| | | Reporting criterion |
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| 05000250/LER-1988-001, :on 880113,unit Experienced Turbine Runback Due to Dropped Control Rod Assembly & Manual Subcritical Reactor Trip Occurred When Addl Control Rods Dropped Into Core. Caused by Personnel Error.Personnel Counseled |
- on 880113,unit Experienced Turbine Runback Due to Dropped Control Rod Assembly & Manual Subcritical Reactor Trip Occurred When Addl Control Rods Dropped Into Core. Caused by Personnel Error.Personnel Counseled
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| 05000251/LER-1988-001-01, :on 880129,operability Requirements of Tech Spec 3.5.1 for Steam Generator lo-lo Level Reactor Could Not Be Met.Caused by Procedural Error.Setpoints of Affected Channels Rechecked,Calibr & Procedure Revised |
- on 880129,operability Requirements of Tech Spec 3.5.1 for Steam Generator lo-lo Level Reactor Could Not Be Met.Caused by Procedural Error.Setpoints of Affected Channels Rechecked,Calibr & Procedure Revised
| 10 CFR 50.73(a)(2) |
| 05000251/LER-1988-002-01, :on 880202,containment & Control Room Ventilation Isolation Occurred.Caused by Personnel Error While Performing Mod to Remove Remote Alarm Function.Planner & Technician Involved Counselled |
- on 880202,containment & Control Room Ventilation Isolation Occurred.Caused by Personnel Error While Performing Mod to Remove Remote Alarm Function.Planner & Technician Involved Counselled
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-002, :on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced |
- on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced
| 10 CFR 50.73(e)(2)(v) |
| 05000250/LER-1988-003, :on 880308,containment Ventilation & Control Room Ventilation Isolation Occurred.Caused by Minor Electrical Transient Upon Failure of One Light Filament. Failed Dual Filament Bulb Replaced |
- on 880308,containment Ventilation & Control Room Ventilation Isolation Occurred.Caused by Minor Electrical Transient Upon Failure of One Light Filament. Failed Dual Filament Bulb Replaced
| 10 CFR 50.73(e)(2) |
| 05000251/LER-1988-003-01, :on 880207,shutdown of Unit from 100% Power Commenced Due to Exceeding Requirements of Tech Spec for Having Battery Charger 4S Out of Svc.Caused by Failure of Snubber Capacitor.Capacitor Replaced |
- on 880207,shutdown of Unit from 100% Power Commenced Due to Exceeding Requirements of Tech Spec for Having Battery Charger 4S Out of Svc.Caused by Failure of Snubber Capacitor.Capacitor Replaced
| 10 CFR 50.73(c)(2) |
| 05000250/LER-1988-004, :on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of Actions |
- on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of Actions
| 10 CFR 50.73(e)(2) |
| 05000251/LER-1988-004-02, :on 880408,Tech Spec Table 3.5-2 Requirements Exceeded.Caused by Failure of Relays 327TX/4A2 & 327TX/4A2 in Undervoltage Protection Scheme for 4A 480 Volt Load Ctr. Relays Replaced & Tested |
- on 880408,Tech Spec Table 3.5-2 Requirements Exceeded.Caused by Failure of Relays 327TX/4A2 & 327TX/4A2 in Undervoltage Protection Scheme for 4A 480 Volt Load Ctr. Relays Replaced & Tested
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| 05000251/LER-1988-004-03, :on 880408,Tech Spec 3.5-2,Item 3.2.b Exceeded. Caused by Failure of Relays in Undervoltage Protection Scheme.Relays Replaced & Satisfactorily Tested Before Unit Shutdown Commenced |
- on 880408,Tech Spec 3.5-2,Item 3.2.b Exceeded. Caused by Failure of Relays in Undervoltage Protection Scheme.Relays Replaced & Satisfactorily Tested Before Unit Shutdown Commenced
| 10 CFR 50.73(e)(2)(iv) |
| 05000251/LER-1988-004, Forwards Corrected LER 88-004,correcting Event Date in Block 5 of Rept Form as Submitted W/Util | Forwards Corrected LER 88-004,correcting Event Date in Block 5 of Rept Form as Submitted W/Util | |
| 05000251/LER-1988-005-01, :on 880425,calibr of Nuclear Instrumentation Sys Power Range Detectors Performed Late.Caused by Personnel Error.Digital Data Processing Sys Repaired & Group Responsible for Performance Discussed Event |
- on 880425,calibr of Nuclear Instrumentation Sys Power Range Detectors Performed Late.Caused by Personnel Error.Digital Data Processing Sys Repaired & Group Responsible for Performance Discussed Event
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| 05000250/LER-1988-005, :on 880415,loss of Flowpath from Boric Acid Storage Tanks to RCS Occurred.Caused by Loose Screw in Motor/Pump Coupling.Boric Acid Transfer Pump 4A Realigned to Provide Boric Acid Flow Path to Unit 3 |
- on 880415,loss of Flowpath from Boric Acid Storage Tanks to RCS Occurred.Caused by Loose Screw in Motor/Pump Coupling.Boric Acid Transfer Pump 4A Realigned to Provide Boric Acid Flow Path to Unit 3
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| 05000251/LER-1988-006-01, :on 880716,containment Ventilation & Control Room Ventilation Sys Isolation Occurred.Caused by Very Conservative Setpoint for R-11 Actuation.Unit Removed from Operation & Temporary Repair Effected |
- on 880716,containment Ventilation & Control Room Ventilation Sys Isolation Occurred.Caused by Very Conservative Setpoint for R-11 Actuation.Unit Removed from Operation & Temporary Repair Effected
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-006, :on 880408,surveillance of Hydrogen & Oxygen Concentration of Inservice Gas Decay Tank Missed.Caused by Personnel Error.Surveillance Incorporated Into Chemistry Primary Daily Worksheet & Personnel Counseled |
- on 880408,surveillance of Hydrogen & Oxygen Concentration of Inservice Gas Decay Tank Missed.Caused by Personnel Error.Surveillance Incorporated Into Chemistry Primary Daily Worksheet & Personnel Counseled
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(ii) |
| 05000250/LER-1988-007, :on 880427,3A Intake Cooling Water (Icw) Pump out-of-svc Due to Discharge Pressure Gauge Piping Failure. Caused by Corrosion of Coupling Attaching Pressure Gauge Piping to Icw Discharge Pipe.Piping Repaired |
- on 880427,3A Intake Cooling Water (Icw) Pump out-of-svc Due to Discharge Pressure Gauge Piping Failure. Caused by Corrosion of Coupling Attaching Pressure Gauge Piping to Icw Discharge Pipe.Piping Repaired
| 10 CFR 50.73(e)(2)(vii) 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(ii) |
| 05000251/LER-1988-007-01, :on 880812,while Performing Corrective Maint, Subcritical Reactor Trip Occurred.Caused by Failure of Source Range Neutron Detector N-32.Post-trip Review Performed & Detector Replaced |
- on 880812,while Performing Corrective Maint, Subcritical Reactor Trip Occurred.Caused by Failure of Source Range Neutron Detector N-32.Post-trip Review Performed & Detector Replaced
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| 05000251/LER-1988-008-01, :on 880815,Phase a of Containment Isolation Train a Actuated.Caused by Wire Bundle Bouncing Contacts of Relay 4-SIA2.Actuation Signal Reset |
- on 880815,Phase a of Containment Isolation Train a Actuated.Caused by Wire Bundle Bouncing Contacts of Relay 4-SIA2.Actuation Signal Reset
| 10 CFR 50.73(s)(2)(i) 10 CFR 50.73(s)(2)(v) 10 CFR 50.73(s)(2) |
| 05000250/LER-1988-008, :on 880613,flowpath Which Could Result in Insufficient NPSH to Certain Pumps During LOCA Recirculation Identified.Procedures Revised to Maintain Valve 887 Locked in Fully Open Position |
- on 880613,flowpath Which Could Result in Insufficient NPSH to Certain Pumps During LOCA Recirculation Identified.Procedures Revised to Maintain Valve 887 Locked in Fully Open Position
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-009, :on 880527,determined That Tech Spec Surveillances for Station Battery Pilot Cell Rotation Not Properly Implemented in 1987.Caused by Personnel Error & Procedure Inadequacy.Training Bulletin Issued |
- on 880527,determined That Tech Spec Surveillances for Station Battery Pilot Cell Rotation Not Properly Implemented in 1987.Caused by Personnel Error & Procedure Inadequacy.Training Bulletin Issued
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| 05000251/LER-1988-009, :on 880816,steam Generator Feedwater Pump Tripped During Coating of Condensate Polisher Vessel 4B W/ Resin for Secondary Sys Startup.Caused by Failure of Differential Pressure Switch.Switch Replaced |
- on 880816,steam Generator Feedwater Pump Tripped During Coating of Condensate Polisher Vessel 4B W/ Resin for Secondary Sys Startup.Caused by Failure of Differential Pressure Switch.Switch Replaced
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| 05000251/LER-1988-010-01, :on 880819,reactor Trip Occurred Due to lo-lo Steam Generator B Level.Caused by Cognitive Personnel Error. Reactor Control Operator Counseled Re Procedural Compliance & Attention to Details |
- on 880819,reactor Trip Occurred Due to lo-lo Steam Generator B Level.Caused by Cognitive Personnel Error. Reactor Control Operator Counseled Re Procedural Compliance & Attention to Details
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-010, :on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced |
- on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced
| 10 CFR 50.73(s)(2) |
| 05000250/LER-1988-011, :on 880529,discovered That Diesel Oil Storage Tank Isolation Valve 70-003 Locked Closed.Caused by Personnel Error.Technician Disciplined & Info Bulletin Re Work Controls & Procedural Compliance Issued |
- on 880529,discovered That Diesel Oil Storage Tank Isolation Valve 70-003 Locked Closed.Caused by Personnel Error.Technician Disciplined & Info Bulletin Re Work Controls & Procedural Compliance Issued
| 10 CFR 50.73(e)(2) |
| 05000251/LER-1988-011-01, :on 880816,damage Occurred to Property in Excess of $2,000 Due to Spent Fuel Pool Leakage.Caused by Pump Failure Causing Vent Valve to Vibrate Open.Floor Drain Sys Cleaned.Pump & Oiler Repaired & Inspected |
- on 880816,damage Occurred to Property in Excess of $2,000 Due to Spent Fuel Pool Leakage.Caused by Pump Failure Causing Vent Valve to Vibrate Open.Floor Drain Sys Cleaned.Pump & Oiler Repaired & Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-012, :on 880614,QA Audit Caused Investigation Into Delay in Issuing Fire Protection Impairment Form for Four Penetration Seals in Switchgear Room.Caused by Inadequate Controls.Seal Surveillance Being Generated |
- on 880614,QA Audit Caused Investigation Into Delay in Issuing Fire Protection Impairment Form for Four Penetration Seals in Switchgear Room.Caused by Inadequate Controls.Seal Surveillance Being Generated
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| 05000251/LER-1988-012-01, :on 880905,control Rod K-12 Dropped from 228 Steps to 0 Step,Causing Turbine Runback to 60% Power.Cause of Drop Under Investigation.Insp of Control Rod K-12 Will Be Performed During Current Refueling Outage |
- on 880905,control Rod K-12 Dropped from 228 Steps to 0 Step,Causing Turbine Runback to 60% Power.Cause of Drop Under Investigation.Insp of Control Rod K-12 Will Be Performed During Current Refueling Outage
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1)(0) |
| 05000250/LER-1988-013, :on 880707,discovered That Monthly Channel Functional Test Surveillance Procedure Did Not Check Sys Alarm.Caused by Personnel Error.Surveillance Procedure Corrected & Personnel Counseled |
- on 880707,discovered That Monthly Channel Functional Test Surveillance Procedure Did Not Check Sys Alarm.Caused by Personnel Error.Surveillance Procedure Corrected & Personnel Counseled
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| 05000250/LER-1988-014, :on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements |
- on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-015, :on 880729,valves in Flow Path Between Hydrogen Monitors & Containment Bldg Not Verified in Proper Position. Caused by Inadequate Administrative Controls.Procedures Revised to Verify Valve Position |
- on 880729,valves in Flow Path Between Hydrogen Monitors & Containment Bldg Not Verified in Proper Position. Caused by Inadequate Administrative Controls.Procedures Revised to Verify Valve Position
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| 05000250/LER-1988-016, :on 880811,containment Spray Pump out-of-svc for Maint Exceeding Tech Specs Limits.Caused by Lack of Knowledge Re Need for break-in Period for New Bearings. Training Procedures to Be Revised |
- on 880811,containment Spray Pump out-of-svc for Maint Exceeding Tech Specs Limits.Caused by Lack of Knowledge Re Need for break-in Period for New Bearings. Training Procedures to Be Revised
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-017, :on 880815,control Room Ventilation Sys Out of Svc in Excess of Tech Spec Time Limit Due to Intermittent Circuit Failure.Caused by Procedural Deficiency.Bridge Circuit Replaced & Plant Mod in Effect |
- on 880815,control Room Ventilation Sys Out of Svc in Excess of Tech Spec Time Limit Due to Intermittent Circuit Failure.Caused by Procedural Deficiency.Bridge Circuit Replaced & Plant Mod in Effect
| 10 CFR 50.73(e)(1) |
| 05000250/LER-1988-018-06, :on 880822,determined That Refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of ECCS Sys.Caused by Procedure Inadequacy.Procedure Revised to Exclude Monthly Cycling of Tank Outlet Valves |
- on 880822,determined That Refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of ECCS Sys.Caused by Procedure Inadequacy.Procedure Revised to Exclude Monthly Cycling of Tank Outlet Valves
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-018, :on 880822,refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of Eccs,Including RHR, Containment Spray & Hpsi.Caused by Procedure Inadequacy. Procedures Revised to Exclude Monthly Cycling |
- on 880822,refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of Eccs,Including RHR, Containment Spray & Hpsi.Caused by Procedure Inadequacy. Procedures Revised to Exclude Monthly Cycling
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| 05000250/LER-1988-019, :on 880822,boric Acid Transfer Pump 3A Declared out-of-svc.Caused by Lack of Visible Water Level & Zero Nitrogen Pressure in Seal Pot & Failure of Pump Seal.Seal Replaced & Pump Returned to Svc |
- on 880822,boric Acid Transfer Pump 3A Declared out-of-svc.Caused by Lack of Visible Water Level & Zero Nitrogen Pressure in Seal Pot & Failure of Pump Seal.Seal Replaced & Pump Returned to Svc
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| 05000250/LER-1988-020, :on 880831,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Routine Test of Channel B Air Intake Radiation Monitor.Caused by Spurious Actuation Signal.Recirculation Mode Verified |
- on 880831,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Routine Test of Channel B Air Intake Radiation Monitor.Caused by Spurious Actuation Signal.Recirculation Mode Verified
| 10 CFR 50.73(s)(2) |
| 05000250/LER-1988-021, :on 880913,pressurizer PORV Stroke Time Exceeded Tech Spec Design Basis Value of 3.0 for Heat Input Case.Caused by Undersized Air & Nitrogen Backup Supply Line to Actuators.Procedures Revised |
- on 880913,pressurizer PORV Stroke Time Exceeded Tech Spec Design Basis Value of 3.0 for Heat Input Case.Caused by Undersized Air & Nitrogen Backup Supply Line to Actuators.Procedures Revised
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| 05000250/LER-1988-022, :on 880920,emergency Diesel Generator a Declared out-of-svc Due to High Fuel Oil Pressure.Diesel Generator B out-of-svc Since 880917.Caused by Excessive Particles in Filter.Filter Replaced |
- on 880920,emergency Diesel Generator a Declared out-of-svc Due to High Fuel Oil Pressure.Diesel Generator B out-of-svc Since 880917.Caused by Excessive Particles in Filter.Filter Replaced
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(x)(2) |
| 05000250/LER-1988-023, :on 880926,chemistry Technician Reported That There Was No Flow Indication to Plant Process Radiation Monitor R-19.Caused by Solids from Steam Generator Blowdown. Sample Flows to R-19 Will Be Monitored |
- on 880926,chemistry Technician Reported That There Was No Flow Indication to Plant Process Radiation Monitor R-19.Caused by Solids from Steam Generator Blowdown. Sample Flows to R-19 Will Be Monitored
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| 05000250/LER-1988-024, :on 881001,RHR Pump Declared Out Svc Due to Leakage from Pump Seal.Cause Not Identified.Seal Cooler Flushed Prior to Reassembly to Remove Foreign Matl & Installation Technique Revised |
- on 881001,RHR Pump Declared Out Svc Due to Leakage from Pump Seal.Cause Not Identified.Seal Cooler Flushed Prior to Reassembly to Remove Foreign Matl & Installation Technique Revised
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| 05000250/LER-1988-025, :on 881013,determined That Potential Interaction Existed Between Emergency Diesel Generator Pump Control Sys Which Could Have Prevented Fulfillment of Safety Function.Caused by Inadequate Design |
- on 881013,determined That Potential Interaction Existed Between Emergency Diesel Generator Pump Control Sys Which Could Have Prevented Fulfillment of Safety Function.Caused by Inadequate Design
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-026, :on 881107,unit Violated FSAR Design Requirements Re Hurricane Flood Protection |
- on 881107,unit Violated FSAR Design Requirements Re Hurricane Flood Protection
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| 05000250/LER-1988-027, :on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped |
- on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-028, :on 881117,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Test of Channel B Air Intake Radiation Monitor RAI 6642.Caused by Maladjustment of Monitor During Calibr.Instruction Revised |
- on 881117,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Test of Channel B Air Intake Radiation Monitor RAI 6642.Caused by Maladjustment of Monitor During Calibr.Instruction Revised
| 10 CFR 50.73(e)(2) |
| 05000250/LER-1988-029, :on 881121,specialist Accidently short- Circuited Power Terminal Lead Which Resulted in Closure of RHR Suction Isolation Valve MOV-3-750.Caused by Personnel Error.Personnel Briefed |
- on 881121,specialist Accidently short- Circuited Power Terminal Lead Which Resulted in Closure of RHR Suction Isolation Valve MOV-3-750.Caused by Personnel Error.Personnel Briefed
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1) |
| 05000250/LER-1988-030, :on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced |
- on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced
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| 05000250/LER-1988-031, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | |
| 05000250/LER-1988-032, :on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised |
- on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised
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