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List of results

• 05000331/LER-2003-006, For Duane Armold Energy Center Regarding an Unplanned Manual Reactor Scram Due to Degrading Condenser Vacuum  + (For Duane Armold Energy Center Regarding an Unplanned Manual Reactor Scram Due to Degrading Condenser Vacuum)
• 05000331/LER-2006-003, For Duane Arnold Energy Center, Re Residual Heat Removal Service Water Pump Inoperability Due to Motor Cooler Failures  + (For Duane Arnold Energy Center, Re Residual Heat Removal Service Water Pump Inoperability Due to Motor Cooler Failures)
• 05000366/LER-2008-003, For Edwin I. Hatch, Unit 2 Regarding Crack in Reactor Pressure Boundary Piping Due to High Cycle Fatigue Results in Leakage  + (For Edwin I. Hatch, Unit 2 Regarding Crack in Reactor Pressure Boundary Piping Due to High Cycle Fatigue Results in Leakage)
• 05000341/LER-2003-003, For Fermi 2 Re Non-Conservative Setpoints for Stability Option III (OPRM) Period Based Detection Algorithm, Period Confirmation Adjustable Variables  + (For Fermi 2 Re Non-Conservative Setpoints for Stability Option III (OPRM) Period Based Detection Algorithm, Period Confirmation Adjustable Variables)
• 05000341/LER-2010-001, For Fermi 2, Regarding Automatic Reactor Shutdown Due to Generator Current Transformer Wiring Failure  + (For Fermi 2, Regarding Automatic Reactor Shutdown Due to Generator Current Transformer Wiring Failure)
• 05000341/LER-2010-002, For Fermi 2, Regarding Automatic Reactor Scram and Loss of Offsite Power Due to Severe Weather  + (For Fermi 2, Regarding Automatic Reactor Scram and Loss of Offsite Power Due to Severe Weather)
• 05000341/LER-2016-010, For Fermi, Unit 2, Regarding Secondary Containment Pressure Exceeding Technical Specification Due to Adverse Weather  + (For Fermi, Unit 2, Regarding Secondary Containment Pressure Exceeding Technical Specification Due to Adverse Weather)
• 05000285/LER-2006-006, For Fort Calhoun Regarding Inadvertent Start of Emergency Diesel Generator 2  + (For Fort Calhoun Regarding Inadvertent Start of Emergency Diesel Generator 2)
• 05000285/LER-2011-006, For Fort Calhoun Regarding Inoperability of Both Trains of Containment Coolers Due to a Mispositioned Valve  + (For Fort Calhoun Regarding Inoperability of Both Trains of Containment Coolers Due to a Mispositioned Valve)
• 05000285/LER-2006-005, For Fort Calhoun Station Regarding Faulty Maintenance Renders One Train of Containment Spray System Inoperable  + (For Fort Calhoun Station Regarding Faulty Maintenance Renders One Train of Containment Spray System Inoperable)
• 05000285/LER-2011-007, For Fort Calhoun Station Regarding Violation of Technical Specifications Due to Reactor Coolant System Boundary Leakage  + (For Fort Calhoun Station Regarding Violation of Technical Specifications Due to Reactor Coolant System Boundary Leakage)
• 05000285/LER-2010-004, For Fort Calhoun Station, Regarding Acoustic Monitor Failure Due to Inadequate Barriers for Protection of Cable  + (For Fort Calhoun Station, Regarding Acoustic Monitor Failure Due to Inadequate Barriers for Protection of Cable)
• 05000285/LER-2010-001, For Fort Calhoun Station, Regarding Containment Integrity Violated During Performance of Leak Test  + (For Fort Calhoun Station, Regarding Containment Integrity Violated During Performance of Leak Test)
• 05000285/LER-2011-003, For Fort Calhoun Station, Regarding Inadequate Flooding Protection Due to Ineffective Oversight  + (For Fort Calhoun Station, Regarding Inadequate Flooding Protection Due to Ineffective Oversight)
• 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23  + (For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23)
• 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)