| | | Reporting criterion |
|---|
| 05000397/LER-1986-001, :on 860209,spurious Actuation of Control Room Emergency Filtration Sys Occurred Due to Chlorine Monitor Tape Depletion.Caused by Inadequate Design & Personnel Error.Tape Replaced |
- on 860209,spurious Actuation of Control Room Emergency Filtration Sys Occurred Due to Chlorine Monitor Tape Depletion.Caused by Inadequate Design & Personnel Error.Tape Replaced
| |
| 05000397/LER-1986-002, :on 860226,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal Under Normal Conditions.Cause Unknown.Method of Circulating Water Treatment Will Be Changed |
- on 860226,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal Under Normal Conditions.Cause Unknown.Method of Circulating Water Treatment Will Be Changed
| |
| 05000397/LER-1986-003, :on 860314,reactor Scram Occurred Due to Incorrect Switch Position During APRM Channel a Functional Test.Caused by Personnel Error.Technicians Counseled & Trained in Proper Actions |
- on 860314,reactor Scram Occurred Due to Incorrect Switch Position During APRM Channel a Functional Test.Caused by Personnel Error.Technicians Counseled & Trained in Proper Actions
| |
| 05000397/LER-1986-004, :on 860316,during Reactor Shutdown,Reactor Scram Occurred & Pressure Transient Caused Nuclear Instrumentation intermediate-range Monitor Channels to Exceed High Upscale Trip Setpoint |
- on 860316,during Reactor Shutdown,Reactor Scram Occurred & Pressure Transient Caused Nuclear Instrumentation intermediate-range Monitor Channels to Exceed High Upscale Trip Setpoint
| |
| 05000397/LER-1986-005, :on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed |
- on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed
| 10 CFR 50.73(a)(2)(1) |
| 05000397/LER-1986-006, :on 860421,reactor Protective Trip Occurred During Installation of Shorting Links for Reactor Protection Sys.Caused by Operator Error,Resulting in Short Circuit. Operator Counseled & Procedure Enhanced |
- on 860421,reactor Protective Trip Occurred During Installation of Shorting Links for Reactor Protection Sys.Caused by Operator Error,Resulting in Short Circuit. Operator Counseled & Procedure Enhanced
| |
| 05000397/LER-1986-007, :on 860217,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Undetermined.Method of Circulating Water Treatment Will Be Changed |
- on 860217,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Undetermined.Method of Circulating Water Treatment Will Be Changed
| |
| 05000397/LER-1986-008, :on 860505,potential Transformer Secondary Fuse Blew,Resulting in Spurious Voltage Loss Signal to SM-8 Undervoltage Protection Cricuitry.Caused by Electrical Maint Technician Error.Technician Counseled |
- on 860505,potential Transformer Secondary Fuse Blew,Resulting in Spurious Voltage Loss Signal to SM-8 Undervoltage Protection Cricuitry.Caused by Electrical Maint Technician Error.Technician Counseled
| |
| 05000397/LER-1986-009, :on 860426,secondary Containment Sys Emergency Operation Initiated When Control Power Fuse in Reactor Bldg Ventilation High Radiation Monitoring Circuitry Blew.Cause Undetermined |
- on 860426,secondary Containment Sys Emergency Operation Initiated When Control Power Fuse in Reactor Bldg Ventilation High Radiation Monitoring Circuitry Blew.Cause Undetermined
| |
| 05000397/LER-1986-010, :on 860513,Diesel Generator 1 Fuel Storage Tank Below Min Inventory.Caused by 24 H Diesel Generator Run When Diesel Generator 2 Out of Svc.Fuel Storage Tank Filled & in Compliance |
- on 860513,Diesel Generator 1 Fuel Storage Tank Below Min Inventory.Caused by 24 H Diesel Generator Run When Diesel Generator 2 Out of Svc.Fuel Storage Tank Filled & in Compliance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000397/LER-1986-011, :on 860509,nuclear Steam Supply Shutoff Sys Actuated Due to Momentary Loss of Instrument Power. Cause Unknown.Reactor Protection Sys Half Scram & Isolation Signals Reset |
- on 860509,nuclear Steam Supply Shutoff Sys Actuated Due to Momentary Loss of Instrument Power. Cause Unknown.Reactor Protection Sys Half Scram & Isolation Signals Reset
| |
| 05000397/LER-1986-012, :on 860512,isolation Function of Nuclear Steam Supply Shutoff Sys Actuated Due to Deenergization of Reactor Protective Sys Supply Bus A.Caused by Inadequate Procedures. Inboard Isolation Valves Restored |
- on 860512,isolation Function of Nuclear Steam Supply Shutoff Sys Actuated Due to Deenergization of Reactor Protective Sys Supply Bus A.Caused by Inadequate Procedures. Inboard Isolation Valves Restored
| |
| 05000397/LER-1986-014, :on 860523,discovered That Two Containment Exhaust Purge Sys Test Connection Isolation Valves Not Tested at 24-month Interval.Caused by Personnel Error. Surveillance Procedure Modified |
- on 860523,discovered That Two Containment Exhaust Purge Sys Test Connection Isolation Valves Not Tested at 24-month Interval.Caused by Personnel Error. Surveillance Procedure Modified
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000397/LER-1986-015, :on 860606,RWCU Sys Isolated During Leak Detection Sys Temp Indicator Calibr.Caused by Technician Incorrectly Lifting Lead.Technician Counseled & Training Package Modified to Include Calibr Procedure |
- on 860606,RWCU Sys Isolated During Leak Detection Sys Temp Indicator Calibr.Caused by Technician Incorrectly Lifting Lead.Technician Counseled & Training Package Modified to Include Calibr Procedure
| |
| 05000397/LER-1986-016, :on 860612,RWCU Sys Isolation Occurred.Caused by Instrument Technician Using Wrong Switch While Performing Channel Functional Test for RWCU High Delta Flow.Labels for Test Switches Will Be Improved |
- on 860612,RWCU Sys Isolation Occurred.Caused by Instrument Technician Using Wrong Switch While Performing Channel Functional Test for RWCU High Delta Flow.Labels for Test Switches Will Be Improved
| |
| 05000397/LER-1986-017, :on 860608,RWCU Sys Automatically Isolated Due to High Differential Flow.Caused by Personnel Error.Rwcu Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow.Personnel Counseled |
- on 860608,RWCU Sys Automatically Isolated Due to High Differential Flow.Caused by Personnel Error.Rwcu Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow.Personnel Counseled
| |
| 05000397/LER-1986-018, :on 860526 & 29,diesel Generator 2 Failed During post-mod Diagnostic Testing.Cause Undetermined. Procedure Will Be Written to Provide More Detailed Guidance Re post-mod Retesting |
- on 860526 & 29,diesel Generator 2 Failed During post-mod Diagnostic Testing.Cause Undetermined. Procedure Will Be Written to Provide More Detailed Guidance Re post-mod Retesting
| |
| 05000397/LER-1986-019, :on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected |
- on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi) |
| 05000397/LER-1986-020, :on 860610,while Recovering from Overspeed Trip Test,Reactor Scrammed.Caused by Inadequate Turbine Operating Procedure.Procedure Modified to Include Addl Info Re Tv/Gv Transfer & Expected Plant Response |
- on 860610,while Recovering from Overspeed Trip Test,Reactor Scrammed.Caused by Inadequate Turbine Operating Procedure.Procedure Modified to Include Addl Info Re Tv/Gv Transfer & Expected Plant Response
| |
| 05000397/LER-1986-021, :on 860620,plant Shutdown Commenced Due to Leakage from RCS Pressure Isolation Valve Exceeding 1 Gpm. Caused by Damage to Valve Seat,Disk & Internal Surfaces from Cavitation.Valve Replaced |
- on 860620,plant Shutdown Commenced Due to Leakage from RCS Pressure Isolation Valve Exceeding 1 Gpm. Caused by Damage to Valve Seat,Disk & Internal Surfaces from Cavitation.Valve Replaced
| 10 CFR 50.73(a)(2)(1) |
| 05000397/LER-1986-022, :on 860627,during Planned Outage While Electrical Loads Supplied by Offsite Power Source,Standby Diesel Generators Automatically Started.Caused by Momentary Loss of Power from nonplant-related Trip |
- on 860627,during Planned Outage While Electrical Loads Supplied by Offsite Power Source,Standby Diesel Generators Automatically Started.Caused by Momentary Loss of Power from nonplant-related Trip
| |
| 05000397/LER-1986-023, :on 860710,reactor Scram Occurred Following Opening of Incorrect Circuit Breaker During Electrical Ground Isolation.Caused by Personnel Error.Engineer Drawing & Circuit Breaker Labeling Will Be Changed |
- on 860710,reactor Scram Occurred Following Opening of Incorrect Circuit Breaker During Electrical Ground Isolation.Caused by Personnel Error.Engineer Drawing & Circuit Breaker Labeling Will Be Changed
| |
| 05000397/LER-1986-024, :on 860721,standby Diesel Generator 2 (DG2) Started.Caused by Internal Electrical Fault on One of Three Condensate Booster pumps.DG2 Secured Per Plant Procedure & Returned to Normal Backup |
- on 860721,standby Diesel Generator 2 (DG2) Started.Caused by Internal Electrical Fault on One of Three Condensate Booster pumps.DG2 Secured Per Plant Procedure & Returned to Normal Backup
| |
| 05000397/LER-1986-026, :on 860725,following Reactor Scram,Containment Isolation at RWCU Sys Actuated Due to High Differential Flow.Caused by Inadequate Design.Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow |
- on 860725,following Reactor Scram,Containment Isolation at RWCU Sys Actuated Due to High Differential Flow.Caused by Inadequate Design.Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow
| |
| 05000397/LER-1986-027, :on 860903,evaluation Concluded That Engineering Criteria Supplied by Burns & Roe,Inc,In Electrical Spec 2808-218 Nonconservative.Procedures Utilizing Faulty Data Will Be Modified |
- on 860903,evaluation Concluded That Engineering Criteria Supplied by Burns & Roe,Inc,In Electrical Spec 2808-218 Nonconservative.Procedures Utilizing Faulty Data Will Be Modified
| 10 CFR 21.21(b)(3) |
| 05000397/LER-1986-029, :on 860822,drywell Hydrogen Analyzers Calibr Using 2% & 6% by Vol Hydrogen Gas Rather than 0% & 25% Required by Tech Specs.Caused by Personnel Error.Analyzers Recalibr.Tech Spec Amend Requested |
- on 860822,drywell Hydrogen Analyzers Calibr Using 2% & 6% by Vol Hydrogen Gas Rather than 0% & 25% Required by Tech Specs.Caused by Personnel Error.Analyzers Recalibr.Tech Spec Amend Requested
| 10 CFR 50.73(a)(2)(i) |
| 05000397/LER-1986-030, :on 860903,reactor Scram Occurred Due to Low Reactor Water Level.Caused by Reactor Feedwater Pump Trip & Failure of Recirculation Flow Control Valve to Run Back. Preventive Maint Procedure Will Be Written |
- on 860903,reactor Scram Occurred Due to Low Reactor Water Level.Caused by Reactor Feedwater Pump Trip & Failure of Recirculation Flow Control Valve to Run Back. Preventive Maint Procedure Will Be Written
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000397/LER-1986-031, :on 860910,RCIC Inboard Steam Line Isolation Valves Closed on Erroneous RCIC Equipment Area High Temp Signal.Caused by Technicians Inadvertently Connecting Test Equipment to Wrong Circuit.Personnel Counseled |
- on 860910,RCIC Inboard Steam Line Isolation Valves Closed on Erroneous RCIC Equipment Area High Temp Signal.Caused by Technicians Inadvertently Connecting Test Equipment to Wrong Circuit.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000397/LER-1986-032, :on 861007,review of Plant Records Revealed That Control Rod Block intermediate-range Neutron Monitoring Quarterly Calibr Not Performed.Caused Insufficient Programmatic Controls.Items Now Tracked |
- on 861007,review of Plant Records Revealed That Control Rod Block intermediate-range Neutron Monitoring Quarterly Calibr Not Performed.Caused Insufficient Programmatic Controls.Items Now Tracked
| |
| 05000397/LER-1986-034, :on 861017,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.No Cause Established.Tech Spec Amend Requested to Delete Chlorine Detection Requirements.W/Undated Ltr |
- on 861017,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.No Cause Established.Tech Spec Amend Requested to Delete Chlorine Detection Requirements.W/Undated Ltr
| |
| 05000397/LER-1986-035, :on 861101 & 08,emergency Filtration Sys Initiated on High Chlorine Signal.No Root Cause Determined. Chlorine Detectors Will Be Removed After Tech Spec Approval |
- on 861101 & 08,emergency Filtration Sys Initiated on High Chlorine Signal.No Root Cause Determined. Chlorine Detectors Will Be Removed After Tech Spec Approval
| |
| 05000397/LER-1986-036, :on 861110,control Room Emergency Filtration Sys Automatically Initiated on False High Chlorine Signal. Caused by Broken chlorine-sensitive Paper Tape.Chlorine Monitor Investigated & Tape Replaced |
- on 861110,control Room Emergency Filtration Sys Automatically Initiated on False High Chlorine Signal. Caused by Broken chlorine-sensitive Paper Tape.Chlorine Monitor Investigated & Tape Replaced
| |
| 05000397/LER-1986-037, :on 861120,plant Shut Down After Connector for Signal Cable of Acoustic Monitoring Channel 5C Determined to Be Not Environmentally Qualified.Caused by Inadequate Maint Work Request.Vital Work Requests Reviewed |
- on 861120,plant Shut Down After Connector for Signal Cable of Acoustic Monitoring Channel 5C Determined to Be Not Environmentally Qualified.Caused by Inadequate Maint Work Request.Vital Work Requests Reviewed
| |
| 05000397/LER-1986-038, :on 861120,reactor Scram Occurred.Caused by Rapid Decrease in Reactor Water Level Upon Incorrect Alignment of Condensate Cleanup Block Valves & Feedwater Diversion to Empty Line.Operators Counseled |
- on 861120,reactor Scram Occurred.Caused by Rapid Decrease in Reactor Water Level Upon Incorrect Alignment of Condensate Cleanup Block Valves & Feedwater Diversion to Empty Line.Operators Counseled
| |
| 05000397/LER-1986-039, :on 861123,control Room Emergency Filtration Sys Initiated on False High Chlorine Signal.Caused by Incorrect Lamp (5.6V) Inadvertently Installed.Lamp Replaced |
- on 861123,control Room Emergency Filtration Sys Initiated on False High Chlorine Signal.Caused by Incorrect Lamp (5.6V) Inadvertently Installed.Lamp Replaced
| |
| 05000397/LER-1986-040, :on 861125,technicians Failed to Obtain Drywell Samples Every 12 H as Required.Caused by Failure of Personnel to Follow Procedures.Personnel Counseled |
- on 861125,technicians Failed to Obtain Drywell Samples Every 12 H as Required.Caused by Failure of Personnel to Follow Procedures.Personnel Counseled
| |
| 05000397/LER-1986-041, :on 861126,1202,05 & 06,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal for No Apparent Reason.Investigation of Chlorine Monitor Did Not Reveal Any Malfunctions |
- on 861126,1202,05 & 06,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal for No Apparent Reason.Investigation of Chlorine Monitor Did Not Reveal Any Malfunctions
| |
| 05000397/LER-1986-042, :on 861201,plant Nonconformance Rept Issued to Document Omission of Fire Door C228 from Two Surveillance Procedures.Caused by Personnel Error.Door Verified Operable & Locked & All Surveillance Procedures Checked |
- on 861201,plant Nonconformance Rept Issued to Document Omission of Fire Door C228 from Two Surveillance Procedures.Caused by Personnel Error.Door Verified Operable & Locked & All Surveillance Procedures Checked
| |
| 05000397/LER-1986-043, :on 861217 & 19,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Unknown.Control Room Emergency Filtration Sys Returned to Normal Lineup |
- on 861217 & 19,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Unknown.Control Room Emergency Filtration Sys Returned to Normal Lineup
| |
| 05000397/LER-1986-044, :on 861222,liquid Radwaste Effluents Discharged W/Radioactive Liquid Effluent Monitor Inoperable & Only One Predischarge Batch Sample Obtained & Analyzed.Caused by Personnel Error.Personnel Counseled |
- on 861222,liquid Radwaste Effluents Discharged W/Radioactive Liquid Effluent Monitor Inoperable & Only One Predischarge Batch Sample Obtained & Analyzed.Caused by Personnel Error.Personnel Counseled
| |