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| 05000322/LER-1986-001, :on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements |
- on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements
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| 05000322/LER-1986-002, :on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired |
- on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired
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| 05000322/LER-1986-004, :on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging |
- on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging
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| 05000322/LER-1986-005, :on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency |
- on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency
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| 05000322/LER-1986-007, :on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised |
- on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised
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| 05000322/LER-1986-008, :on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised |
- on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised
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| 05000322/LER-1986-009, :on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed |
- on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed
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| 05000322/LER-1986-011, :on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220 |
- on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220
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| 05000322/LER-1986-011-02, Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | |
| 05000322/LER-1986-012, :on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication |
- on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication
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| 05000322/LER-1986-013, :on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated |
- on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated
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| 05000322/LER-1986-015, :on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed |
- on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed
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| 05000322/LER-1986-016, :on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines |
- on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines
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| 05000322/LER-1986-018, :on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised |
- on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised
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| 05000322/LER-1986-019, :on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised |
- on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised
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| 05000322/LER-1986-020, :on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector |
- on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector
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| 05000322/LER-1986-021, :on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves |
- on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves
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| 05000322/LER-1986-022, :on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps |
- on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps
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| 05000322/LER-1986-023, :on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised |
- on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised
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| 05000322/LER-1986-024, :on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress |
- on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress
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| 05000322/LER-1986-025, :on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples |
- on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples
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| 05000322/LER-1986-026, :on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised |
- on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000322/LER-1986-027, :on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer |
- on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer
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| 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced |
- on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
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| 05000322/LER-1986-030, :on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists |
- on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000322/LER-1986-031, :on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities |
- on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities
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| 05000322/LER-1986-033, :on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve |
- on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve
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| 05000322/LER-1986-034, :on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down |
- on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) |
| 05000322/LER-1986-035, :on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc |
- on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc
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| 05000322/LER-1986-036, :on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised |
- on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000322/LER-1986-037, :on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished |
- on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished
| 10 CFR 50.73(a)(2)(i) |
| 05000322/LER-1986-039, :on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated |
- on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000322/LER-1986-040, :on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced |
- on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000322/LER-1986-042, :on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010 |
- on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010
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| 05000322/LER-1986-044, :on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal |
- on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000322/LER-1986-045, :on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled |
- on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |