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| 05000220/LER-1985-001, :on 850123,24 & 0207,automatic Initiations of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Ventilation Duct Radiation Monitor 11.Sensor Converter Replaced |
- on 850123,24 & 0207,automatic Initiations of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Ventilation Duct Radiation Monitor 11.Sensor Converter Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-002, :on 850214,auxiliary Control Room Fire Suppression Sys Inoperable.Caused by Inoperable Fire Dampers.Fire Dampers Repaired & Tested.Personnel Instructed in Tech Spec Requirements |
- on 850214,auxiliary Control Room Fire Suppression Sys Inoperable.Caused by Inoperable Fire Dampers.Fire Dampers Repaired & Tested.Personnel Instructed in Tech Spec Requirements
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| 05000220/LER-1985-003, On 850304,reactor Scram Initiated.Caused by Technicians Trying to Rectify Error Condition in Transmitter During Monthly Surveillance.Procedure Revised to Caution Technicians on Effects of Errors | On 850304,reactor Scram Initiated.Caused by Technicians Trying to Rectify Error Condition in Transmitter During Monthly Surveillance.Procedure Revised to Caution Technicians on Effects of Errors | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-004, :on 850304,during Shutdown,Turbine Trip Signal Led to HPCI Initiation.Caused by High Reactor Water Level.Level Control Adjusted.Water Level Returned to Normal |
- on 850304,during Shutdown,Turbine Trip Signal Led to HPCI Initiation.Caused by High Reactor Water Level.Level Control Adjusted.Water Level Returned to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-005, :on 850416,reactor Scram Occurred Due to APRM High Flux Level.Caused by Partial Closing of Turbine Control Valves Due to Disturbance in Turbine Control Sys.Work Requests Issued to Troubleshoot Sys |
- on 850416,reactor Scram Occurred Due to APRM High Flux Level.Caused by Partial Closing of Turbine Control Valves Due to Disturbance in Turbine Control Sys.Work Requests Issued to Troubleshoot Sys
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| 05000220/LER-1985-006, :on 850419,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Reactor Bldg Ventilation Duct Monitor 11.Sys Checked & Source Calibr.Sys Returned to Svc |
- on 850419,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Reactor Bldg Ventilation Duct Monitor 11.Sys Checked & Source Calibr.Sys Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-007, :on 850424,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Technician Shorting Wire in Cable Connector to Sensor for Emergency Condensor Ventilation Monitor 121 |
- on 850424,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Technician Shorting Wire in Cable Connector to Sensor for Emergency Condensor Ventilation Monitor 121
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| 05000220/LER-1985-008-01, :on 850610,discovered That Temporary Jumper Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit.Cause Unstated.Review Completed.New Procedure to Ensure Timely Reviews Implemented |
- on 850610,discovered That Temporary Jumper Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit.Cause Unstated.Review Completed.New Procedure to Ensure Timely Reviews Implemented
| 10 CFR 50.73(a)(2)(i) |
| 05000220/LER-1985-008, Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C | Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C | 10 CFR 50.73(a)(2)(i) |
| 05000220/LER-1985-009, :on 850522 & 31,discovered Instrument Channel Tests Not Performed on Three of Four Emergency Condenser Sys Noble Gas Activity & Suppression Chamber Water Level Monitors.Cause Unknown.Tests Performed |
- on 850522 & 31,discovered Instrument Channel Tests Not Performed on Three of Four Emergency Condenser Sys Noble Gas Activity & Suppression Chamber Water Level Monitors.Cause Unknown.Tests Performed
| 10 CFR 50.73(a)(2)(1) |
| 05000220/LER-1985-010, :on 850815,accidental Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Electrical Spike Experienced by Channel 12 Reactor Bldg Ventilation Duct Monitor.Ventilation Sys Reset |
- on 850815,accidental Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Electrical Spike Experienced by Channel 12 Reactor Bldg Ventilation Duct Monitor.Ventilation Sys Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-011, :on 850610,review Revealed That Radiological Habitability of Technical Support Ctr (TSC) Not Consistent w/NUREG-0737,Suppl 1.Cause Unstated.Tsc Being Relocated to Better Location Re Radiation Shielding |
- on 850610,review Revealed That Radiological Habitability of Technical Support Ctr (TSC) Not Consistent w/NUREG-0737,Suppl 1.Cause Unstated.Tsc Being Relocated to Better Location Re Radiation Shielding
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| 05000220/LER-1985-012, :on 850916,reactor Cleanup Sys Isolated Due to High Area Temp.Caused by Steam Leaking from Gland Packing on 1-inch Vent Valve from Cleanup Nonregenerative Hx.Leak Repaired |
- on 850916,reactor Cleanup Sys Isolated Due to High Area Temp.Caused by Steam Leaking from Gland Packing on 1-inch Vent Valve from Cleanup Nonregenerative Hx.Leak Repaired
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| 05000220/LER-1985-013, :on 850621 & 25,automatic Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Spurious Upscale Deflection of Control Room Vent Monitor Due to Line Noise.Involved Monitors Recalibr |
- on 850621 & 25,automatic Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Spurious Upscale Deflection of Control Room Vent Monitor Due to Line Noise.Involved Monitors Recalibr
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| 05000220/LER-1985-014, :on 850819,during Surveillance Insp,Maint Electrician Inadvertently Grounded Main Generator Excitation Sys Amplidyne Motor Generator Set,Causing Main Generator & Turbine Trips & Reactor Scram |
- on 850819,during Surveillance Insp,Maint Electrician Inadvertently Grounded Main Generator Excitation Sys Amplidyne Motor Generator Set,Causing Main Generator & Turbine Trips & Reactor Scram
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| 05000220/LER-1985-015, :on 850911,personnel Informed of Three Instances of Cable Routing Discrepancies.Operators Informed. Mods Designed & Will Be Installed in Timely Manner |
- on 850911,personnel Informed of Three Instances of Cable Routing Discrepancies.Operators Informed. Mods Designed & Will Be Installed in Timely Manner
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| 05000220/LER-1985-016, :on 850927,three Normally Open Dampers Failed to Isolate on Halon Suppression Signal.Caused by Interruption to Initiation Circuit Due to Wiring Change on 850918.Wiring Corrected |
- on 850927,three Normally Open Dampers Failed to Isolate on Halon Suppression Signal.Caused by Interruption to Initiation Circuit Due to Wiring Change on 850918.Wiring Corrected
| 10 CFR 50.73(a)(2) |
| 05000220/LER-1985-017, :on 850823,reactor Scram Initiated Due to Reactor Low Water Level.Caused by Detached Range Spring & Lock Screw in Valve Positioner Closing Valve on Feedwater Pump 11.Lock Screw & Addl Hardware Replaced |
- on 850823,reactor Scram Initiated Due to Reactor Low Water Level.Caused by Detached Range Spring & Lock Screw in Valve Positioner Closing Valve on Feedwater Pump 11.Lock Screw & Addl Hardware Replaced
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| 05000220/LER-1985-018, :on 851010,low Air Pressure Start Test of Tech Spec Section 4.6.7.b.4 Failed.Caused by Need to Energize or Manually Bypass Solenoids on Governor Sys.Mods to Governor Sys & Sys Manual Start Performed |
- on 851010,low Air Pressure Start Test of Tech Spec Section 4.6.7.b.4 Failed.Caused by Need to Energize or Manually Bypass Solenoids on Governor Sys.Mods to Governor Sys & Sys Manual Start Performed
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| 05000220/LER-1985-019, :on 851015,discovered Emergency Isolation Dc Motor Operated Valves 39-07 & 39-08 Might Not Close within 38 During Accident.Possibly Caused by Incorrectly Sized Electric Supply Cables.Cables Replaced |
- on 851015,discovered Emergency Isolation Dc Motor Operated Valves 39-07 & 39-08 Might Not Close within 38 During Accident.Possibly Caused by Incorrectly Sized Electric Supply Cables.Cables Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000220/LER-1985-020, :on 851030,momentary Loss of Output Power from Uninterruptible Power Supply Motor Generator Set 162 Experienced.Caused by Generator Undervoltage Relay Sensing Spurious Undervoltage |
- on 851030,momentary Loss of Output Power from Uninterruptible Power Supply Motor Generator Set 162 Experienced.Caused by Generator Undervoltage Relay Sensing Spurious Undervoltage
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| 05000220/LER-1985-021, :on 851101,during Normal Operation,Feedwater Flow Control Valve 12 Malfunctioned Causing 95-inch Reactor Water Level Condition.Caused by Problem W/Instrument Air Sys |
- on 851101,during Normal Operation,Feedwater Flow Control Valve 12 Malfunctioned Causing 95-inch Reactor Water Level Condition.Caused by Problem W/Instrument Air Sys
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| 05000220/LER-1985-022, :on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be Inspected |
- on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-023, :on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater Flow |
- on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater Flow
| 10 CFR 50.73(a)(2) |
| 05000220/LER-1985-024, :on 851212,turbine Trip & Subsequent HPCI Mode of Feedwater Initiation Occurred.Caused by Difference Between Level Indications Due to Different Indicator Mfg. Water Level Lowered & HPCI Reset |
- on 851212,turbine Trip & Subsequent HPCI Mode of Feedwater Initiation Occurred.Caused by Difference Between Level Indications Due to Different Indicator Mfg. Water Level Lowered & HPCI Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000220/LER-1985-025, :on 851215,reactor Power Reduction Initiated Due to Inability to Monitor Specified Core Thermal Parameters.Caused by Plant Process Computer Failure. Reactor Power Restored |
- on 851215,reactor Power Reduction Initiated Due to Inability to Monitor Specified Core Thermal Parameters.Caused by Plant Process Computer Failure. Reactor Power Restored
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |