| | | Reporting criterion |
|---|
| 05000316/LER-1986-001-01, :on 860117,flow Stopped for Continuous Tritium Sampling of Unit Vent Effluent.Caused by Sampling Line Blockage Due to Ice.Ice Removed & Tracing Repaired |
- on 860117,flow Stopped for Continuous Tritium Sampling of Unit Vent Effluent.Caused by Sampling Line Blockage Due to Ice.Ice Removed & Tracing Repaired
| |
| 05000315/LER-1986-001, :on 860120,high Alarms Resulted in ESF Actuation Signal Possibly Causing Isolation of Containment Purge Sys If Purge Sys in Svc.Caused by Leak in Porv.Alarm Setpoint Readjusted |
- on 860120,high Alarms Resulted in ESF Actuation Signal Possibly Causing Isolation of Containment Purge Sys If Purge Sys in Svc.Caused by Leak in Porv.Alarm Setpoint Readjusted
| |
| 05000316/LER-1986-002, :on 860122,discovered That 4 H Surveillance Frequency Exceeded on Four Occasions Between 851023-26.Cause Attributed to Lack of Procedural Control.Procedural Requirements Implemented |
- on 860122,discovered That 4 H Surveillance Frequency Exceeded on Four Occasions Between 851023-26.Cause Attributed to Lack of Procedural Control.Procedural Requirements Implemented
| |
| 05000315/LER-1986-002-01, :on 860217,two Reactor Trip Sys Interlock Setpoints Found Out of Compliance W/Tech Spec Definitions. Caused by Misinterpretation of Tech Spec Requirements.Tech Spec Rev Under Consideration |
- on 860217,two Reactor Trip Sys Interlock Setpoints Found Out of Compliance W/Tech Spec Definitions. Caused by Misinterpretation of Tech Spec Requirements.Tech Spec Rev Under Consideration
| |
| 05000315/LER-1986-002, :on 860217,discovered That Three Reactor Trip Sys Interlock Setpoints Not Set Per Tech Spec Requirements. Caused by Misinterpretation of Tech Specs.Procedures Revised to Agree W/Tech Specs |
- on 860217,discovered That Three Reactor Trip Sys Interlock Setpoints Not Set Per Tech Spec Requirements. Caused by Misinterpretation of Tech Specs.Procedures Revised to Agree W/Tech Specs
| |
| 05000315/LER-1986-003-01, :on 860228,evaluation of Noncompliance Rept (NCR) RQA-86-03-1 Concluded Certain Fire Protection Piping W/O Seismic Restraints Previously Installed Over safety-related Components.Also Reportable Per Part 21 |
- on 860228,evaluation of Noncompliance Rept (NCR) RQA-86-03-1 Concluded Certain Fire Protection Piping W/O Seismic Restraints Previously Installed Over safety-related Components.Also Reportable Per Part 21
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000316/LER-1986-003, :on 860207,ESF Actuation Occurred.Caused by High Alarm Signal.High Alarm Setpoint Set at Max Scale & Alert Alarm Setpoints Set to Correspond W/Current Radiological Conditions |
- on 860207,ESF Actuation Occurred.Caused by High Alarm Signal.High Alarm Setpoint Set at Max Scale & Alert Alarm Setpoints Set to Correspond W/Current Radiological Conditions
| |
| 05000315/LER-1986-004-01, :on 860228,evaluation of Noncompliance Rept Concluded Potential Loss of safety-related Electrical Equipment Due to Improper Application of Motor Control Ctr Reversing Starter Transformers.Reportable Per Part 21 |
- on 860228,evaluation of Noncompliance Rept Concluded Potential Loss of safety-related Electrical Equipment Due to Improper Application of Motor Control Ctr Reversing Starter Transformers.Reportable Per Part 21
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000316/LER-1986-004, :on 860129,defective Fire Penetration Discovered in Control Cable Vault.Caused by Silicone Seal Not Installed When Penetration Made.Fire Watch Posted & Permanent Seal Installed.Safety Evaluation Performed |
- on 860129,defective Fire Penetration Discovered in Control Cable Vault.Caused by Silicone Seal Not Installed When Penetration Made.Fire Watch Posted & Permanent Seal Installed.Safety Evaluation Performed
| |
| 05000315/LER-1986-004, :on 860228,reversing Starters Improperly Arranged in Motor Control Ctr & Fault in Control Transformer Could Result in Loss of Ctr.Design Change Implemented & Problem Will Be Resolved During Outage |
- on 860228,reversing Starters Improperly Arranged in Motor Control Ctr & Fault in Control Transformer Could Result in Loss of Ctr.Design Change Implemented & Problem Will Be Resolved During Outage
| |
| 05000000/LER-1986-005-03, Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points | Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points | |
| 05000315/LER-1986-005-01, :on 860411,reevaluation of Enerfab Test Rept Re Failure of Glass Test Specimen for Containment Airlock Exposed to Beta Radiation Occurred.Unable to Determine If Results Applicable to Glass Used at Plant |
- on 860411,reevaluation of Enerfab Test Rept Re Failure of Glass Test Specimen for Containment Airlock Exposed to Beta Radiation Occurred.Unable to Determine If Results Applicable to Glass Used at Plant
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000315/LER-1986-006-01, :on 860326,discrepancy Noted Between Reactor Protection & Engineered Safeguards Sys Time Response Test Procedure & Tech Spec Requirements.Reactor Coolant Pump Undervoltage Relay Response Time Omitted.Procedure Revised |
- on 860326,discrepancy Noted Between Reactor Protection & Engineered Safeguards Sys Time Response Test Procedure & Tech Spec Requirements.Reactor Coolant Pump Undervoltage Relay Response Time Omitted.Procedure Revised
| |
| 05000316/LER-1986-006, :on 860225,ESF Actuation Occurred.Caused by Increased Activity Levels in Containment.High Alarm Set Points & Alert Alarm Setpoints Readjusted |
- on 860225,ESF Actuation Occurred.Caused by Increased Activity Levels in Containment.High Alarm Set Points & Alert Alarm Setpoints Readjusted
| |
| 05000316/LER-1986-007, :on 860303,discovered That Safety Pins in Fire Door (Ieee/Dr) 314 Protecting Pressurizer Heater Transformer Room in Place W/No Personnel Present,Making Door Inoperable. Caused by Personnel Error.Procedures Reviewed |
- on 860303,discovered That Safety Pins in Fire Door (Ieee/Dr) 314 Protecting Pressurizer Heater Transformer Room in Place W/No Personnel Present,Making Door Inoperable. Caused by Personnel Error.Procedures Reviewed
| |
| 05000315/LER-1986-007-01, :on 860326,discrepancy Noted Between Reactor Protection & Engineered Safeguards Sys Time Response Test Procedure & Tech Spec 3.3-5 Re Turbine trip-reactor Trip Response Time.Rev Proposed |
- on 860326,discrepancy Noted Between Reactor Protection & Engineered Safeguards Sys Time Response Test Procedure & Tech Spec 3.3-5 Re Turbine trip-reactor Trip Response Time.Rev Proposed
| |
| 05000315/LER-1986-007, :on 860326,discovered Failure to Verify Time Response of Turbine Trip Involving Reactor Trip from Steam Generator hi-hi Level.Caused by Procedural Deficiency.Esf Time Response Test Procedure Will Be Revised |
- on 860326,discovered Failure to Verify Time Response of Turbine Trip Involving Reactor Trip from Steam Generator hi-hi Level.Caused by Procedural Deficiency.Esf Time Response Test Procedure Will Be Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000315/LER-1986-008-01, :on 860424,reactor Trip Function of Manual Safety Injection Circuitry Found Not Specifically Tested During Review to Ensure Compliance W/Tech Spec Surveillance & Bases Requirements |
- on 860424,reactor Trip Function of Manual Safety Injection Circuitry Found Not Specifically Tested During Review to Ensure Compliance W/Tech Spec Surveillance & Bases Requirements
| |
| 05000316/LER-1986-008, :on 860311,ESF Reactor Trip Signal Received Due to Control Power Wires Pulling Free from power-range Nuclear Instrument Drawer & Shorting Out.Caused by Faulty Electrical Connector & Mislabeled Doors |
- on 860311,ESF Reactor Trip Signal Received Due to Control Power Wires Pulling Free from power-range Nuclear Instrument Drawer & Shorting Out.Caused by Faulty Electrical Connector & Mislabeled Doors
| |
| 05000315/LER-1986-009-01, :on 860507,O-ring Seal Discovered Missing from Particulate Filter Holder.Caused by Procedural Deficiency. Routine Weekly Sample Procedure Changed to Incorporate Check for O-ring Seal to Filter |
- on 860507,O-ring Seal Discovered Missing from Particulate Filter Holder.Caused by Procedural Deficiency. Routine Weekly Sample Procedure Changed to Incorporate Check for O-ring Seal to Filter
| 10 CFR 50.73(a)(2)(i) |
| 05000315/LER-1986-010-01, :on 860515,upper Containment Area Particulate Radiation Monitor Spiked to High Alarm Status.Caused by Software Error of Eberline DAM-1 & 3.Alarm Automatically Reset.Upgraded Software to Be Installed |
- on 860515,upper Containment Area Particulate Radiation Monitor Spiked to High Alarm Status.Caused by Software Error of Eberline DAM-1 & 3.Alarm Automatically Reset.Upgraded Software to Be Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000316/LER-1986-010, :on 860317,w/unit in Mode 5 (Cold Shutdown), Fire Seal F-6801 in Control Room Discovered Missing Approx 9 Square Inches of Sealing Foam.Cause Undetermined.Permanent Repair Completed on 860403 |
- on 860317,w/unit in Mode 5 (Cold Shutdown), Fire Seal F-6801 in Control Room Discovered Missing Approx 9 Square Inches of Sealing Foam.Cause Undetermined.Permanent Repair Completed on 860403
| |
| 05000315/LER-1986-011-01, :on 860528,lower Containment Airborne Particulate Monitors Train a & B High Alarmed.Caused by Leaking Valves Mfg by Velan,Copes-Vulcan,Inc & Conval,Inc. Valves Repaired |
- on 860528,lower Containment Airborne Particulate Monitors Train a & B High Alarmed.Caused by Leaking Valves Mfg by Velan,Copes-Vulcan,Inc & Conval,Inc. Valves Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000315/LER-1986-012-01, :on 860528,during Mode 1,turbine Trip/Reactor Trip Occurred Due to Apparent Overspeed of Main Turbine. Cause Unknown.Trip Deemed Spurious Event.Frequency to Voltage Converter & Comparator Replaced |
- on 860528,during Mode 1,turbine Trip/Reactor Trip Occurred Due to Apparent Overspeed of Main Turbine. Cause Unknown.Trip Deemed Spurious Event.Frequency to Voltage Converter & Comparator Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000315/LER-1986-013-01, :on 860513 & 0606,procedural Deficiencies Re Actuation of Auxiliary Feedwater Sys Components on Loss of 4-kV Bus Voltage Noted.Procedures Literally Inconsistent W/ Tech Specs.Procedures Revised |
- on 860513 & 0606,procedural Deficiencies Re Actuation of Auxiliary Feedwater Sys Components on Loss of 4-kV Bus Voltage Noted.Procedures Literally Inconsistent W/ Tech Specs.Procedures Revised
| |
| 05000316/LER-1986-013, :on 860325,ESF Signal Generated During Test of Westinghouse solid-state Reactor Protection Sys.Caused by Personnel Error Due to Confusing Labeling of Logic Circuit Boards.Labels Clarified |
- on 860325,ESF Signal Generated During Test of Westinghouse solid-state Reactor Protection Sys.Caused by Personnel Error Due to Confusing Labeling of Logic Circuit Boards.Labels Clarified
| |
| 05000316/LER-1986-014, :on 860404,discovered That ESF Ventilation Sys HV-AES-1 Air Flow Rate Greater than Tech Spec Limit.Caused by Surveillance Procedure Deficiency.Procedure Will Be Revised to Include Addl Data |
- on 860404,discovered That ESF Ventilation Sys HV-AES-1 Air Flow Rate Greater than Tech Spec Limit.Caused by Surveillance Procedure Deficiency.Procedure Will Be Revised to Include Addl Data
| |
| 05000315/LER-1986-014-01, :on 860628,surveillance Testing Not Performed to Meet Requirements of Tech Spec 4.5.2.d.1 to Verify Interlock Action of RHR from Rcs.Caused by Personnel Error. Procedures Written to Ensure Compliance |
- on 860628,surveillance Testing Not Performed to Meet Requirements of Tech Spec 4.5.2.d.1 to Verify Interlock Action of RHR from Rcs.Caused by Personnel Error. Procedures Written to Ensure Compliance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000315/LER-1986-015-01, :on 860801,reactor Tripped from Steam Generator hi-hi Level.Caused by Inability of Personnel to Manually Control Main Feedwater Pump & Feedwater Valves.Operators Counseled |
- on 860801,reactor Tripped from Steam Generator hi-hi Level.Caused by Inability of Personnel to Manually Control Main Feedwater Pump & Feedwater Valves.Operators Counseled
| 10 CFR 50.73(a)(2) |
| 05000316/LER-1986-016, :on 860429,in Mode 6 W/Core Unloaded,Esf & Reactor Trip Signals Received.Caused by Shorted Control Power Wires to power-range Nuclear Instrument Drawer.Insps of Electrical Connectors Conducted |
- on 860429,in Mode 6 W/Core Unloaded,Esf & Reactor Trip Signals Received.Caused by Shorted Control Power Wires to power-range Nuclear Instrument Drawer.Insps of Electrical Connectors Conducted
| |
| 05000315/LER-1986-016-01, :on 860710,power-range Nuclear Instrumentation Time Response Testing Not Performed by Acceptable Test Method.Caused by Procedure Deficiency.Procedure Changes Implemented |
- on 860710,power-range Nuclear Instrumentation Time Response Testing Not Performed by Acceptable Test Method.Caused by Procedure Deficiency.Procedure Changes Implemented
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000316/LER-1986-017, :on 860506,contract Personnel Noticed Fire Seal W-9095 Had Foam Removed.Caused by Personnel Error.Fire Watch Posted & Fire Seal Repaired.Ltr Sent to All Dept Heads Re Maintaining Operable Fire Seals |
- on 860506,contract Personnel Noticed Fire Seal W-9095 Had Foam Removed.Caused by Personnel Error.Fire Watch Posted & Fire Seal Repaired.Ltr Sent to All Dept Heads Re Maintaining Operable Fire Seals
| |
| 05000315/LER-1986-017-01, :on 860722,turbine Tripped on Stator Cooling Water Low Pressure Trip Signal,Resulting in Turbine Trip/ Reactor Trip.Caused by Personnel Error.Personnel Counseled |
- on 860722,turbine Tripped on Stator Cooling Water Low Pressure Trip Signal,Resulting in Turbine Trip/ Reactor Trip.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2) |
| 05000315/LER-1986-018-01, :on 860802,reactor Trip Occurred from Steam Generator Flow Mismatch Coinciding W/Low Steam Generator Level.Caused by Increased Turbine Load.Personnel Counseled |
- on 860802,reactor Trip Occurred from Steam Generator Flow Mismatch Coinciding W/Low Steam Generator Level.Caused by Increased Turbine Load.Personnel Counseled
| 10 CFR 50.73(a)(2) |
| 05000316/LER-1986-018, :on 860509,partial Noncompliance W/Tech Spec 4.3.3.9.2 Surveillance Requirements for Steam Generator Blowdown Sys Discovered.Caused by Misinterpretation of Procedures.Procedures Revised |
- on 860509,partial Noncompliance W/Tech Spec 4.3.3.9.2 Surveillance Requirements for Steam Generator Blowdown Sys Discovered.Caused by Misinterpretation of Procedures.Procedures Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000315/LER-1986-019-01, :on 860731,discovered That During Calibr of Waste Gas Hydrogen Analyzer,Improper Gas Mixture Used to Check Accuracy of Analyzer Following 860703 Calibr.Caused by Personnel Error.Calibr of Analyzer Performed |
- on 860731,discovered That During Calibr of Waste Gas Hydrogen Analyzer,Improper Gas Mixture Used to Check Accuracy of Analyzer Following 860703 Calibr.Caused by Personnel Error.Calibr of Analyzer Performed
| |
| 05000316/LER-1986-019, :on 860605,during Mode 5,fire Insp Missed on Inoperable Fire Door 470.Caused by Personnel Error.Action Initiated to Restore Identification Numbers to Appropriate Plant Door & Personnel Counseled |
- on 860605,during Mode 5,fire Insp Missed on Inoperable Fire Door 470.Caused by Personnel Error.Action Initiated to Restore Identification Numbers to Appropriate Plant Door & Personnel Counseled
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000316/LER-1986-020, :on 860623,during Surveillance Test Activities, Discovered That RCS Narrow Range Tavg Resistive Temp Detector Channel Functional Tests Not Conducted.Caused by Deficient Procedures.Temp Reduced |
- on 860623,during Surveillance Test Activities, Discovered That RCS Narrow Range Tavg Resistive Temp Detector Channel Functional Tests Not Conducted.Caused by Deficient Procedures.Temp Reduced
| 10 CFR 50.73(a)(2)(i) |
| 05000315/LER-1986-020, :on 851102,main Steam Safety Valves Discovered Out of Spec During Surveillance Testing.Caused by Lack of Procedural Instructions.Safety Valves Setpoints Reset |
- on 851102,main Steam Safety Valves Discovered Out of Spec During Surveillance Testing.Caused by Lack of Procedural Instructions.Safety Valves Setpoints Reset
| 10 CFR 50.73(s)(2)(x) 10 CFR 50.73(s)(2)(v) 10 CFR 50.73(s)(2)(5) |
| 05000315/LER-1986-020-02, :on 851102,860623,831016 & 840702,main Steam Safety Valve Lift Setpoints Found Out of Spec.Caused by Lack of Procedural Instructions.Procedure Will Be Modified on 860825 |
- on 851102,860623,831016 & 840702,main Steam Safety Valve Lift Setpoints Found Out of Spec.Caused by Lack of Procedural Instructions.Procedure Will Be Modified on 860825
| |
| 05000315/LER-1986-021-01, :on 860925,during Surveillance Testing, Determined That RHR May Have Been in Unanalyzed Configuration for LOCA Found in Fsar.Caused by Lack of Specificity in Tech Specs |
- on 860925,during Surveillance Testing, Determined That RHR May Have Been in Unanalyzed Configuration for LOCA Found in Fsar.Caused by Lack of Specificity in Tech Specs
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000316/LER-1986-021, :on 860707,during Troubleshooting of source- Range Nuclear Instrument N-32,spike on ESF Signal Occurred. Procedures Revised to Permit Bypassing Reactor Trip Function During Troubleshooting |
- on 860707,during Troubleshooting of source- Range Nuclear Instrument N-32,spike on ESF Signal Occurred. Procedures Revised to Permit Bypassing Reactor Trip Function During Troubleshooting
| 10 CFR 50.73(a)(2) |
| 05000315/LER-1986-021, :on 860925,RHR Sys May Have Been in Analyzed Configuration Re LOCA Analysis.Caused by Misunderstanding of Tech Spec 3.5.2.Caution Tags Placed on Safety Injection & RHR Sys to Prevent Isolation |
- on 860925,RHR Sys May Have Been in Analyzed Configuration Re LOCA Analysis.Caused by Misunderstanding of Tech Spec 3.5.2.Caution Tags Placed on Safety Injection & RHR Sys to Prevent Isolation
| |
| 05000316/LER-1986-022, :on 860710 & 11,two power-range Nuclear Instrumentation Ni Channels (N-41 & N-42) Inoperable Due to Personnel Failure to Properly Document & Control Drawing Error.Administrative Controls Strengthened |
- on 860710 & 11,two power-range Nuclear Instrumentation Ni Channels (N-41 & N-42) Inoperable Due to Personnel Failure to Properly Document & Control Drawing Error.Administrative Controls Strengthened
| |
| 05000315/LER-1986-022-01, :on 861002,rod Insertion Limit Monitor Declared Inoperable After Determination That Limits Outside Tech Spec Requirements.Caused by Personnel Error.Rod Insertion Limit Calibr Procedure Revised & Performed |
- on 861002,rod Insertion Limit Monitor Declared Inoperable After Determination That Limits Outside Tech Spec Requirements.Caused by Personnel Error.Rod Insertion Limit Calibr Procedure Revised & Performed
| 10 CFR 50.73(a)(2)(1) |
| 05000316/LER-1986-023, :on 860715 & 18,erroneous Accumulator Level Indication Resulted in Low Accumulator Vol.Caused by Instrumentation Failure.Diagnostic Testing of Instrumentation Planned for Mar 1987 Outage |
- on 860715 & 18,erroneous Accumulator Level Indication Resulted in Low Accumulator Vol.Caused by Instrumentation Failure.Diagnostic Testing of Instrumentation Planned for Mar 1987 Outage
| 10 CFR 50.73(a)(2)(i) |
| 05000315/LER-1986-023-01, :on 861122,turbine Trip/Reactor Trip Occurred. Caused by Adjustment of Thrust Bearing Wear Detector Drifting to Point Where Turbine Shaft Displacement Would Generate Trip Signal.Detector Adjusted |
- on 861122,turbine Trip/Reactor Trip Occurred. Caused by Adjustment of Thrust Bearing Wear Detector Drifting to Point Where Turbine Shaft Displacement Would Generate Trip Signal.Detector Adjusted
| 10 CFR 50.73(a)(2) |
| 05000316/LER-1986-024, :on 860718,ESF Actuation Occurred Due to hi-hi Steam Generator Level.Caused by Failed Amplifier in Feedwater Flow Transmitter.Plant Procedures Implemented. Investigation Continuing |
- on 860718,ESF Actuation Occurred Due to hi-hi Steam Generator Level.Caused by Failed Amplifier in Feedwater Flow Transmitter.Plant Procedures Implemented. Investigation Continuing
| 10 CFR 50.73(a)(2) |
| 05000315/LER-1986-024-01, :on 861111,w/reactor at 90% Power,Esf Ventilation Fans Discovered Inoperable for Approx 18 Minutes.Caused by Damper Misalignment & Failure to Rept Error.Position Indicators Evaluated |
- on 861111,w/reactor at 90% Power,Esf Ventilation Fans Discovered Inoperable for Approx 18 Minutes.Caused by Damper Misalignment & Failure to Rept Error.Position Indicators Evaluated
| 10 CFR 50.73(a)(2)(i) |
| 05000316/LER-1986-025, :on 860912,determined That Replacement Timer Switches for 250 Volt Dc Battery Chargers Had Questionable Seismic Qualifications.Cause Unknown.Investigation Underway to Determine Why Seismic Concerns Not Addressed |
- on 860912,determined That Replacement Timer Switches for 250 Volt Dc Battery Chargers Had Questionable Seismic Qualifications.Cause Unknown.Investigation Underway to Determine Why Seismic Concerns Not Addressed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |