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| 05000400/LER-1991-001, :on 910103,operations Personnel Identified Procedural Deficiency That Resulted in Check Valves Not Being Tested as Required.Caused by Procedural Deficiency. Procedure Revised to Incorporate Testing |
- on 910103,operations Personnel Identified Procedural Deficiency That Resulted in Check Valves Not Being Tested as Required.Caused by Procedural Deficiency. Procedure Revised to Incorporate Testing
| 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(4) |
| 05000400/LER-1991-001-01, :on 910225,Tech Spec Violation Due to Missed Surveillance Testing for Control Room HVAC Check Valves. Caused by Procedural Deficiency.Event Will Be Reviewed & ISI Personnel to Perform Comprehensive Review |
- on 910225,Tech Spec Violation Due to Missed Surveillance Testing for Control Room HVAC Check Valves. Caused by Procedural Deficiency.Event Will Be Reviewed & ISI Personnel to Perform Comprehensive Review
| 10 CFR 50.73(a)(2) |
| 05000400/LER-1991-002-02, :on 910305,determined That Underfrequency Reactor Coolant Pump Reactor Trip Inoperable on Train B of Solid State Protection Sys.Caused by Umbilical Cord in Breakers Not Connected.Training Provided |
- on 910305,determined That Underfrequency Reactor Coolant Pump Reactor Trip Inoperable on Train B of Solid State Protection Sys.Caused by Umbilical Cord in Breakers Not Connected.Training Provided
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-003-01, :on 910121,missed Surveillance Test During Emergency Diesel Generator Fuel Oil Sampling.Caused by Personnel Error.Training Conducted for Chemistry Personnel & Procedure RST-209 Revised |
- on 910121,missed Surveillance Test During Emergency Diesel Generator Fuel Oil Sampling.Caused by Personnel Error.Training Conducted for Chemistry Personnel & Procedure RST-209 Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-004-01, :on 910314,train B Essential Svc Chilled Water Sys Inoperable Due to Unsatisfactory Performance Test Results.Caused by Inability to Verify Check Valve Had Closed.Procedure OPT-1512 Revised |
- on 910314,train B Essential Svc Chilled Water Sys Inoperable Due to Unsatisfactory Performance Test Results.Caused by Inability to Verify Check Valve Had Closed.Procedure OPT-1512 Revised
| |
| 05000400/LER-1991-005-01, :on 910313,Tech Spec 3.0.3 Entered Due to Failed Performance Test on Emergency Sequencer B While Csip a Inoperable.Caused by Isolated Contact Failure in B Program Relay.Faulty Relay Replaced |
- on 910313,Tech Spec 3.0.3 Entered Due to Failed Performance Test on Emergency Sequencer B While Csip a Inoperable.Caused by Isolated Contact Failure in B Program Relay.Faulty Relay Replaced
| 10 CFR 50.73(s)(2)(8) |
| 05000400/LER-1991-006-01, :on 910319,shutdown Margin Requirements Not Verified During Surveillance Testing on source-range Nuclear Instruments.Caused by Misinterpretation of Tech Specs.Procedures Will Be Revised |
- on 910319,shutdown Margin Requirements Not Verified During Surveillance Testing on source-range Nuclear Instruments.Caused by Misinterpretation of Tech Specs.Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000400/LER-1991-007-01, :on 910325,one Emergency Svc Water Pump Inappropriately Removed from Svc for Outage Work.Caused by Personnel/Mgt Error.Info Re Event Disseminated to Personnel & TS Will Be Annotated |
- on 910325,one Emergency Svc Water Pump Inappropriately Removed from Svc for Outage Work.Caused by Personnel/Mgt Error.Info Re Event Disseminated to Personnel & TS Will Be Annotated
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(6) |
| 05000400/LER-1991-008-02, Forwards LER 91-008-02.Rev Discusses Addl Testing Performed on High Head SI Sys During Current Refueling Outage & Mod to Sys Which Will Prevent Recurrence of Event | Forwards LER 91-008-02.Rev Discusses Addl Testing Performed on High Head SI Sys During Current Refueling Outage & Mod to Sys Which Will Prevent Recurrence of Event | |
| 05000400/LER-1991-008-01, :on 910403,common-cause Failures Affecting Trains of High Head Safety Injection Identified.Caused by Water Hammer That Apparently Occurred Because of Air Void. Relief Valves Being Rebuilt & Retested |
- on 910403,common-cause Failures Affecting Trains of High Head Safety Injection Identified.Caused by Water Hammer That Apparently Occurred Because of Air Void. Relief Valves Being Rebuilt & Retested
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-008, :on 910403,common Causes Failure of High Head Safety Injection Alternate Miniflow Occurred.Caused by Water Hammer Due to Air Void.Supports Added to Test Connection Lines |
- on 910403,common Causes Failure of High Head Safety Injection Alternate Miniflow Occurred.Caused by Water Hammer Due to Air Void.Supports Added to Test Connection Lines
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-009-01, :on 910521,AFW Actuation Occurred Due to Steam Generator Hi-Hi Level Alarm Inadvertently Generated During Troubleshooting.Caused by Personnel Error.Technicians Counseled & Addl Procedural Guidance Developed |
- on 910521,AFW Actuation Occurred Due to Steam Generator Hi-Hi Level Alarm Inadvertently Generated During Troubleshooting.Caused by Personnel Error.Technicians Counseled & Addl Procedural Guidance Developed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-010-01, :on 910603,automatic Reactor Trip Occurred Due to Pressure Spike in Flow Transmitter Ref Leg for Reactor Coolant Loop Low Flow.Caused by Perturbation in Sensing Lines.Rcs Flow Calibr Procedures Revised |
- on 910603,automatic Reactor Trip Occurred Due to Pressure Spike in Flow Transmitter Ref Leg for Reactor Coolant Loop Low Flow.Caused by Perturbation in Sensing Lines.Rcs Flow Calibr Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000400/LER-1991-011-01, :on 910512,identified Required Boration Flowpath Functional But Not Operable for Six Days.Caused by Human Error.Procedure RST-201 Being Revised to Specify Acceptable Range for Boron Concentration |
- on 910512,identified Required Boration Flowpath Functional But Not Operable for Six Days.Caused by Human Error.Procedure RST-201 Being Revised to Specify Acceptable Range for Boron Concentration
| 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000400/LER-1991-012-01, :on 910515,unplanned Actuation of Auxiliary Feedwater Sys Occurred.Caused by Failure of Main Feed Pump a to Start.Investigation & Testing Performed on Pump & Associated Circuitry |
- on 910515,unplanned Actuation of Auxiliary Feedwater Sys Occurred.Caused by Failure of Main Feed Pump a to Start.Investigation & Testing Performed on Pump & Associated Circuitry
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000400/LER-1991-013-01, :on 910515,reactor Trip Occurred During Performance of Calibrs.Caused by Personnel Error.Need for Effective Communications Stressed to Applicable Operations Personnel |
- on 910515,reactor Trip Occurred During Performance of Calibrs.Caused by Personnel Error.Need for Effective Communications Stressed to Applicable Operations Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1) |
| 05000400/LER-1991-015, :on 910519,AFW Actuation Occurred.Caused by Improperly Set Feed Flow Transmitter.Investigation, Adjustment & Successful Testing Performed to Restore Feed Flow Transmitter to Svc |
- on 910519,AFW Actuation Occurred.Caused by Improperly Set Feed Flow Transmitter.Investigation, Adjustment & Successful Testing Performed to Restore Feed Flow Transmitter to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(s)(2) |
| 05000400/LER-1991-016-01, :on 910808,containment Cooling Water Pump B Started,Resulting in Momentary Pressure Spike Which Caused Three Relief Valves to Open.Caused by Error in Original Sys Design.Personnel Trained Re Valve Setting |
- on 910808,containment Cooling Water Pump B Started,Resulting in Momentary Pressure Spike Which Caused Three Relief Valves to Open.Caused by Error in Original Sys Design.Personnel Trained Re Valve Setting
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1) |
| 05000400/LER-1991-017-01, :on 910827,tech Spec Violation Occurred Due to Missed Composite Sample During Release of Secondary Waste Sample Tank.Caused by Personnel Error.Verified That Effluent Stream Contained No Radioactivity |
- on 910827,tech Spec Violation Occurred Due to Missed Composite Sample During Release of Secondary Waste Sample Tank.Caused by Personnel Error.Verified That Effluent Stream Contained No Radioactivity
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000400/LER-1991-018-01, :on 910923,personnel Emergency Air Lock Surveillance Interval Exceeded Surveillance Requirement 4.6.1.3.b.1 of Once Per 6 Months.Caused by Personnel Error. Schedule Revised |
- on 910923,personnel Emergency Air Lock Surveillance Interval Exceeded Surveillance Requirement 4.6.1.3.b.1 of Once Per 6 Months.Caused by Personnel Error. Schedule Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000400/LER-1991-019-01, :on 911022,containment Ventilation Isolation Signal Generated,Resulting in Unplanned Actuation of ESF Component.Caused by Spike on Three Radiation Monitors.Power Supply Circuitry Repaired & Adjusted |
- on 911022,containment Ventilation Isolation Signal Generated,Resulting in Unplanned Actuation of ESF Component.Caused by Spike on Three Radiation Monitors.Power Supply Circuitry Repaired & Adjusted
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-019, :on 911022,containment Ventilation Isolated Due to Spike on Radiation Monitor,Constituting Unplanned Actuation of ESF Component.Special Test Developed & Performed During Refueling Outage 4 |
- on 911022,containment Ventilation Isolated Due to Spike on Radiation Monitor,Constituting Unplanned Actuation of ESF Component.Special Test Developed & Performed During Refueling Outage 4
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) |
| 05000400/LER-1991-020-01, :on 911204,discovered Deficiency in Radiation Surveillance Test Used for Leak Testing Sealed Sources to Satisfy TS Requirements.Caused by Procedural Deficiency. Procedure Revised & Training Provided |
- on 911204,discovered Deficiency in Radiation Surveillance Test Used for Leak Testing Sealed Sources to Satisfy TS Requirements.Caused by Procedural Deficiency. Procedure Revised & Training Provided
| 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2) |
| 05000400/LER-1991-021-01, :on 911218,error Discovered in Program Utilized to Determine Containment Sump in-leakage Flow Rate.Caused by Personnel Error During Computer Design Development.Erroneous Error Corrected & Event Reviewed |
- on 911218,error Discovered in Program Utilized to Determine Containment Sump in-leakage Flow Rate.Caused by Personnel Error During Computer Design Development.Erroneous Error Corrected & Event Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(o)(2) 10 CFR 50.73(o)(2)(v) |