DT-21-07, Management Directive 10.102, Labor-Management Relations Program for Federal Employees
05000282/LER-1987-006-01, :on 870520,inadvertent Automatic Start of Auxiliary Feedwater Pump Occurred While Steam Generator 12 Being Drained in Preparation for Plugging One Tube.Caused by Personnel Error.Personnel Counseled
05000369/LER-1986-018, :on 860924,high Pressure Reactor Trip Occurred Due to Turbine Control Sys Malfunction.Cause Unknown. Troubleshooting & Monitoring of Turbine Control Sys Will Continue
05000346/LER-1986-035, :on 860813,seismic Monitoring Sys Inoperable. Caused by Deficient Surveillance Test Procedures.Strong Motion Accelerometers Removed for Calibr & Test Procedures Revised to Meet Tech Specs
05000370/LER-1985-014-02, :on 850517,reactor Critical W/Bank C Control Rods Below Min Tech Spec Insertion Limits.Caused by Incorrect Coefficients in Xenon Predict Computer Program. Control Rods Reinserted.Procedures Modified
05000281/LER-1986-015-01, :on 861031,pressurizer Safety Valve Setpoints Found Outside Allowable Limits.Caused by Failure to Compensate for Operating Temp & Valve Wear.Valves Replaced & Setpoints Reset
05000424/LER-1987-007, :on 870301,control Room Annunciator Alerted Operators That Steam Generator hi-hi Water Level Setpoint Had Been Reached.Caused by Personnel Error.Operators Counseled on Monitoring Steam Generator Level
05000266/LER-1986-001, :on 860102,during Full power,20% Turbine Runback Experienced.Caused by Voltage Spike in Channel 44 of Power Range Instrumentation Sys Due to Faulty 25-volt Power Supply.Power Supply Replaced
05000318/LER-1985-008-01, :on 850724,MSIV Failed to Fully Close & Declared Inoperable.Caused by Oil Deficiency Due to Gas Bubble in Hydraulic Fluid Header & Addl Component Malfunctions.Suppressor Bladders Replaced
05000259/LER-1985-031, :on 850706-09,engineering Reviews Revealed Flanged Joints on Water Recirculation,Air Release,Pressure Reducing & Water Regulator Valves.Caused by Failure to Specify Flange Types
05000321/LER-1985-026-01, :on 850627,reactor Scrammed.Caused by Nonlicensed Personnel Closing Incorrect Fire Valve Chamber Resulting in phase-to-ground Fault Trip on Transformer. Valves Labeled & Nozzle Realigned
05000219/LER-1985-017, :on 850708,drywell Bulk Average Temps Exceeded. Cause Under Investigation But Appears to Be Associated W/Cooler Design Capacities.Addl Thermocouples at Lower Elevation in Drywell Utilized
05000336/LER-1985-005, :on 850401,retest of Control Switch Caused Loss of Normal Power Signal to Be Generated to 4.16 Kv Emergency Bus 24D.Caused by Personnel Error.Personnel Instructed to Use Increased Caution in Researching Circuits
05000327/LER-1985-007, :on 850131,while Performing Surveillance Instruction 166.21,Train B Emergency Gas Treatment Sys Room Cooler Would Not Start.Caused by Blown Control Fuse.Fuse Replaced
05000483/LER-1985-002, :on 850107,reactor Tripped from 50% Power Due to Turbine Trip.Caused by Spurious High Vibration Signal. High Vibration Turbine Trip Circuitry Modified
05000388/LER-1985-009, :on 850212,setpoints for Three Reactor Water Level Switches Found to Be Outside Acceptance Criteria During Performance of Scheduled Surveillance.Caused by Instrument Drift.Instruments Recalibr
05000388/LER-1984-011-01, :on 840705 & 06,four Spurious Actuations of Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Experienced.Caused by Malfunctioning Output Breaker.Breaker Replaced
05000249/LER-1984-015-06, :on 840925,during Planned Unit Shutdown,Reactor Scrammed on Low Condenser Vacuum Caused by Air in-leakage Through Damaged Bellows on Seal Steam Relief Valve Discharge Line.Bellows Replaced
05000348/LER-1984-020, :on 840907,control Room Fire Barrier Penetrations 01-155-02 & 06-155-03 Found Not to Be Sealed Per Tech Specs.Cause Not Stated.Penetrations Sealed & Declared Operable on 840912
05000327/LER-1984-036, :on 840618,neoprene Gasket Slipped & Bus Conductor Grounded,Causing Turbine & Reactor Trip.Caused by Slipped Gasket.Potential Transformer Insulators Cleaned & Gaskets Reworked
05000369/LER-1984-015, :on 840426,during Performance of Rod Control Cluster Assembly Drop Timing,Rod B-12 Failed to Indicate Correct Position.Caused by Defective Detector/Encoder Card. Card Replaced & Drop Timing Completed
05000369/LER-1984-014, :on 840420,essential 4,160-volt Switchgear Equipment Transfer Aisle 1 Inadvertently Deenergized During ESF Test.Caused by Personnel Error.Offsite Power Returned to Equipment Transfer Aisle 1
05000306/LER-1984-001-01, :on 840618,during Safeguards Logic Test,Logic for Opening Safety Injection Suction Valves from Refueling Water Storage Tank Satisfied.Open Valves Immediately Closed. Procedures Revised to Prevent Recurrence
05000327/LER-1984-043, :on 840627,during Surveillance,Thermal Fire Detector Discovered Inoperable.Required 1 H Fire Watch Not Established.Shift Engineer Not Notified.Fire Detector Replaced & Returned to Svc
05000220/LER-1984-010, :on 840608,reactor Protection Sys Channel 4 Power Supply Bus Experienced Momentary Power Loss Causing Condenser vacuum-MSIV Closure Scram Bypass Relays to Deenergize
05000369/LER-1984-020, :on 840606,reactor Tripped When Spurious Undervoltage Relay Actuation Deenergized One Reactor Coolant Pump.Caused by Component Malfunction.Further Testing Will Be Conducted to Determine Failure Mechanism
05000280/LER-1984-009, :on 840407,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level Exceeding Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Level Monitored Every 4 H
05000327/LER-1984-001-01, :on 840102,high Radiation Alarm Actuated, Causing Containment Vent Isolation to Occur.Caused by Spurious Signals on Radiation Monitor.Alarm Reset & Monitor Returned to Svc
05000275/LER-1985-011, :on 850217,manual Reactor Trip Initiated in Response to Automatic Shutdown of Main Feedwater Pumps 1-1 & 1-2 from Excessive Thrust Bearing Wear Indication.Thrust Bearing Wear Detection Sys Reset