| | | Reporting criterion |
|---|
| 05000341/LER-1985-001, :on 850328 & 31,reactor Protection Sys Div 1 Power Loss Occurred,Resulting in Reactor Scram.Caused by Ground Fault at Breaker A6.Breaker Replaced & Duct Leak Repaired W/Temporary Seal |
- on 850328 & 31,reactor Protection Sys Div 1 Power Loss Occurred,Resulting in Reactor Scram.Caused by Ground Fault at Breaker A6.Breaker Replaced & Duct Leak Repaired W/Temporary Seal
| |
| 05000341/LER-1985-002, :on 850328 & 31,loss of Power to Sys Svc Transformer Occurred,Resulting in Half Scram Signal & Isolation of Reactor Water Cleanup Sys.Caused by Ground Fault at Breaker A6.Duct Leak Repaired |
- on 850328 & 31,loss of Power to Sys Svc Transformer Occurred,Resulting in Half Scram Signal & Isolation of Reactor Water Cleanup Sys.Caused by Ground Fault at Breaker A6.Duct Leak Repaired
| |
| 05000341/LER-1985-003, :on 850403,after Calibr of Div II 48/24-volt Dc Battery Charger B-1,no Output Current Observed.Low Voltage Alarm Ignored Based on Belief That Problem Involved Spare Charger.Cause Unknown |
- on 850403,after Calibr of Div II 48/24-volt Dc Battery Charger B-1,no Output Current Observed.Low Voltage Alarm Ignored Based on Belief That Problem Involved Spare Charger.Cause Unknown
| |
| 05000341/LER-1985-004, :on 850402,fire-rated Assembly Floor Plug & CO2 Suppression Sys Boundary Removed & Fire Watch Not Initiated within 1 H.Caused by Personnel Ignorance of Requirements & Unposted Floor Plugs |
- on 850402,fire-rated Assembly Floor Plug & CO2 Suppression Sys Boundary Removed & Fire Watch Not Initiated within 1 H.Caused by Personnel Ignorance of Requirements & Unposted Floor Plugs
| |
| 05000341/LER-1985-005, :on 850408,while Restarting Reactor Vessel Water Level Instrument to Svc Following Calibr,Full Scram Signal Generated.Caused by Erroneous Reactor Vessel Water Level Signal Due to Pressure Transient |
- on 850408,while Restarting Reactor Vessel Water Level Instrument to Svc Following Calibr,Full Scram Signal Generated.Caused by Erroneous Reactor Vessel Water Level Signal Due to Pressure Transient
| |
| 05000341/LER-1985-006, :on 850407,standby Gas Treatment Sys Div 1 & Associated Carbon Dioxide Fire Protection Sys Inoperable. Caused by Failure to Align Both Sys After Minor Mods. Procedure Revised |
- on 850407,standby Gas Treatment Sys Div 1 & Associated Carbon Dioxide Fire Protection Sys Inoperable. Caused by Failure to Align Both Sys After Minor Mods. Procedure Revised
| |
| 05000341/LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written |
- on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written
| |
| 05000341/LER-1985-008, :on 850425,reactor Protection Sys Actuated Twice.Caused by False Upscale Trip Due to Bumping of Intermediate Range Monitor Cables.First Control Rod Valved Out.Second Control Rod Inserted Fully |
- on 850425,reactor Protection Sys Actuated Twice.Caused by False Upscale Trip Due to Bumping of Intermediate Range Monitor Cables.First Control Rod Valved Out.Second Control Rod Inserted Fully
| |
| 05000341/LER-1985-009, :on 850426,CRD Friction Testing Performed W/O Reactor Protection Sys Shorting Links Being Removed,Per Tech Specs.Shorting Links Removed & Testing Continued.Tech Spec Change Will Be Requested |
- on 850426,CRD Friction Testing Performed W/O Reactor Protection Sys Shorting Links Being Removed,Per Tech Specs.Shorting Links Removed & Testing Continued.Tech Spec Change Will Be Requested
| |
| 05000341/LER-1985-010, :on 850427,reactor Protection Sys Tripped. Caused by APRM E Upscale Trip Due to Recorder Door Malfunction.Lprm Cables & Connectors Repaired & Chart Recorder Door Modified |
- on 850427,reactor Protection Sys Tripped. Caused by APRM E Upscale Trip Due to Recorder Door Malfunction.Lprm Cables & Connectors Repaired & Chart Recorder Door Modified
| |
| 05000341/LER-1985-011, :on 850427,two Reactor Protection Sys Actuations Occurred from Source Range Monitor Upscale Trips. Caused by radio-frequency Signal from Test Equipment. Procedure Revised to Prevent Reoccurrence |
- on 850427,two Reactor Protection Sys Actuations Occurred from Source Range Monitor Upscale Trips. Caused by radio-frequency Signal from Test Equipment. Procedure Revised to Prevent Reoccurrence
| |
| 05000341/LER-1985-012, :on 850428,reactor Scrammed Twice During Installation of Reactor Protection Sys Shorting Links. Caused by Personnel Failure to Follow Written Procedures. Event Being Reviewed & Warning Signs Posted |
- on 850428,reactor Scrammed Twice During Installation of Reactor Protection Sys Shorting Links. Caused by Personnel Failure to Follow Written Procedures. Event Being Reviewed & Warning Signs Posted
| |
| 05000341/LER-1985-013, :on 850428,secondary Containment Integrity Not Established During Core Alterations for CRD Friction Test. Caused by Personnel Misunderstanding Applicability of Requirement.Procedure Change Initiated |
- on 850428,secondary Containment Integrity Not Established During Core Alterations for CRD Friction Test. Caused by Personnel Misunderstanding Applicability of Requirement.Procedure Change Initiated
| |
| 05000341/LER-1985-014, :on 850501,reactor Protection Sys Actuation Occurred on Erroneous Indication at Reactor Vessel Level 3, Resulting in Full Scram & Isolation Signal for Valve Groups 4,13 & 15.Caused by Personnel Error |
- on 850501,reactor Protection Sys Actuation Occurred on Erroneous Indication at Reactor Vessel Level 3, Resulting in Full Scram & Isolation Signal for Valve Groups 4,13 & 15.Caused by Personnel Error
| |
| 05000341/LER-1985-015, :on 850506,during Restoration of Reactor Vessel Level Instrument to Svc,Full Scram Signal Generated. Caused by Erroneous Level Indication Due to Incorrect Valving Technique.Valve Training Continuing |
- on 850506,during Restoration of Reactor Vessel Level Instrument to Svc,Full Scram Signal Generated. Caused by Erroneous Level Indication Due to Incorrect Valving Technique.Valve Training Continuing
| |
| 05000341/LER-1985-016, :on 850509,scram & Several Primary Containment Isolations Occurred.Caused by Improper Valving on Reactor Water Level Instrument.Personnel Counseled.Permanent Installation Planned |
- on 850509,scram & Several Primary Containment Isolations Occurred.Caused by Improper Valving on Reactor Water Level Instrument.Personnel Counseled.Permanent Installation Planned
| |
| 05000341/LER-1985-018, :on 850523,monthly Diesel Fuel Sample & Analysis for Particulate Contamination Discovered 15 Days Overdue.Caused by Failure to Update Chemistry Sampling Schedule.Schedule Corrected |
- on 850523,monthly Diesel Fuel Sample & Analysis for Particulate Contamination Discovered 15 Days Overdue.Caused by Failure to Update Chemistry Sampling Schedule.Schedule Corrected
| |
| 05000341/LER-1985-019, :on 850524,control Ctr HVAC Sys Switched to Emergency Recirculation Mode During Testing of Turbine Bldg HVAC Exhaust Radiation Monitor.Caused by Momentary Loss of or Disturbance in AC Power to Monitor |
- on 850524,control Ctr HVAC Sys Switched to Emergency Recirculation Mode During Testing of Turbine Bldg HVAC Exhaust Radiation Monitor.Caused by Momentary Loss of or Disturbance in AC Power to Monitor
| |
| 05000341/LER-1985-020, :on 850604,discovery Made That Grab Samples of Reactor Bldg Ventilation Effluent Not Taken within 8 H of Failure of Reactor Bldg Ventilation Effluent Radiation Monitor.Caused by Personnel Error |
- on 850604,discovery Made That Grab Samples of Reactor Bldg Ventilation Effluent Not Taken within 8 H of Failure of Reactor Bldg Ventilation Effluent Radiation Monitor.Caused by Personnel Error
| |
| 05000341/LER-1985-021, :on 850607,reactor Protection Sys & ESF Actuations Occurred During Surveillance Testing of Reactor Vessel Pressure Instruments.Caused by Personnel Error. Procedure Revised |
- on 850607,reactor Protection Sys & ESF Actuations Occurred During Surveillance Testing of Reactor Vessel Pressure Instruments.Caused by Personnel Error. Procedure Revised
| |
| 05000341/LER-1985-022, :on 850606,reactor Protection Sys Actuated. Caused by Movement of Test Signal Cable,Causing Transient to Produce half-scram Signal on Trip Sys a While Signal on Trip Sys B Present.Testing Minimized |
- on 850606,reactor Protection Sys Actuated. Caused by Movement of Test Signal Cable,Causing Transient to Produce half-scram Signal on Trip Sys a While Signal on Trip Sys B Present.Testing Minimized
| |
| 05000341/LER-1985-023, :on 850610,reactor Bldg Closed Cooling Water Pressure Differential Control Valve Went to Full Open Position.Caused by Dirt on Valve Controller Flapper & Nozzle.Controller Cleaned & Retested |
- on 850610,reactor Bldg Closed Cooling Water Pressure Differential Control Valve Went to Full Open Position.Caused by Dirt on Valve Controller Flapper & Nozzle.Controller Cleaned & Retested
| |
| 05000341/LER-1985-024, :on 850622,during Operational Condition 2, Reactor Water Cleanup Sys Isolated.Caused by False High Differential Flow Signal Being Out of Calibr.Instrumentation Recalibr |
- on 850622,during Operational Condition 2, Reactor Water Cleanup Sys Isolated.Caused by False High Differential Flow Signal Being Out of Calibr.Instrumentation Recalibr
| |
| 05000341/LER-1985-025, :on 850614,reactor Water Cleanup Sys Isolated W/Plant in Operational Condition 4.Caused by Spurious Electrical Signals Associated W/Steam Leak Detection Fuse Reinstallation.Circuitry Delay in Design Stage |
- on 850614,reactor Water Cleanup Sys Isolated W/Plant in Operational Condition 4.Caused by Spurious Electrical Signals Associated W/Steam Leak Detection Fuse Reinstallation.Circuitry Delay in Design Stage
| |
| 05000341/LER-1985-026, :on 850615,emergency Equipment Cooling Water Sys Automatically Initiated When Third Pump Started.Caused by Bypass Valve Overshoot.Operating Procedure Revised to Place Sys in Override Prior to Switching Pumps |
- on 850615,emergency Equipment Cooling Water Sys Automatically Initiated When Third Pump Started.Caused by Bypass Valve Overshoot.Operating Procedure Revised to Place Sys in Override Prior to Switching Pumps
| |
| 05000341/LER-1985-027, :on 850617,outboard Primary Containment Isolation Valve G33F004 of Reactor Water Cleanup Sys Closed Causing Both Pumps to Trip.Cause Not Found.Valve Isolation Logic Reset |
- on 850617,outboard Primary Containment Isolation Valve G33F004 of Reactor Water Cleanup Sys Closed Causing Both Pumps to Trip.Cause Not Found.Valve Isolation Logic Reset
| |
| 05000341/LER-1985-028, :on 850627,Div I Reactor Water Cleanup Sys Inboard Isolation Valve Closed & Cleanup Sys Pumps Tripped. Caused by Spurious Steam Leak Detection Signal.Isolation Reset & Pumps Restarted |
- on 850627,Div I Reactor Water Cleanup Sys Inboard Isolation Valve Closed & Cleanup Sys Pumps Tripped. Caused by Spurious Steam Leak Detection Signal.Isolation Reset & Pumps Restarted
| |
| 05000341/LER-1985-029, :on 850628,reactor Manually Scrammed in Response to Trip of Running CRD Pump.Caused by CRD Pump Trip Due to Low Suction Pressure Transient Occurring When Torus Water Mgt Sys Valve Opened |
- on 850628,reactor Manually Scrammed in Response to Trip of Running CRD Pump.Caused by CRD Pump Trip Due to Low Suction Pressure Transient Occurring When Torus Water Mgt Sys Valve Opened
| |
| 05000341/LER-1985-030, :on 850701,at 2% Power,Reactor Scram Occurred. Caused by Procedural Error Resulting in Spurious Water Level 3 Signal Generation.Instrumentation & Control Technician Training Enhanced to Prevent Recurrence |
- on 850701,at 2% Power,Reactor Scram Occurred. Caused by Procedural Error Resulting in Spurious Water Level 3 Signal Generation.Instrumentation & Control Technician Training Enhanced to Prevent Recurrence
| |
| 05000341/LER-1985-031, :on 850703,outboard Isolation Valve of Reactor Water Cleanup Sys Closed.Caused by Spurious High Differential Temp Indication from Steam Leak Detection Circuitry.Isolation Reset & Sys Restarted |
- on 850703,outboard Isolation Valve of Reactor Water Cleanup Sys Closed.Caused by Spurious High Differential Temp Indication from Steam Leak Detection Circuitry.Isolation Reset & Sys Restarted
| |
| 05000341/LER-1985-032, :on 850704,inboard & Outboard Primary Containment Isolation Valves for Reactor Water Cleanup (RWCU) Sys Left Open W/Flow to RWCU Pumps & Breakers Deenergized.Caused by Personnel Error |
- on 850704,inboard & Outboard Primary Containment Isolation Valves for Reactor Water Cleanup (RWCU) Sys Left Open W/Flow to RWCU Pumps & Breakers Deenergized.Caused by Personnel Error
| |
| 05000341/LER-1985-034, :on 850706,reactor Water Cleanup Sys Inboard & Outboard Primary Containment Isolation Valves Closed.Caused by Inadequate Instrument Loop Calibr Procedure.Procedure Revised.Loop Recalibr |
- on 850706,reactor Water Cleanup Sys Inboard & Outboard Primary Containment Isolation Valves Closed.Caused by Inadequate Instrument Loop Calibr Procedure.Procedure Revised.Loop Recalibr
| |
| 05000341/LER-1985-035, :on 850709,reactor Scram Occurred Due to Actual Reactor Water Level 3 Condition.Caused by Operator Not Recognizing Water Level Decrease & Failing to Respond to Alarm.Shift Supervisors Counseled |
- on 850709,reactor Scram Occurred Due to Actual Reactor Water Level 3 Condition.Caused by Operator Not Recognizing Water Level Decrease & Failing to Respond to Alarm.Shift Supervisors Counseled
| |
| 05000341/LER-1985-036, :on 850710,inboard & Outboard Primary Containment Isolation Valves Opened & Deenergized,Violating Tech Spec 3.6.3.Caused by Personnel Oversight.Event Discussed & Surveillance Procedures Altered |
- on 850710,inboard & Outboard Primary Containment Isolation Valves Opened & Deenergized,Violating Tech Spec 3.6.3.Caused by Personnel Oversight.Event Discussed & Surveillance Procedures Altered
| |
| 05000341/LER-1985-037, :on 850711,surveillance Channel Check for Four Isolation Actuation Instruments Required by Tech Spec 4.3.2.1-1 Inadvertently Missed.Caused by Procedural Deficiency.Procedure Reviewed & Revised |
- on 850711,surveillance Channel Check for Four Isolation Actuation Instruments Required by Tech Spec 4.3.2.1-1 Inadvertently Missed.Caused by Procedural Deficiency.Procedure Reviewed & Revised
| |
| 05000341/LER-1985-038, :on 850713,HPCI/RCIC Surveillance Tests Not Performed within 12 H Time Limit Prescribed by Tech Specs. Caused by Omission of Tests in General Operating Procedures. Procedural Deficiencies Corrected |
- on 850713,HPCI/RCIC Surveillance Tests Not Performed within 12 H Time Limit Prescribed by Tech Specs. Caused by Omission of Tests in General Operating Procedures. Procedural Deficiencies Corrected
| |
| 05000341/LER-1985-039, :on 850716,after Starting HPCI Sys to Perform Startup Test,Oil Leak Developed at Operator of Turbine Stop Valve.Caused by Loose Flange Between Pilot Valve Assembly & Valve Operator.Flange Bolts Tightened |
- on 850716,after Starting HPCI Sys to Perform Startup Test,Oil Leak Developed at Operator of Turbine Stop Valve.Caused by Loose Flange Between Pilot Valve Assembly & Valve Operator.Flange Bolts Tightened
| |
| 05000341/LER-1985-040, :on 850720,error Discovered in Surveillance Procedure While Performing Channel Function Test on Reactor Water Cleanup Sys Differential Flow Instrumentation.Caused by Omitted Procedure Rev.Procedure Modified |
- on 850720,error Discovered in Surveillance Procedure While Performing Channel Function Test on Reactor Water Cleanup Sys Differential Flow Instrumentation.Caused by Omitted Procedure Rev.Procedure Modified
| |
| 05000341/LER-1985-042, :on 850722,emergency Equipment Cooling & Svc Water Sys Automatically Started in Response to Low Differential Pressure Condition.Cause Undetermined |
- on 850722,emergency Equipment Cooling & Svc Water Sys Automatically Started in Response to Low Differential Pressure Condition.Cause Undetermined
| |
| 05000341/LER-1985-043, :on 850724,Div 1 Core Spray Mode Inoperable Due to Deenergization of RCIC Room Cooler T41-B021. Caused by Cooler Room Control Switch in Off Position. Cooler Returned to Normal |
- on 850724,Div 1 Core Spray Mode Inoperable Due to Deenergization of RCIC Room Cooler T41-B021. Caused by Cooler Room Control Switch in Off Position. Cooler Returned to Normal
| |
| 05000341/LER-1985-044, :on 850726,Div II Control Ctr HVAC Supply Fan Shut Down for Insp.Fan Not Returned to Svc Until 2 Days After Expiration of 7-day Limiting Condition for Operation Due to Failure to Log Condition |
- on 850726,Div II Control Ctr HVAC Supply Fan Shut Down for Insp.Fan Not Returned to Svc Until 2 Days After Expiration of 7-day Limiting Condition for Operation Due to Failure to Log Condition
| |
| 05000341/LER-1985-045, :on 850727,reactor Bldg HVAC Sys Tripped.Caused by Erratic Operation of Freezestat T41-N054B.Freezestat Switch Replaced w/like-for-like Switch |
- on 850727,reactor Bldg HVAC Sys Tripped.Caused by Erratic Operation of Freezestat T41-N054B.Freezestat Switch Replaced w/like-for-like Switch
| |
| 05000341/LER-1985-046, :on 850813,reactor Water Cleanup Sys Isolated Due to High Differential Flow Signal.Caused by Effects of Changing Condenser Back Pressure.Flow Limited to 30 Gpm Max Until Basis for Calibr Reevaluated |
- on 850813,reactor Water Cleanup Sys Isolated Due to High Differential Flow Signal.Caused by Effects of Changing Condenser Back Pressure.Flow Limited to 30 Gpm Max Until Basis for Calibr Reevaluated
| |
| 05000341/LER-1985-047, :on 850729,valves Closed Causing Div I ECCS & Emergency Diesel Generators to Become Inoperable.Caused by Operator Error.No Corrective Action Required |
- on 850729,valves Closed Causing Div I ECCS & Emergency Diesel Generators to Become Inoperable.Caused by Operator Error.No Corrective Action Required
| |
| 05000341/LER-1985-048, :on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised |
- on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised
| |
| 05000341/LER-1985-049, :on 850814,Div 2 Emergency Diesel Generator 13 Automatically Started.Caused by Electrical Technician Inadvertently Shorting Adjacent Terminals,In Turn Shorting Generator Contact Wires.Procedures Revised |
- on 850814,Div 2 Emergency Diesel Generator 13 Automatically Started.Caused by Electrical Technician Inadvertently Shorting Adjacent Terminals,In Turn Shorting Generator Contact Wires.Procedures Revised
| |
| 05000341/LER-1985-050, :on 850814,reactor Water Cleanup Sys Isolated. Caused by Spurious Actuation of Temp Switches in Reactor Water Cleanup Sys Steam Leak Detection Sys.Engineering Evaluating Sys to Prepare Design Change |
- on 850814,reactor Water Cleanup Sys Isolated. Caused by Spurious Actuation of Temp Switches in Reactor Water Cleanup Sys Steam Leak Detection Sys.Engineering Evaluating Sys to Prepare Design Change
| |
| 05000341/LER-1985-052, :on 850818,Div II Reactor Bldg Pressure High/ Low Plan Received.Caused by Reactor Bldg Supply Airflow Being Too High.Airflow Reduced & Div II of Standby Gas Treatment Initiated to Restore Pressure |
- on 850818,Div II Reactor Bldg Pressure High/ Low Plan Received.Caused by Reactor Bldg Supply Airflow Being Too High.Airflow Reduced & Div II of Standby Gas Treatment Initiated to Restore Pressure
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000341/LER-1985-053, :on 850824,ESF Actuated When Instrument Repairman Inadvertently Shorted 120 Volt Ac Power Supply. Caused by Repairman Error in Choosing Wrong Size Screwdriver.Fuse Replaced |
- on 850824,ESF Actuated When Instrument Repairman Inadvertently Shorted 120 Volt Ac Power Supply. Caused by Repairman Error in Choosing Wrong Size Screwdriver.Fuse Replaced
| |
| 05000341/LER-1985-054, :on 850827,HPCI Sys Isolated.Caused by Personnel Selecting Wrong Module Inside Panel.Diagrams Showing Locations & Identification of Switch Modules from Rear or Panel Added to Surveillance Procedures |
- on 850827,HPCI Sys Isolated.Caused by Personnel Selecting Wrong Module Inside Panel.Diagrams Showing Locations & Identification of Switch Modules from Rear or Panel Added to Surveillance Procedures
| |