Search by property

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

• 05000416/LER-2010-002, For Grand Gulf, Control Room Air Conditioning Subsystem B Tripped on Low Oil Pressure While in the a Subsystem Was Inoperable for Maintenance Resulting in a Condition That Could Have Prevented the Fulfillment of the Mitigation  + (For Grand Gulf, Control Room Air Conditioning Subsystem B Tripped on Low Oil Pressure While in the a Subsystem Was Inoperable for Maintenance Resulting in a Condition That Could Have Prevented the Fulfillment of the Mitigation)
• 05000261/LER-2003-001, For H. B. Robinson Unit 2 Regarding Failure to Complete Technical Specifications Required Action within the Allowed Completion Time  + (For H. B. Robinson Unit 2 Regarding Failure to Complete Technical Specifications Required Action within the Allowed Completion Time)
• 05000261/LER-2010-002, For H. B. Robinson, Unit 2, Regarding Plant Trip Due to Electrical Fault  + (For H. B. Robinson, Unit 2, Regarding Plant Trip Due to Electrical Fault)
• 05000261/LER-2012-004, For H.B. Robinson Unit 2, Regarding Reactor Tripped Due to a Turbine Trip Caused by a Feedwater Isolation Signal from Steam Generator B High Level  + (For H.B. Robinson Unit 2, Regarding Reactor Tripped Due to a Turbine Trip Caused by a Feedwater Isolation Signal from Steam Generator B High Level)
• 05000261/LER-2010-001, For H.B. Robinson, Unit 2, Regarding Emergency Diesel Generator Inoperable in Excess of Technical Specifications Completion Time Due to Output Breaker Failure  + (For H.B. Robinson, Unit 2, Regarding Emergency Diesel Generator Inoperable in Excess of Technical Specifications Completion Time Due to Output Breaker Failure)
• 05000261/LER-2009-003, For H.B. Robinson, Unit 2, Regarding Manual Reactor Trip Due to Failure of a Steam Generator Level Module  + (For H.B. Robinson, Unit 2, Regarding Manual Reactor Trip Due to Failure of a Steam Generator Level Module)
• 05000400/LER-2010-005, For Harris Nuclear Plant, Unit 1 Regarding Emergency Core Cooling System (ECCS) Inoperable for Greater than Time Allowed by Technical Specifications  + (For Harris Nuclear Plant, Unit 1 Regarding Emergency Core Cooling System (ECCS) Inoperable for Greater than Time Allowed by Technical Specifications)
• 05000400/LER-2010-003, For Harris, Unit 1, Regarding Condition Prohibited by Technical Specifications When Non-Seismic System Was Aligned to Refueling Water Storage Tank  + (For Harris, Unit 1, Regarding Condition Prohibited by Technical Specifications When Non-Seismic System Was Aligned to Refueling Water Storage Tank)
• 05000354/LER-2010-003, For Hope Creek Generating Station, RHR Shutdown Cooling Suction Relief Valve Missed Surveillance  + (For Hope Creek Generating Station, RHR Shutdown Cooling Suction Relief Valve Missed Surveillance)
• 05000354/LER-2011-001, For Hope Creek Generating Station, Regarding HPCI Operation Credit in UFSAR Scenario Not Supported by Existing Documentation  + (For Hope Creek Generating Station, Regarding HPCI Operation Credit in UFSAR Scenario Not Supported by Existing Documentation)
• 05000354/LER-2007-005, For Hope Creek Lab Error Resulting in Inappropriate Access Authorization  + (For Hope Creek Lab Error Resulting in Inappropriate Access Authorization)
• 05000354/LER-2009-003, For Hope Creek, Regarding Traversing In-Core Probe (TIP) Containment Isolation Valves Found Open  + (For Hope Creek, Regarding Traversing In-Core Probe (TIP) Containment Isolation Valves Found Open)
• 05000247/LER-2009-004, For Indian Point 2, Regarding Loss of Single Train 23 Charging Pump Required for Remote Plant Shutdown from the Control Room Due to a Failure of a Pump Internal Check Valve  + (For Indian Point 2, Regarding Loss of Single Train 23 Charging Pump Required for Remote Plant Shutdown from the Control Room Due to a Failure of a Pump Internal Check Valve)
• 05000247/LER-2010-006, For Indian Point 2, Regarding Safety System Functional Failure Due to Inoperable Reactor Coolant Loop 21 and 22 Wide Range Hot Leg Temperature Indicators Credited for Remote Shutdown Per Technical Specification 3.3.4  + (For Indian Point 2, Regarding Safety System Functional Failure Due to Inoperable Reactor Coolant Loop 21 and 22 Wide Range Hot Leg Temperature Indicators Credited for Remote Shutdown Per Technical Specification 3.3.4)
• 05000247/LER-2010-002, For Indian Point 2, Regarding Technical Specification Prohibited Condition Caused by Two Main Steam Safety Valves Outside As-Found Lift Setpoint Test Acceptance Criteria  + (For Indian Point 2, Regarding Technical Specification Prohibited Condition Caused by Two Main Steam Safety Valves Outside As-Found Lift Setpoint Test Acceptance Criteria)
• 05000247/LER-2018-003, For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap  + (For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap)
• 05000247/LER-2010-008, For Indian Point Unit 2, Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Low-Low Level Alarms  + (For Indian Point Unit 2, Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Low-Low Level Alarms)
• 05000247/LER-2012-005, For Indian Point Unit 2, Regarding Technical Specification Prohibited Condition Caused by a Main Steam Safety Valve Outside Its As-Found Lift Setpoint Test Acceptance Criteria Due to Spring Skew/Spindle Wear  + (For Indian Point Unit 2, Regarding Technical Specification Prohibited Condition Caused by a Main Steam Safety Valve Outside Its As-Found Lift Setpoint Test Acceptance Criteria Due to Spring Skew/Spindle Wear)
• 05000247/LER-2012-004, For Indian Point Unit 2, Regarding Unanalyzed Condition and Safety System Functional Failure Due to Use of Rad Bypass Switch for Steam Generator Blowdown Isolation Valves Which Defeats Their Automatic Isolation for Analyzed Eve  + (For Indian Point Unit 2, Regarding Unanalyzed Condition and Safety System Functional Failure Due to Use of Rad Bypass Switch for Steam Generator Blowdown Isolation Valves Which Defeats Their Automatic Isolation for Analyzed Events)
• 05000286/LER-2003-003, For Indian Point Unit 3 Regarding Automatic Turbine Trip/Reactor Trip Due to Fault in 345kV Generator Output Breaker 3  + (For Indian Point Unit 3 Regarding Automatic Turbine Trip/Reactor Trip Due to Fault in 345kV Generator Output Breaker 3)
• 05000286/LER-2011-003, For Indian Point Unit 3, Regarding Technical Specification Required Shutdown and a Safety System Functional Failure for a Leaking Service Water Piper Causing Flooding in the SW Valve Pit Preventing Access for Accident Mitigatio  + (For Indian Point Unit 3, Regarding Technical Specification Required Shutdown and a Safety System Functional Failure for a Leaking Service Water Piper Causing Flooding in the SW Valve Pit Preventing Access for Accident Mitigation)
• 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  + (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)
• 05000247/LER-2007-001, For Indian Point, Unit 2, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Residual Heat Removal Pump Due to an Electrical Supply Breaker Failure  + (For Indian Point, Unit 2, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Residual Heat Removal Pump Due to an Electrical Supply Breaker Failure)
• ML19093B095  + (For Information, Enclosed Are Copies of VEPCO Topical Report VEP-FED-29, Surry Unit 1, Cycle 4 Core Performance)
• ML19093B019  + (For Information, Enclosed Are Five Copies of VEPCO Topical Reports VEP-FRD-27, Surry Unit 2, Cycle 3 Core Performance Report & VEP-FRD-28, Surry Unit 2, Cycle 4 Startup Physics Test Report)

• ML20044B948  + (For Ipe)

• 05000333/LER-2009-003, For James A. FitzPatrick, Regarding Individual Granted Unescorted Access Based on an Incomplete Background Check  + (For James A. FitzPatrick, Regarding Individual Granted Unescorted Access Based on an Incomplete Background Check)
• 05000333/LER-2009-002, For James A. FitzPatrick, Regarding Subsystem Inoperable in Excess of Technical Specifications Allowed Out-of-Service Time  + (For James A. FitzPatrick, Regarding Subsystem Inoperable in Excess of Technical Specifications Allowed Out-of-Service Time)
• 05000333/LER-2009-004, For James A. Fitzpatrick, Regarding Subsystem Inoperable in Excess of Technical Specifications Allowed Out-of-Service Time  + (For James A. Fitzpatrick, Regarding Subsystem Inoperable in Excess of Technical Specifications Allowed Out-of-Service Time)
• 05000333/LER-2023-004, For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem  + (For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem)
• 05000348/LER-2002-004, For Joseph M. Farley Nuclear Plant Unit 1 Regarding Manual Reactor Trip on Loss of Both Steam Generator Feed Pumps  + (For Joseph M. Farley Nuclear Plant Unit 1 Regarding Manual Reactor Trip on Loss of Both Steam Generator Feed Pumps)
• 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  + (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)
• 05000305/LER-2003-004, For Kewaunee Failure to Log Nuclear Instrumentation Quadrant Power Tilt as Required by Tech Spec 3.10.j Due to Procedural Inadequacy  + (For Kewaunee Failure to Log Nuclear Instrumentation Quadrant Power Tilt as Required by Tech Spec 3.10.j Due to Procedural Inadequacy)
• 05000305/LER-2011-002, For Kewaunee Power Station Loss of Station Backfeed Results in Loss of One Train of Offsite Power During Refueling Outage  + (For Kewaunee Power Station Loss of Station Backfeed Results in Loss of One Train of Offsite Power During Refueling Outage)
• 05000305/LER-2005-012-01, For Kewaunee Power Station Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation  + (For Kewaunee Power Station Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation)
• 05000305/LER-2011-001, For Kewaunee Power Station, Regarding Auxiliary Building Special Ventilation Inoperability Results in Prohibited Technical Specification Condition  + (For Kewaunee Power Station, Regarding Auxiliary Building Special Ventilation Inoperability Results in Prohibited Technical Specification Condition)
• 05000305/LER-2012-003, For Kewaunee Power Station, Regarding Nuclear Instruments Inoperable for Longer Period than Allowed by Technical Specifications  + (For Kewaunee Power Station, Regarding Nuclear Instruments Inoperable for Longer Period than Allowed by Technical Specifications)
• 05000305/LER-2011-004, For Kewaunee Power Station, Regarding One Offsite AC Electrical Circuit Inoperable Not Performed Until After Discovery  + (For Kewaunee Power Station, Regarding One Offsite AC Electrical Circuit Inoperable Not Performed Until After Discovery)
• 05000305/LER-2011-005, For Kewaunee Power Station, for Shield Building Ventilation Train Inoperable for Longer Period than Allowed by Technical Specifications  + (For Kewaunee Power Station, for Shield Building Ventilation Train Inoperable for Longer Period than Allowed by Technical Specifications)
• 05000305/LER-2012-002, For Kewaunee Regarding Safety Injection Inoperable for Longer Period than Allowed by Technical Specifications  + (For Kewaunee Regarding Safety Injection Inoperable for Longer Period than Allowed by Technical Specifications)
• 05000305/LER-2009-004, For Kewaunee, Regarding Failed Backdraft Damper Renders Containment Fan Coil Unit Inoperable  + (For Kewaunee, Regarding Failed Backdraft Damper Renders Containment Fan Coil Unit Inoperable)
• 05000305/LER-2010-001, For Kewaunee, Regarding Safety Injection Pump Recirculation Line Isolation Results in Violation of Technical Specification  + (For Kewaunee, Regarding Safety Injection Pump Recirculation Line Isolation Results in Violation of Technical Specification)
• PM-90-037, For LERs 90-002 & 90-003  + (For LERs 90-002 & 90-003)
• 05000373/LER-2011-001, For LaSalle County Station, Unit 1 Re Automatic Reactor Scram Due to Main Power Transformer C Phase Electrical Fault  + (For LaSalle County Station, Unit 1 Re Automatic Reactor Scram Due to Main Power Transformer C Phase Electrical Fault)
• 05000373/LER-2018-003-01, For LaSalle County Station, Unit 1, Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test  + (For LaSalle County Station, Unit 1, Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test)
• 05000374/LER-2018-001, For LaSalle County Station, Unit 2, Manual Reactor Scram Due to Main Condenser Vacuum Degradation  + (For LaSalle County Station, Unit 2, Manual Reactor Scram Due to Main Condenser Vacuum Degradation)
• LR-N12-0200, For License Amendment Request - Cyber Security Plan Implementation Schedule Milestones  + (For License Amendment Request - Cyber Security Plan Implementation Schedule Milestones)
• 05000352/LER-2003-002, For Limerick Generating Station, Units 1 & 2 Regarding Core Alteration Without Secondary Containment Established  + (For Limerick Generating Station, Units 1 & 2 Regarding Core Alteration Without Secondary Containment Established)
• 05000352/LER-2002-004, For Limerick Unit 1 Regarding Reactor Enclosure Recirculation System (RERS) Train Potentially Inoperable for a Period Exceeding the TS AOT  + (For Limerick Unit 1 Regarding Reactor Enclosure Recirculation System (RERS) Train Potentially Inoperable for a Period Exceeding the TS AOT)
• 05000352/LER-2011-003, For Limerick, Unit 1, Regarding High Pressure Coolant Injection System Turbine Control Valve Failed to Fully Close During Testing  + (For Limerick, Unit 1, Regarding High Pressure Coolant Injection System Turbine Control Valve Failed to Fully Close During Testing)
• 05000352/LER-2009-002, For Limerick, Unit 1, Regarding a Control Room Emergency Fresh Air Supply System Subsystem Inoperable  + (For Limerick, Unit 1, Regarding a Control Room Emergency Fresh Air Supply System Subsystem Inoperable)