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- 05000457/LER-1990-011-02, :on 900805 & 06,containment - Fuel Handling Incident Area Radiation Monitor Momentarily Went Into High Alarm & Interlock Actuation.Caused by Failed Component. Detector Replaced & Monitor Recalibr + ( :on 900805 & 06,containment - Fuel Handling Incident Area Radiation Monitor Momentarily Went Into High Alarm & Interlock Actuation.Caused by Failed Component. Detector Replaced & Monitor Recalibr )
- 05000369/LER-1990-021-01, :on 900805,control Room Operator Inadvertently Used semi-daily Surveillance Items Procedure Checklist to Complete Unit 1 semi-daily Surveillance Requirements.Caused by Personnel Error.Operator Counseled + ( :on 900805,control Room Operator Inadvertently Used semi-daily Surveillance Items Procedure Checklist to Complete Unit 1 semi-daily Surveillance Requirements.Caused by Personnel Error.Operator Counseled )
- 05000272/LER-1990-025-01, :on 900806,control Room Air Intake Radiation Sys Monitor Alarm Circuitry Spiked High Resulting in Automatic Switching of Ventilation to Accident Mode of Operation.Addl Spikes Occurred on 900807 & 08 + ( :on 900806,control Room Air Intake Radiation Sys Monitor Alarm Circuitry Spiked High Resulting in Automatic Switching of Ventilation to Accident Mode of Operation.Addl Spikes Occurred on 900807 & 08 )
- 05000397/LER-1990-015, :on 900806,diesel Fuel Oil Analysis Tech Spec Surveillance Verification Time Requirement Exceeded.Caused by Inadequate Procedure & Work Practices.Temporary Procedure for Diesel Generator Fuel Sampling Cancelled + ( :on 900806,diesel Fuel Oil Analysis Tech Spec Surveillance Verification Time Requirement Exceeded.Caused by Inadequate Procedure & Work Practices.Temporary Procedure for Diesel Generator Fuel Sampling Cancelled )
- 05000213/LER-1990-013, :on 900806,engineering Evaluation Determined That Installation of Incorrect O-ring Matl in Four safety- Related motor-operated Valves Could Render Valves Inoperable.Caused by Procedural Inadequacies + ( :on 900806,engineering Evaluation Determined That Installation of Incorrect O-ring Matl in Four safety- Related motor-operated Valves Could Render Valves Inoperable.Caused by Procedural Inadequacies )
- 05000213/LER-1990-014, :on 900806,incorrect Torque Switch Settings Discovered on RCS Loop Isolation Valves.Caused by Inadequate Setpoint Control.Torque Switches Set to Mfg Recommended Setting + ( :on 900806,incorrect Torque Switch Settings Discovered on RCS Loop Isolation Valves.Caused by Inadequate Setpoint Control.Torque Switches Set to Mfg Recommended Setting )
- 05000245/LER-1990-013, :on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset + ( :on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset )
- 05000397/LER-1990-016, :on 900806,steam Supply Line Isolation Valve for RCIC Sys Turbine Discovered to Have Unacceptable Closing Time.Caused by Personnel Error.Personnel Counseled & Trained on ASME Test Program & Generic Ltr 89-04 + ( :on 900806,steam Supply Line Isolation Valve for RCIC Sys Turbine Discovered to Have Unacceptable Closing Time.Caused by Personnel Error.Personnel Counseled & Trained on ASME Test Program & Generic Ltr 89-04 )
- 05000424/LER-1990-024-01, :on 900807,Unit 2 Containment Isolation Valves Associated W/Train a Closed & Unit 1 Valves Opened for Testing.Caused by Procedural Inadequacy.Procedures Revised & Procedure Coordinator Informed + ( :on 900807,Unit 2 Containment Isolation Valves Associated W/Train a Closed & Unit 1 Valves Opened for Testing.Caused by Procedural Inadequacy.Procedures Revised & Procedure Coordinator Informed )
- 05000259/LER-1990-013-01, :on 900807,fuse Blew in Primary Containment Isolation Sys Logic Panel Resulting in Actuation of Esf. Caused by Random Failure of Relay.Failed Relay Replaced & Primary Containment Isolation Logic Reset + ( :on 900807,fuse Blew in Primary Containment Isolation Sys Logic Panel Resulting in Actuation of Esf. Caused by Random Failure of Relay.Failed Relay Replaced & Primary Containment Isolation Logic Reset )
- 05000445/LER-1990-022, :on 900807,realized That Pressurizer Heatup Limit Exceeded Due to Failure to Comply W/Tech Spec Action Statement Following 900726 & 30 Events.Caused by Inadequate post-trip Review.Procedures & Training Revised + ( :on 900807,realized That Pressurizer Heatup Limit Exceeded Due to Failure to Comply W/Tech Spec Action Statement Following 900726 & 30 Events.Caused by Inadequate post-trip Review.Procedures & Training Revised )
- 05000316/LER-1990-008-02, :on 900807,when Seal Matl Removed for Lab Analysis,Portions Found Badly Degraded.Cause Not Determined. Safety Evaluation Performed Concluding That Degraded Barrier Seals Did Not Represent Safety Threat + ( :on 900807,when Seal Matl Removed for Lab Analysis,Portions Found Badly Degraded.Cause Not Determined. Safety Evaluation Performed Concluding That Degraded Barrier Seals Did Not Represent Safety Threat )
- 05000298/LER-1990-009, :on 900808,RCIC Inoperable Due to Failure of motor-operated Steam Supply Valve.Caused by Hydraulic Lock Condition in Spring Pack.Motor Replaced & Spring Pack Cleaned + ( :on 900808,RCIC Inoperable Due to Failure of motor-operated Steam Supply Valve.Caused by Hydraulic Lock Condition in Spring Pack.Motor Replaced & Spring Pack Cleaned )
- 05000424/LER-1990-020-01, :on 900808,personnel Error Led to Tech Spec Violation + ( :on 900808,personnel Error Led to Tech Spec Violation )
- 05000445/LER-1990-023, :on 900808,reactor Tripped on Loss of Feedwater Flow.Caused by Loose Fuse in Main Feedwater Control Power Circuit.Corrective Maint Performed on Malfunctioning Fuse Clip + ( :on 900808,reactor Tripped on Loss of Feedwater Flow.Caused by Loose Fuse in Main Feedwater Control Power Circuit.Corrective Maint Performed on Malfunctioning Fuse Clip )
- 05000313/LER-1990-008, :on 900809,determined That Control Room Wall Not Seismically Qualified.Caused by Engineering Error in Accepting Deficient Installation During Const of Wall.Review of All Masonary Walls in Progress + ( :on 900809,determined That Control Room Wall Not Seismically Qualified.Caused by Engineering Error in Accepting Deficient Installation During Const of Wall.Review of All Masonary Walls in Progress )
- 05000304/LER-1990-009-07, :on 900809,diesel Generator Output Breaker 2B auto-closed While Attempting to Synchronize Diesel Generator to Bus 249.Investigation Revealed Cable Not Shown on Drawings.Cable Disconnected at Each End + ( :on 900809,diesel Generator Output Breaker 2B auto-closed While Attempting to Synchronize Diesel Generator to Bus 249.Investigation Revealed Cable Not Shown on Drawings.Cable Disconnected at Each End )
- 05000311/LER-1990-032, :on 900809,inservice Testing Program Discovered Not in Compliance.Caused by Inadequate Administrative Control.Review of Administrative Controls for Compliance W/Surveillance Frequency Changes Initiated + ( :on 900809,inservice Testing Program Discovered Not in Compliance.Caused by Inadequate Administrative Control.Review of Administrative Controls for Compliance W/Surveillance Frequency Changes Initiated )
- 05000311/LER-1990-033, :on 900809,isolation Signals Received from Containment purge/pressure-vacuum Relief Sys & on 900824, Second ESF Signal Occurred.Caused by Design/Equipment. Channel 2R11A Repaired + ( :on 900809,isolation Signals Received from Containment purge/pressure-vacuum Relief Sys & on 900824, Second ESF Signal Occurred.Caused by Design/Equipment. Channel 2R11A Repaired )
- 05000254/LER-1990-016-02, :on 900809,loss of Diesel Fire Pump 1/2A Due to Failure of Starting Relays Occurred.Caused by Component Failure.Relays Replaced + ( :on 900809,loss of Diesel Fire Pump 1/2A Due to Failure of Starting Relays Occurred.Caused by Component Failure.Relays Replaced )
- 05000458/LER-1990-025, :on 900809,surveillance Requirements Not Performed on Valve Due to Omission from Tech Spec Table 3.6.4-1.Caused by Personnel Oversight.Monthly Operating Log Revised + ( :on 900809,surveillance Requirements Not Performed on Valve Due to Omission from Tech Spec Table 3.6.4-1.Caused by Personnel Oversight.Monthly Operating Log Revised )
- 05000280/LER-1990-009-01, :on 900810 & 29,containment Vacuum Pump Flow Paths Became Inoperable.Caused by Failure of Process Vent Normal Range Radiation Monitor Due to Defective Flow Switch & Failed Cpu Card.Components Replaced + ( :on 900810 & 29,containment Vacuum Pump Flow Paths Became Inoperable.Caused by Failure of Process Vent Normal Range Radiation Monitor Due to Defective Flow Switch & Failed Cpu Card.Components Replaced )
- 05000458/LER-1990-026, :on 900810,RWCU Isolated.Caused by Short Circuit During Jumper Manipulation.Prompt Maint Work Order Initiated to Replace Blown Fuses + ( :on 900810,RWCU Isolated.Caused by Short Circuit During Jumper Manipulation.Prompt Maint Work Order Initiated to Replace Blown Fuses )
- 05000416/LER-1990-014, :on 900810,retest Not Performed Prior to Returning Secondary Containment Isolation Valve to Operable Status.Caused by Programmatic Weaknesses in Administrative Controls.Plant Procedures Changed + ( :on 900810,retest Not Performed Prior to Returning Secondary Containment Isolation Valve to Operable Status.Caused by Programmatic Weaknesses in Administrative Controls.Plant Procedures Changed )
- 05000259/LER-1990-014-01, :on 900810,unplanned ESF Actuation Occurred. Caused by Blown Fuse.Fuse Replaced.Reactor Protection Sys Bus 1A Realigned to Alternate Power Supply on 900811.W/ + ( :on 900810,unplanned ESF Actuation Occurred. Caused by Blown Fuse.Fuse Replaced.Reactor Protection Sys Bus 1A Realigned to Alternate Power Supply on 900811.W/ )
- 05000353/LER-1990-016-01, :on 900811,Tech Spec 3.7.6.4 Not Met Since Halon Sys Inoperable + ( :on 900811,Tech Spec 3.7.6.4 Not Met Since Halon Sys Inoperable )
- 05000423/LER-1990-027, :on 900811,Tech Spec Fire Door Discovered Blocked Open.Caused by Inadequate Training of Fire Watch Personnel.Door Closed & Fire Watch Personnel Issued Memo Reinforcing Importance of Patrol Info + ( :on 900811,Tech Spec Fire Door Discovered Blocked Open.Caused by Inadequate Training of Fire Watch Personnel.Door Closed & Fire Watch Personnel Issued Memo Reinforcing Importance of Patrol Info )
- 05000282/LER-1990-009-01, :on 900811,automatic Start of Component Cooling Pump Occurred.Caused by Momentary Low Pressure in Component Cooling Water Sys.Procedures to Be Revised to Warn Operator of Possibility of Automatic Pump Starts + ( :on 900811,automatic Start of Component Cooling Pump Occurred.Caused by Momentary Low Pressure in Component Cooling Water Sys.Procedures to Be Revised to Warn Operator of Possibility of Automatic Pump Starts )
- 05000414/LER-1990-007-02, :on 900811,diesel Generator Battery 2A Found to Have Cell Below Tech Spec Required Voltage.Caused by High Temp Environ That Battery Constantly Exposed To.Low Cell Jumpered & Bad Cell Replaced + ( :on 900811,diesel Generator Battery 2A Found to Have Cell Below Tech Spec Required Voltage.Caused by High Temp Environ That Battery Constantly Exposed To.Low Cell Jumpered & Bad Cell Replaced )
- 05000029/LER-1990-006, :on 900811,emergency Diesel Generators Failed Tech Spec Surveillance Test.Investigation Team Formed to Review Testing History & Determine Cause.Design Change to Replace Emergency Diesel Generators Initiated + ( :on 900811,emergency Diesel Generators Failed Tech Spec Surveillance Test.Investigation Team Formed to Review Testing History & Determine Cause.Design Change to Replace Emergency Diesel Generators Initiated )
- 05000353/LER-1990-016-02, :on 900811,failure to Meet Tech Spec 3.7.6.4 Since Halon Sys Inoperable & Tech Spec Action Not Taken in Appropriate Time Period + ( :on 900811,failure to Meet Tech Spec 3.7.6.4 Since Halon Sys Inoperable & Tech Spec Action Not Taken in Appropriate Time Period )
- 05000456/LER-1990-013, :on 900811,feedwater Isolation Occurred Due to Spurious Actuation of Train B Feedwater Isolation Circuitry. Feedwater Isolation Reset & Flow Reestablished to Steam Generators + ( :on 900811,feedwater Isolation Occurred Due to Spurious Actuation of Train B Feedwater Isolation Circuitry. Feedwater Isolation Reset & Flow Reestablished to Steam Generators )
- 05000456/LER-1990-013-02, :on 900811,feedwater Isolation Occurred Due to Spurious Actuation of Train B Feedwater Isolation Circuitry. Feedwater Isolation Reset & Feedwater Flow Reestablished to Steam Generators + ( :on 900811,feedwater Isolation Occurred Due to Spurious Actuation of Train B Feedwater Isolation Circuitry. Feedwater Isolation Reset & Feedwater Flow Reestablished to Steam Generators )
- 05000254/LER-1990-017, :on 900811,observed Excessive Leakage Through HPCI Steam Exhaust Check Valve Due to Deterioration of Seat. Caused by Gap Between Seat & Disk Along Ctr Sealing Surface of Disks.Steam Exhaust Check Valve Replaced + ( :on 900811,observed Excessive Leakage Through HPCI Steam Exhaust Check Valve Due to Deterioration of Seat. Caused by Gap Between Seat & Disk Along Ctr Sealing Surface of Disks.Steam Exhaust Check Valve Replaced )
- 05000455/LER-1990-005-11, :on 900811,pre-outage Mod Work Initiated W/O Proper Operability Review Due to Personnel Error.Daily Const Work Authorization Sheet Formalized & Will Specify Scope of Work Step by Step During Nonoutage Periods + ( :on 900811,pre-outage Mod Work Initiated W/O Proper Operability Review Due to Personnel Error.Daily Const Work Authorization Sheet Formalized & Will Specify Scope of Work Step by Step During Nonoutage Periods )
- 05000254/LER-1990-021, :on 900812,RHR Valve 1001-50 Failed to Open During Shutdown Cooling & Startup Operations.Caused by Thermal Binding of Valve & Hydraulic Lock of Valve Operator.Valve Manually Operated + ( :on 900812,RHR Valve 1001-50 Failed to Open During Shutdown Cooling & Startup Operations.Caused by Thermal Binding of Valve & Hydraulic Lock of Valve Operator.Valve Manually Operated )
- 05000251/LER-1990-008-02, :on 900812,automatic Reactor Trip on low-low Steam Generator Level Occurred Due to Loss of Steam Generator 4A Feedwater Pump.Caused by Incorrect Setpoint on Agastat Trip Delay.Condensate Pump Repaired + ( :on 900812,automatic Reactor Trip on low-low Steam Generator Level Occurred Due to Loss of Steam Generator 4A Feedwater Pump.Caused by Incorrect Setpoint on Agastat Trip Delay.Condensate Pump Repaired )
- 05000456/LER-1990-014-01, :on 900812,entry Into Mode 3 Occurred Prior to Performing 1B MSIV Operability Test.Caused by Mgt, Procedural & Communication Deficiency & Inadequate Review. Training Provided + ( :on 900812,entry Into Mode 3 Occurred Prior to Performing 1B MSIV Operability Test.Caused by Mgt, Procedural & Communication Deficiency & Inadequate Review. Training Provided )
- 05000272/LER-1990-027-01, :on 900812,main Steamline Isolation Actuation Occurred.Caused by Possible Equipment/Design Concerns. Design Mods to Correct Main Steamline Flow Instrumenation Concerns Under Development + ( :on 900812,main Steamline Isolation Actuation Occurred.Caused by Possible Equipment/Design Concerns. Design Mods to Correct Main Steamline Flow Instrumenation Concerns Under Development )
- 05000254/LER-1990-021-01, :on 900812,residual Heat Removal Valve 1001-50 Failed to Open Due to Thermal Binding + ( :on 900812,residual Heat Removal Valve 1001-50 Failed to Open Due to Thermal Binding )
- 05000352/LER-1990-015-01, :on 900813,RWCU Sys Isolation Occurred. Isolation Resulted from High Regenerative HX Room Temp. Caused by Leaking Sys Vent Valves.Leaking Valves Replaced + ( :on 900813,RWCU Sys Isolation Occurred. Isolation Resulted from High Regenerative HX Room Temp. Caused by Leaking Sys Vent Valves.Leaking Valves Replaced )
- 05000245/LER-1990-012-01, :on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor + ( :on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor )
- 05000424/LER-1987-083, :on 900813,discovered That Instrument 2TIS-10980 Used for Verifying Refueling Water Storage Tank Temp Not Indicating.Caused by Procedural Inadequacy. Procedures Revised + ( :on 900813,discovered That Instrument 2TIS-10980 Used for Verifying Refueling Water Storage Tank Temp Not Indicating.Caused by Procedural Inadequacy. Procedures Revised )
- 05000295/LER-1990-017-01, :on 900813,turbine Bearing Lift Oil Pumps Tripped.Caused by Personnel Error.Event Tailgated W/All Operations & Maint Personnel,W/Emphasis on Importance of Employing Self Check Process + ( :on 900813,turbine Bearing Lift Oil Pumps Tripped.Caused by Personnel Error.Event Tailgated W/All Operations & Maint Personnel,W/Emphasis on Importance of Employing Self Check Process )
- 05000272/LER-1990-028-01, :on 900814,Tech Spec 3.0.3 Entered Due to More than One Arpi Per Bank Inoperable.Caused by Sys Design.Sys Presently Under Consideration for Upgrade to Eliminate Temp Susceptibility of Coils + ( :on 900814,Tech Spec 3.0.3 Entered Due to More than One Arpi Per Bank Inoperable.Caused by Sys Design.Sys Presently Under Consideration for Upgrade to Eliminate Temp Susceptibility of Coils )
- 05000327/LER-1990-015, :on 900814,limiting Condition for Operation Entered When Two Pressure Channels Declared Inoperable. Caused by Planned Maint Activities.Channel Calibr Performed on 1-LT-68-320 + ( :on 900814,limiting Condition for Operation Entered When Two Pressure Channels Declared Inoperable. Caused by Planned Maint Activities.Channel Calibr Performed on 1-LT-68-320 )
- 05000254/LER-1990-019-01, :on 900814,missed Tech Spec Surveillance on Main Steam Radiation Monitors Due to Operator Misjudgement + ( :on 900814,missed Tech Spec Surveillance on Main Steam Radiation Monitors Due to Operator Misjudgement )
- 05000528/LER-1990-006-02, :on 900814,reactor Trip Occurred Following Manual Turbine Trip & Phase B of Main Transformer Loosing Forced Cooling.Caused by Failure of Control Power Transformer.Transformer Replaced + ( :on 900814,reactor Trip Occurred Following Manual Turbine Trip & Phase B of Main Transformer Loosing Forced Cooling.Caused by Failure of Control Power Transformer.Transformer Replaced )
- 05000440/LER-1990-017, :on 900814,thermal Power Exceeded Authorized Limits Due to Feedwater Heater Level Control Failure.Caused by Component Failure W/Contributing Procedural Deficiency. Off Normal Instruction Enhanced + ( :on 900814,thermal Power Exceeded Authorized Limits Due to Feedwater Heater Level Control Failure.Caused by Component Failure W/Contributing Procedural Deficiency. Off Normal Instruction Enhanced )
- 05000352/LER-1990-016-01, :on 900815,Tech Spec Limiting Condition for Operation Action Not Implemented within Required Time Period Due to Firewatch Employee Failure to Perform Surveillance Procedure.Caused by Personnel Falsifying Tests + ( :on 900815,Tech Spec Limiting Condition for Operation Action Not Implemented within Required Time Period Due to Firewatch Employee Failure to Perform Surveillance Procedure.Caused by Personnel Falsifying Tests )
- 05000370/LER-1990-007-03, :on 900815,Unit 2 Forced to Shut Down Due to Unidentified Reactor Coolant Leak.Cause Unknown.Leakage from Valve 2NI-458 Secured & on 900817 Unit 2 Entered Mode 1. Evaluation Underway to Prevent Recurrence + ( :on 900815,Unit 2 Forced to Shut Down Due to Unidentified Reactor Coolant Leak.Cause Unknown.Leakage from Valve 2NI-458 Secured & on 900817 Unit 2 Entered Mode 1. Evaluation Underway to Prevent Recurrence )