353/LER-1917-008, Regarding Eog Inoperable for Greater than 30 Days Resulting in Condition Prohibited by Technical Specifications +
- 05000387/LER-1917-006, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan +
- 05000352/LER-1917-004, Regarding Core Spray Pump Failed to Start Resulting in Condition Prohibited by TS +
- 05000440/LER-1917-006, Regarding Loss of Safety Function Due to the Inoperability of Both Trains of Motor Control Center Ventilation +
- 05000397/LER-1917-007, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure +
- 05000306/LER-1917-001, Regarding 23 Containment Fan Coil Unit Operability +
- 05000346/LER-1917-002, For Davis-Besse Nuclear Power Station, Unit 1, Regarding Auxiliary Feed Water Pump Turbine Bearing Damaged Due to Improperly Marked Lubricating Oil Sight Glass +
- 05000353/LER-1917-007, Regarding Reactor Mode Switch Change During RCIC Testing +
- 05000293/LER-1917-012, Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit +
- 05000458/LER-1917-009, Regarding Potential Loss of Safety Function of Secondary Containment Due to Unsecured Personnel Door +
- 05000220/LER-1917-003, Regarding Automatic Reactor Scram Due to Reactor Vessel Low Water Level +
- 05000425/LER-1917-002, Regarding Valid Undervoltage Condition Results in Automatic Actuation of a Safety System +
- 05000254/LER-1917-003, Regarding Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue +