05000286/LER-1994-010, :on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised1994-11-0707 November 1994
- on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised
05000286/LER-1989-013-01, :on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities1989-07-28028 July 1989
- on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities
05000286/LER-1989-007, :on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained1989-04-17017 April 1989
- on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained
05000286/LER-1989-001, :on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded1989-03-0303 March 1989
- on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded
05000286/LER-1989-003-01, :on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed1989-02-23023 February 1989
- on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed
05000285/LER-1988-005-01, :on 880612,reactor Trip Occurred on Generated lo-lo Steam Generator Level Received from Steam Generator 32.Caused by Failure of Smoothing Orifice Relief Device in Westinghouse Main Turbine.Orifice Repaired1988-07-12012 July 1988
- on 880612,reactor Trip Occurred on Generated lo-lo Steam Generator Level Received from Steam Generator 32.Caused by Failure of Smoothing Orifice Relief Device in Westinghouse Main Turbine.Orifice Repaired
05000286/LER-1987-009-01, :on 870903,determined That If 480 Volt Tie Breaker Racked Out & Cell Switch in Breaker Failed & Loss of Power Occurred,Associated Diesel Generator Would Not Receive Signal.Cause Not Stated.Cell Switches Replaced1987-10-0202 October 1987
- on 870903,determined That If 480 Volt Tie Breaker Racked Out & Cell Switch in Breaker Failed & Loss of Power Occurred,Associated Diesel Generator Would Not Receive Signal.Cause Not Stated.Cell Switches Replaced
05000286/LER-1987-002, :on 870211,static Inverter Tripped Due to Overcurrent Condition.Caused by short-circuited Solenoid Valve.Failed Solenoid Valve Replaced & All Other Affected Sys Verified to Be Functioning Normally1987-03-13013 March 1987
- on 870211,static Inverter Tripped Due to Overcurrent Condition.Caused by short-circuited Solenoid Valve.Failed Solenoid Valve Replaced & All Other Affected Sys Verified to Be Functioning Normally
05000247/LER-1987-004, :on 870210,reactor Turbine Trip Occurred Due to Trip of Reactor Protection Train B.Caused by Personnel Error.Malfunctioning Breaker Cell Switch Subsequently Repaired1987-03-12012 March 1987
- on 870210,reactor Turbine Trip Occurred Due to Trip of Reactor Protection Train B.Caused by Personnel Error.Malfunctioning Breaker Cell Switch Subsequently Repaired
05000247/LER-1987-003, :on 870202,during Planned Shutdown,Condensate Storage Tank Isolation Valve LCV-1158 Failed to Close in Required Time.On 870203,motor Driven Auxiliary Feedwater Pumps Failed Flow Test1987-03-0404 March 1987
- on 870202,during Planned Shutdown,Condensate Storage Tank Isolation Valve LCV-1158 Failed to Close in Required Time.On 870203,motor Driven Auxiliary Feedwater Pumps Failed Flow Test
05000247/LER-1987-002, :on 870130,MSIVs Ms 1-21 & Ms 1-24 Failed to Fully Close.Caused by Excess Friction of Valve Shaft.Msivs Closed W/Manual Assistance,Lubricated & Retested1987-03-0202 March 1987
- on 870130,MSIVs Ms 1-21 & Ms 1-24 Failed to Fully Close.Caused by Excess Friction of Valve Shaft.Msivs Closed W/Manual Assistance,Lubricated & Retested
05000286/LER-1987-001-01, ,on 870131,reactor Trip & Turbine Trip Initiated by Low Steam Generator Water Level.Caused by Foreign Matter in Multiple Orifice & Check Valve Assembly in Main Boiler Feedwater Pump.Oil Sys Cleaned1987-03-0202 March 1987
,on 870131,reactor Trip & Turbine Trip Initiated by Low Steam Generator Water Level.Caused by Foreign Matter in Multiple Orifice & Check Valve Assembly in Main Boiler Feedwater Pump.Oil Sys Cleaned
05000247/LER-1987-001, :on 870121,while Unit at 98% Power,Plant Shutdown Initiated When Emergency Diesel Generator Svc Water Subsystem Declared Inoperable.Caused by Misalignment of Linkage Between Valves.Linkage Adjusted1987-02-20020 February 1987
- on 870121,while Unit at 98% Power,Plant Shutdown Initiated When Emergency Diesel Generator Svc Water Subsystem Declared Inoperable.Caused by Misalignment of Linkage Between Valves.Linkage Adjusted
05000247/LER-1986-039, :on 861217,control Rod (Rod) BO6 in Control Tank D Found Misaligned from Demand Position by 20 Steps for 16 H Prior to Discovery.Cause Unknown.Personnel Counseled on Maint of Monitor1987-01-16016 January 1987
- on 861217,control Rod (Rod) BO6 in Control Tank D Found Misaligned from Demand Position by 20 Steps for 16 H Prior to Discovery.Cause Unknown.Personnel Counseled on Maint of Monitor
05000286/LER-1986-012-01, :on 861114,reactor Trip Occurred Due to fail- Safe Design.Caused by Unintentional Opening of Dc Power Supply Breaker.Mod Designed to Provide Easier Access to Dc Power Panels & Prevent Recurrence1986-12-15015 December 1986
- on 861114,reactor Trip Occurred Due to fail- Safe Design.Caused by Unintentional Opening of Dc Power Supply Breaker.Mod Designed to Provide Easier Access to Dc Power Panels & Prevent Recurrence
05000247/LER-1986-038, :on 861113,safety Injection Pump 22 Failed to Operate Following Manual Start Signal.Caused by Accumulator Pump P Out of Svc for Maint.Pump Failure Analysis Will Be Performed.Pump Returned to Svc1986-12-14014 December 1986
- on 861113,safety Injection Pump 22 Failed to Operate Following Manual Start Signal.Caused by Accumulator Pump P Out of Svc for Maint.Pump Failure Analysis Will Be Performed.Pump Returned to Svc
05000247/LER-1986-037, :on 861106,reactor Trip Breaker B Opened During Performance of Monthly Surveillance Testing of Analog Bistables.Caused by Failure in One or More of Three Westinghouse BF66 Relays.Relays Replaced1986-12-0606 December 1986
- on 861106,reactor Trip Breaker B Opened During Performance of Monthly Surveillance Testing of Analog Bistables.Caused by Failure in One or More of Three Westinghouse BF66 Relays.Relays Replaced
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 Valves1986-11-22022 November 1986
- 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
05000247/LER-1986-035, :on 861020,reactor Tripped When Reactor Trip Breaker B Opened.Caused by Loose Wires in Relay Racks.Relay Rack Terminals Checked for Loose Connections & Auxiliary Feedwater Sys Retested & Restored to Operation1986-11-19019 November 1986
- on 861020,reactor Tripped When Reactor Trip Breaker B Opened.Caused by Loose Wires in Relay Racks.Relay Rack Terminals Checked for Loose Connections & Auxiliary Feedwater Sys Retested & Restored to Operation
05000247/LER-1986-034, :on 861016,F Function Signal to Overpower & Overtemp delta-T Trips Did Not Meet Test Acceptance Criteria.Caused by Three Defective Controllers.Two Controllers Repaired.Third Controller Replaced1986-11-15015 November 1986
- on 861016,F Function Signal to Overpower & Overtemp delta-T Trips Did Not Meet Test Acceptance Criteria.Caused by Three Defective Controllers.Two Controllers Repaired.Third Controller Replaced
05000247/LER-1986-033, :on 861015,480 Volt Emergency Diesel Generator Output Breakers 52 Eg 2A & 52 Eg 2B Failed to Close During Surveillance Check Causing Required Plant Shutdown.Cause Unknown.Breaker Racked Back to Svc & Tested1986-11-10010 November 1986
- on 861015,480 Volt Emergency Diesel Generator Output Breakers 52 Eg 2A & 52 Eg 2B Failed to Close During Surveillance Check Causing Required Plant Shutdown.Cause Unknown.Breaker Racked Back to Svc & Tested
05000247/LER-1986-032, :on 860922,daily Grab Sample of Containment Atmosphere Not Taken & Analyzed as Required by Tech Spec 3.1.F.1.b.6.Caused by Poor Communication Between Involved Personnel.Personnel Counseled1986-10-22022 October 1986
- on 860922,daily Grab Sample of Containment Atmosphere Not Taken & Analyzed as Required by Tech Spec 3.1.F.1.b.6.Caused by Poor Communication Between Involved Personnel.Personnel Counseled
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 Replaced1986-10-16016 October 1986
- 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
05000286/LER-1986-011-01, :on 860909,reactor Tripped Automatically on Low Steam Generator Water Level.Caused by Water in Boiler Feedpump Control Oil Sys.Oil Sys Cleaned & Temporary Water Deflector Installed1986-10-0909 October 1986
- on 860909,reactor Tripped Automatically on Low Steam Generator Water Level.Caused by Water in Boiler Feedpump Control Oil Sys.Oil Sys Cleaned & Temporary Water Deflector Installed
05000286/LER-1986-010-01, :on 860905,motor-operated Disconnect Switch on Generator Transmission Line Opened,Causing Turbine/Reactor Trip.Caused by Moisture in Underground Conduit Containing Control Wiring.New Conduit Installed1986-10-0606 October 1986
- on 860905,motor-operated Disconnect Switch on Generator Transmission Line Opened,Causing Turbine/Reactor Trip.Caused by Moisture in Underground Conduit Containing Control Wiring.New Conduit Installed
05000286/LER-1986-009-01, :on 860902,control Room Switches for Two Containment Spray Pumps & Two Recirculation Sump Pumps Found in trip-pullout Position.Caused by Lack of Communication. Prewarmup Checkoff List & Procedures Revised1986-10-0202 October 1986
- on 860902,control Room Switches for Two Containment Spray Pumps & Two Recirculation Sump Pumps Found in trip-pullout Position.Caused by Lack of Communication. Prewarmup Checkoff List & Procedures Revised
05000286/LER-1986-008-01, :on 860829,field Insp Identified Absence of Heat Shrink Tubing at Connection of Coaxial Cable of Containment high-range Radiation Monitors R25 & R26.Heat Shrinkable Tubing Installed1986-09-29029 September 1986
- on 860829,field Insp Identified Absence of Heat Shrink Tubing at Connection of Coaxial Cable of Containment high-range Radiation Monitors R25 & R26.Heat Shrinkable Tubing Installed
05000247/LER-1986-030, :on 860812,both Inner & Outer Air Lock Doors Momentarily Opened at Same Time,Resulting in Loss of Containment Integrity.Caused by Closing Mechanism Turning Too Quickly.Door Maint Scheduled1986-09-11011 September 1986
- on 860812,both Inner & Outer Air Lock Doors Momentarily Opened at Same Time,Resulting in Loss of Containment Integrity.Caused by Closing Mechanism Turning Too Quickly.Door Maint Scheduled
05000247/LER-1986-029, :on 860806,two Attempts Made to Close Diesel Generator Output Breaker W/O Success.Caused by Loose Pin or Springs Holding Breaker Stabs in Place.Breaker Refurbished, Tested & Returned to Svc1986-09-0505 September 1986
- on 860806,two Attempts Made to Close Diesel Generator Output Breaker W/O Success.Caused by Loose Pin or Springs Holding Breaker Stabs in Place.Breaker Refurbished, Tested & Returned to Svc
05000247/LER-1986-028, :on 860804,results of Calibr of Refueling Water Storage Tank Level Instrumentation Showed Low Level Alarm Setpoint Above Specified Level Setting.Caused by Unsuitable Instrumentation1986-09-0303 September 1986
- on 860804,results of Calibr of Refueling Water Storage Tank Level Instrumentation Showed Low Level Alarm Setpoint Above Specified Level Setting.Caused by Unsuitable Instrumentation
05000247/LER-1986-027, :on 860802,main Boiler Feed Pump 22 Tripped on Low Automatic Stop Oil Signal.Caused by Excessive Drain Off Through Worn Thrust Bearing to Thrust Seal.Oil Tubing Installed to Increase Oil Supply1986-09-0202 September 1986
- on 860802,main Boiler Feed Pump 22 Tripped on Low Automatic Stop Oil Signal.Caused by Excessive Drain Off Through Worn Thrust Bearing to Thrust Seal.Oil Tubing Installed to Increase Oil Supply
05000286/LER-1983-007-03, /03L-1:on 831205,surveillance Test 3PT-R38 Found 31 Seismic Snubbers Failing Operability Criteria.Caused by Degraded Seal Matl Due to Oil & Rust on Poppets.Snubber Rotation Policy Established1986-08-25025 August 1986
/03L-1:on 831205,surveillance Test 3PT-R38 Found 31 Seismic Snubbers Failing Operability Criteria.Caused by Degraded Seal Matl Due to Oil & Rust on Poppets.Snubber Rotation Policy Established
05000247/LER-1986-026, :on 860724,operation of Gaseous Effluent Monitoring Instrumentation Not in Accordance W/Tech Specs. Caused by Personnel Not Realizing That Inoperable Recorder Disabled Alarm Function.Operators Reinstructed1986-08-23023 August 1986
- on 860724,operation of Gaseous Effluent Monitoring Instrumentation Not in Accordance W/Tech Specs. Caused by Personnel Not Realizing That Inoperable Recorder Disabled Alarm Function.Operators Reinstructed
05000247/LER-1986-024, :on 860718,reactor Shut Down When CRD Mechanism Sys Voltage Degraded Enough to Allow Unlatching of Control Rods & Causing Turbine Trip.Caused by Low Voltage Condition1986-08-17017 August 1986
- on 860718,reactor Shut Down When CRD Mechanism Sys Voltage Degraded Enough to Allow Unlatching of Control Rods & Causing Turbine Trip.Caused by Low Voltage Condition
05000247/LER-1986-025, :on 860718,while Plant in Hot Shutdown,Loss of Instrument Air to Auxiliary Feedwater Sys Experienced.Caused by Inadvertent Breaching of Instrument Air Line.Alternate Air Supply Lines Established1986-08-17017 August 1986
- on 860718,while Plant in Hot Shutdown,Loss of Instrument Air to Auxiliary Feedwater Sys Experienced.Caused by Inadvertent Breaching of Instrument Air Line.Alternate Air Supply Lines Established
05000247/LER-1986-023, :on 860630,surveillance Interval for Exercise Test Exceeded for Rod K-6.Caused by Personnel Error & Inoperable Rod Position Indicator.Operability Tested.Rod Position Indicator Will Be Repaired1986-08-0606 August 1986
- on 860630,surveillance Interval for Exercise Test Exceeded for Rod K-6.Caused by Personnel Error & Inoperable Rod Position Indicator.Operability Tested.Rod Position Indicator Will Be Repaired
05000247/LER-1986-022, :on 860630,low Level Alarm Setpoints for Refueling Water Storage Tank Level Transmitters Discovered Outside Low Level Setpoint Margin Spec.Barton Model 288 Will Be Replaced W/Foxboro Model N-823DP1986-07-29029 July 1986
- on 860630,low Level Alarm Setpoints for Refueling Water Storage Tank Level Transmitters Discovered Outside Low Level Setpoint Margin Spec.Barton Model 288 Will Be Replaced W/Foxboro Model N-823DP
05000247/LER-1986-021, :on 860625,reactor Tripped Following Independent Electrical Overspeed Protection Sys (Ieops) Turbine Trip.Caused by Deficient Procedures Re Replacement of Defective Relays.Drawings Will Be Reissued1986-07-25025 July 1986
- on 860625,reactor Tripped Following Independent Electrical Overspeed Protection Sys (Ieops) Turbine Trip.Caused by Deficient Procedures Re Replacement of Defective Relays.Drawings Will Be Reissued
05000247/LER-1986-020, :on 860624,two Reactor Protection Sys hi-hi Containment Pressure Instruments Inoperable.Caused by Static Inverter Trip & Failure of Alternate Feed to Energize. Breakers & Static Inverter Returned to Svc1986-07-24024 July 1986
- on 860624,two Reactor Protection Sys hi-hi Containment Pressure Instruments Inoperable.Caused by Static Inverter Trip & Failure of Alternate Feed to Energize. Breakers & Static Inverter Returned to Svc
05000247/LER-1986-018, :on 860606,battery Cell Voltage Determined to Be Below Min Acceptable Value at 123.54 Volts Dc & Battery Declared Inoperable.Caused by Defective Transistor in Voltage Regulator.Transistor Replaced1986-07-0707 July 1986
- on 860606,battery Cell Voltage Determined to Be Below Min Acceptable Value at 123.54 Volts Dc & Battery Declared Inoperable.Caused by Defective Transistor in Voltage Regulator.Transistor Replaced
05000247/LER-1986-019, :on 860609,safety Injection Sys Actuated After Manual Reactor/Turbine Trip While One Main Boiler Feed Pump in Operation.Caused by Failed Bistable TC-412 I.Inoperable Pump Repaired & Bistable Replaced1986-07-0707 July 1986
- on 860609,safety Injection Sys Actuated After Manual Reactor/Turbine Trip While One Main Boiler Feed Pump in Operation.Caused by Failed Bistable TC-412 I.Inoperable Pump Repaired & Bistable Replaced
05000247/LER-1986-017, :on 860528,safety Injection Actuation & Reactor Trip Occurred Due to Condenser Steam Dump Valves Opening. Caused by Erratic Steam Dump Controller PC-404 Output. Controller Recalibr1986-07-0101 July 1986
- on 860528,safety Injection Actuation & Reactor Trip Occurred Due to Condenser Steam Dump Valves Opening. Caused by Erratic Steam Dump Controller PC-404 Output. Controller Recalibr
05000247/LER-1986-012, :on 860325,discovered That Large Gas Decay Tank Releases Occurred Between 860303-17.Caused by Personnel Failure to Adhere to Procedure.Surveillance Test Revised to Withdraw Not Applicable Entry1986-06-27027 June 1986
- on 860325,discovered That Large Gas Decay Tank Releases Occurred Between 860303-17.Caused by Personnel Failure to Adhere to Procedure.Surveillance Test Revised to Withdraw Not Applicable Entry
05000286/LER-1986-007-01, :on 860527,during Surveillance Testing W/ Reactor in Hot Shutdown,Inadvertent Safety Injection Actuation Occurred.Caused by Technicians Activating High Steam Flow Portion of Safety Injection Logic1986-06-26026 June 1986
- on 860527,during Surveillance Testing W/ Reactor in Hot Shutdown,Inadvertent Safety Injection Actuation Occurred.Caused by Technicians Activating High Steam Flow Portion of Safety Injection Logic
05000286/LER-1986-006-01, :on 860526,reactor & Turbine Trips Initiated by Low Water Level in Steam Generator 34.Caused by Condensate Polisher Facility Booster Pumps a & B Automatically Starting.Operating Procedures Revised1986-06-25025 June 1986
- on 860526,reactor & Turbine Trips Initiated by Low Water Level in Steam Generator 34.Caused by Condensate Polisher Facility Booster Pumps a & B Automatically Starting.Operating Procedures Revised
05000247/LER-1986-016, :on 860523,unplanned Actuation of Reactor Protection Sys Occurred.Caused by Personnel Error.Personnel Involved in Trip Reinstructed in Correct Performance of Procedure1986-06-23023 June 1986
- on 860523,unplanned Actuation of Reactor Protection Sys Occurred.Caused by Personnel Error.Personnel Involved in Trip Reinstructed in Correct Performance of Procedure
05000247/LER-1986-015, :on 860521,excessive Leakage of Main Steam Safety Relief Valves Found.Caused by Damage to Valves During Secondary Plant Transient on 860501.Valves Refurbished1986-06-20020 June 1986
- on 860521,excessive Leakage of Main Steam Safety Relief Valves Found.Caused by Damage to Valves During Secondary Plant Transient on 860501.Valves Refurbished
05000286/LER-1986-005-01, :on 860523,turbine Trip Occurred During Monthly Surveillance Test 3PT-M12.Caused by Failed Relay in Turbine Independent Electrical Overspeed Protection Sys (Ieops). Relay Replaced & Similar Ieops Relays Tested1986-06-19019 June 1986
- on 860523,turbine Trip Occurred During Monthly Surveillance Test 3PT-M12.Caused by Failed Relay in Turbine Independent Electrical Overspeed Protection Sys (Ieops). Relay Replaced & Similar Ieops Relays Tested
05000286/LER-1986-003-01, :on 860519,high Water Level in Steam Generator 34 Resulted in Turbine & Reactor Trips.Caused by Check Valve BFD-1-32 Failure to Reverse Flow Due to Loose Pivot Pins. Disk Pivot Pins Anchored Properly1986-06-18018 June 1986
- on 860519,high Water Level in Steam Generator 34 Resulted in Turbine & Reactor Trips.Caused by Check Valve BFD-1-32 Failure to Reverse Flow Due to Loose Pivot Pins. Disk Pivot Pins Anchored Properly
05000247/LER-1986-014, :on 860518,seismic Restraint SR-1092 Disconnected.Caused by Failure of Maint Procedure for Reactor Coolant Pump Seal Overhaul to Assure Reinstallation of SR-1092.Procedure Revised1986-06-17017 June 1986
- on 860518,seismic Restraint SR-1092 Disconnected.Caused by Failure of Maint Procedure for Reactor Coolant Pump Seal Overhaul to Assure Reinstallation of SR-1092.Procedure Revised