| Title | Site | Reactor type⠉ |
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05000029/LER-1988-003, :on 880326,reactor Scrammed & Turbine Tripped on Low Steam Generator Level at 85% Power.Caused by Failure of Power Supply for Steam Generator Level Control Channels on Steam Generators.Feedwater Pumps Restarted |
- on 880326,reactor Scrammed & Turbine Tripped on Low Steam Generator Level at 85% Power.Caused by Failure of Power Supply for Steam Generator Level Control Channels on Steam Generators.Feedwater Pumps Restarted
| Yankee Rowe | Westinghouse PWR 4-Loop |
05000206/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1989-012, :on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow |
- on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1989-019, :on 890724,unit Manually Tripped Due to Loss of Feedwater Flow to Steam Generator a & Hi Hi Level & Steam/ Feed Mismatch Alarm Received.Caused by Error in Incorporating Design Change Info |
- on 890724,unit Manually Tripped Due to Loss of Feedwater Flow to Steam Generator a & Hi Hi Level & Steam/ Feed Mismatch Alarm Received.Caused by Error in Incorporating Design Change Info
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1989-023, :on 890918,four Control Rods from Shutdown Bank 2 Dropped Into Core & Approx 23 Later,Remaining 12 Shutdown Bank Control Rods Dropped Into Core.Caused by Failure of Contactor Coil 2MS1.Coil Replaced |
- on 890918,four Control Rods from Shutdown Bank 2 Dropped Into Core & Approx 23 Later,Remaining 12 Shutdown Bank Control Rods Dropped Into Core.Caused by Failure of Contactor Coil 2MS1.Coil Replaced
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1989-023-02, :on 890918,manual Reactor Trip Occurred Following Dropped Shutdown Bank Rods.Caused by Failed Contactor Coil & Blown Fuse.Contactor Coil & Fuse Replaced w/in-kind Parts |
- on 890918,manual Reactor Trip Occurred Following Dropped Shutdown Bank Rods.Caused by Failed Contactor Coil & Blown Fuse.Contactor Coil & Fuse Replaced w/in-kind Parts
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1990-011, :on 900515,manual Reactor Trip Occurred Due to Low & Decreasing Level in Steam Generator Resulting from Loss of Feedwater Flow.Caused by Short to Ground in Valve Control Cable.Investigation Continuing |
- on 900515,manual Reactor Trip Occurred Due to Low & Decreasing Level in Steam Generator Resulting from Loss of Feedwater Flow.Caused by Short to Ground in Valve Control Cable.Investigation Continuing
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1990-019, :on 901016,nuclear Overpower Low Trip Setpoint Was Determined to Be Greater than Allowed by Tech Specs Due to Inadequate Review of Design Change Documents |
- on 901016,nuclear Overpower Low Trip Setpoint Was Determined to Be Greater than Allowed by Tech Specs Due to Inadequate Review of Design Change Documents
| San Onofre | CE Westinghouse PWR 3-Loop |
05000206/LER-1991-010, :on 910528,2 of 12 Control Bank 1 Control Alarms Dropped Into Core & Reactor Manually Tripped.Caused by Open Connection in half-voltage Resistor Network.Jumper & Lugs Replaced w/in-kind Parts |
- on 910528,2 of 12 Control Bank 1 Control Alarms Dropped Into Core & Reactor Manually Tripped.Caused by Open Connection in half-voltage Resistor Network.Jumper & Lugs Replaced w/in-kind Parts
| San Onofre | CE Westinghouse PWR 3-Loop |
05000213/LER-1986-020, :on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled |
- on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1986-027, :on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve |
- on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1986-041, :on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg |
- on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1986-044, :on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated |
- on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1990-010, :on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised |
- on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1990-020, :on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance |
- on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1992-020, :on 920727,wide Range SG Level Channel Declared Inoperable.Caused by Implementation of Std Instrumentation Action Statement W/O Associated Hardware. Channel Restored to Operability |
- on 920727,wide Range SG Level Channel Declared Inoperable.Caused by Implementation of Std Instrumentation Action Statement W/O Associated Hardware. Channel Restored to Operability
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1993-012, :on 930714,high Steam Flow Transmitters Inadvertently Isolated Due to Inadequate Administrative Controls.Preventive Matl Procedure PMP 9.2-29 Revised.W/ |
- on 930714,high Steam Flow Transmitters Inadvertently Isolated Due to Inadequate Administrative Controls.Preventive Matl Procedure PMP 9.2-29 Revised.W/
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1996-022, :on 960901,RCS Loop Stop Valves Were Opened Without Timely Boron Sample.Caused by Personnel Error. Operations Dept Formed New Procedure Group to Upgrade Operations Procedures |
- on 960901,RCS Loop Stop Valves Were Opened Without Timely Boron Sample.Caused by Personnel Error. Operations Dept Formed New Procedure Group to Upgrade Operations Procedures
| Haddam Neck | Westinghouse PWR 4-Loop |
05000213/LER-1997-015, :on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure |
- on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure
| Haddam Neck | Westinghouse PWR 4-Loop |
05000244/LER-1985-014, :on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs |
- on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1985-019, :on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily |
- on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1986-004, :on 860729,reactor Tripped Manually When Large Steam Leak Discovered in Turbine Bldg.Caused by Leak in Pipe Elbow on Moisture Separator Reheater Drain Line 2A.Elbow Replaced & Tested Satisfactorily |
- on 860729,reactor Tripped Manually When Large Steam Leak Discovered in Turbine Bldg.Caused by Leak in Pipe Elbow on Moisture Separator Reheater Drain Line 2A.Elbow Replaced & Tested Satisfactorily
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1986-008, :on 861023,automatic Reactor Trip Occurred from Pressurizer High Pressure Due to Turbine Load Runback.Caused by Personnel Error.Module Replacement Procedure Written & Control & Protective Devices Checked & Tested |
- on 861023,automatic Reactor Trip Occurred from Pressurizer High Pressure Due to Turbine Load Runback.Caused by Personnel Error.Module Replacement Procedure Written & Control & Protective Devices Checked & Tested
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1986-011, :on 861128,MSIV Inadvertently Closed,Causing Pressurizer High Pressure Reactor Trip.Caused by Personnel Error.Event Discussed W/Personnel |
- on 861128,MSIV Inadvertently Closed,Causing Pressurizer High Pressure Reactor Trip.Caused by Personnel Error.Event Discussed W/Personnel
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1995-008, :on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels |
- on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1996-002, :on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed |
- on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-1996-012, :on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was Replaced |
- on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was Replaced
| Ginna | Westinghouse PWR 2-Loop |
05000244/LER-2002-001 | 0 LER 2002-001, Loss of "A" Condenser Circulating Water Pump Results in | R.E. Ginna Nuclear Power Plant0 Page: 1 Of 8 | |
05000244/LER-2003-002, Major Power Grid Disturbance Causes Loss of Electrical Load and Reactor Trip | Major Power Grid Disturbance Causes Loss of Electrical Load and Reactor Trip | Ginna | |
05000244/LER-2009-002, Regarding Plant Trip Due to Loss of Electro-Hydraulic Control System Pressure | Regarding Plant Trip Due to Loss of Electro-Hydraulic Control System Pressure | Ginna | |
05000244/LER-2011-003, Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping | Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping | Ginna | |
05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level | Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level | Ginna | |
05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam | Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam | Ginna | |
05000247/FIN-2013002-01 | Inadequate Maintenance Procedure Results in a Reactor Trip | Indian Point | Westinghouse PWR 4-Loop |
05000247/FIN-2018003-04 | Inadequate Procedure for Turbine Startup Caused a Reactor Trip | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-1917-001, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed | Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-1917-002, Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration | Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-1986-031, :on 860916,during Preparation for Biweekly Rod Exercise Test,Reactor Manually Tripped Following Drop of Three Control Rods.Caused by Inadequate Electrical Jumper. Jumper Replaced |
- on 860916,during Preparation for Biweekly Rod Exercise Test,Reactor Manually Tripped Following Drop of Three Control Rods.Caused by Inadequate Electrical Jumper. Jumper Replaced
| Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-1986-036, :on 861023,reactor Tripped Manually Following Automatic Trip of Main Boiler Feed Pump on High Discharge Pressure Due to Excess Flow.Caused by Problems W/Main Feedwater Discharge Valves |
- on 861023,reactor Tripped Manually Following Automatic Trip of Main Boiler Feed Pump on High Discharge Pressure Due to Excess Flow.Caused by Problems W/Main Feedwater Discharge Valves
| Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2000-001, Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000 | Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000 | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2001-001 | | | |
05000247/LER-2001-007, Re Automatic Reactor Trip Initiated by Main Turbine Trip on Auto Stop Oil | Re Automatic Reactor Trip Initiated by Main Turbine Trip on Auto Stop Oil | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2002-003, Loss of 138 Kv Offsite Power Source Due to Ground Protection Trip Results in Auto Start of Emergency Diesel Generators | Loss of 138 Kv Offsite Power Source Due to Ground Protection Trip Results in Auto Start of Emergency Diesel Generators | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2003-003, From Indian Point, Unit 2 Regarding Automatic Reactor Trip Initiated by a Main Turbine Trip on Auto Stop Oil | From Indian Point, Unit 2 Regarding Automatic Reactor Trip Initiated by a Main Turbine Trip on Auto Stop Oil | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2003-004, Re Automatic Turbine Trip/Reactor Trip Due to 345kV Grid Disturbance | Re Automatic Turbine Trip/Reactor Trip Due to 345kV Grid Disturbance | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2004-001, Re Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating Valve | Re Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating Valve | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2004-002, Re Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring Failure | Re Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring Failure | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2004-005, Regarding Automatic Reactor Trip Due to Turbine Generator Trip Caused by Low Stator Cooling Water Pressure | Regarding Automatic Reactor Trip Due to Turbine Generator Trip Caused by Low Stator Cooling Water Pressure | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2006-003, Regarding Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank Pumps | Regarding Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank Pumps | Indian Point | Westinghouse PWR 4-Loop |
05000247/LER-2006-005, Re Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical Ground | Re Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical Ground | Indian Point | Westinghouse PWR 4-Loop |