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| 05000382/LER-1989-002-01, Forwards LER 89-002-01.Submittal of LER Delayed from 891109 Due to Extenuating Circumstances | Forwards LER 89-002-01.Submittal of LER Delayed from 891109 Due to Extenuating Circumstances | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000382/LER-1989-002, :on 890125,personnel Discovered Discrepancy W/ Safety Classification of Instrument Air Tubing That Supplies Actuators of Safety Injection Sump Outlet Isolation Valves. Caused by Insufficient Documentation |
- on 890125,personnel Discovered Discrepancy W/ Safety Classification of Instrument Air Tubing That Supplies Actuators of Safety Injection Sump Outlet Isolation Valves. Caused by Insufficient Documentation
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000382/LER-1989-003, :on 890204,operators Inadvertently Allowed LPSI Pump B to Start During Testing.Caused by Personnel Error.Personnel Responsible Counseled to Be More Cautious & Thorough Approach When Following Procedures |
- on 890204,operators Inadvertently Allowed LPSI Pump B to Start During Testing.Caused by Personnel Error.Personnel Responsible Counseled to Be More Cautious & Thorough Approach When Following Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000382/LER-1989-004, :on 890303,personnel Noted That Essential Chiller a Experiencing Problems Maintaining Chilled Water Temp.Caused by Small Crack in Low Pressure Valve Ball Float. Unit Shut Down for Maint.Chiller a Replaced |
- on 890303,personnel Noted That Essential Chiller a Experiencing Problems Maintaining Chilled Water Temp.Caused by Small Crack in Low Pressure Valve Ball Float. Unit Shut Down for Maint.Chiller a Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000382/LER-1989-005, :on 890222,Limiting Condition for Operation Action 3.8.1.1 Not Performed When Component Cooling Water Pump a Temporarily Removed from Svc.Caused by Misapplication of Terms Operable & Operability |
- on 890222,Limiting Condition for Operation Action 3.8.1.1 Not Performed When Component Cooling Water Pump a Temporarily Removed from Svc.Caused by Misapplication of Terms Operable & Operability
| 10 CFR 50.73(a)(2)(i) |
| 05000382/LER-1989-006, :on 870105,discovered That Two Manual Isolation Valves Were Shown to Be Normally Open on Design Drawings. Caused by Programmatic Breakdown in Administrative Controls. Valves Closed & Design Drawings Revised |
- on 870105,discovered That Two Manual Isolation Valves Were Shown to Be Normally Open on Design Drawings. Caused by Programmatic Breakdown in Administrative Controls. Valves Closed & Design Drawings Revised
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000382/LER-1989-007, :on 841218 & 890331,inadequate Design of Air Accumulators Allowed Plant to Operate in Unanalyzed Condition Since Initial Startup.Caused by Inadequate Review of Design Requirements.Accumlators Modified |
- on 841218 & 890331,inadequate Design of Air Accumulators Allowed Plant to Operate in Unanalyzed Condition Since Initial Startup.Caused by Inadequate Review of Design Requirements.Accumlators Modified
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000382/LER-1989-008, :on 890426,emergency Diesel Generator Fuel Oil Not Being Sampled,Per ASTM Specified Methods.Caused by Inadequate Procedure as to Tech Spec Requirements.Sampling Procedure Revised to Conform w/ASTM-D270 |
- on 890426,emergency Diesel Generator Fuel Oil Not Being Sampled,Per ASTM Specified Methods.Caused by Inadequate Procedure as to Tech Spec Requirements.Sampling Procedure Revised to Conform w/ASTM-D270
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-009, :on 890504,discovered Discrepancy W/Steam Generator Eddy Current Test Results from Second Refuel Outage.Caused by Personnel Error & Inadequate Administrative Controls.Selection Process Will Be Revised |
- on 890504,discovered Discrepancy W/Steam Generator Eddy Current Test Results from Second Refuel Outage.Caused by Personnel Error & Inadequate Administrative Controls.Selection Process Will Be Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000382/LER-1989-010, :on 890520,determined That Low Recirculation Flow Not Included in Pump Operability Which Resulted in Noncompliance W/Tech Spec 4.0.5.Caused by Miscommunication. Procedures Revised |
- on 890520,determined That Low Recirculation Flow Not Included in Pump Operability Which Resulted in Noncompliance W/Tech Spec 4.0.5.Caused by Miscommunication. Procedures Revised
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-011, :on 890516,discovered Fuel Handling Bldg Normal Ventialtion Exhaust Radiation Monitor B Indicated Zero Process Flow.Caused by Intermittent Equipment Failure.Closer Monitoring of Radiation Sys Stressed |
- on 890516,discovered Fuel Handling Bldg Normal Ventialtion Exhaust Radiation Monitor B Indicated Zero Process Flow.Caused by Intermittent Equipment Failure.Closer Monitoring of Radiation Sys Stressed
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-012, :on 890706,health Physics Technician Noted That Liquid Waste Mgt Sys Effluent Radiation Monitor Sample Pump Not Operating During Radioactive Release of Waste Condensate Tank A.Caused by Inadequate Review of Software |
- on 890706,health Physics Technician Noted That Liquid Waste Mgt Sys Effluent Radiation Monitor Sample Pump Not Operating During Radioactive Release of Waste Condensate Tank A.Caused by Inadequate Review of Software
| 10 CFR 50.73(a)(2)(i) |
| 05000382/LER-1989-013, :on 890719,rapidly Decreasing Level Observed in Steam Generator 1 Resulting in Manual Reactor Trip.Caused by Circuit Failure in Position Control Circuitry.Circuit Card W/Failed Component Replaced & Sys Restored |
- on 890719,rapidly Decreasing Level Observed in Steam Generator 1 Resulting in Manual Reactor Trip.Caused by Circuit Failure in Position Control Circuitry.Circuit Card W/Failed Component Replaced & Sys Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000382/LER-1989-014, :on 890718,discovered That Plant Operated in Condition Prohibited by Tech Specs Re Cooling Water Valves. Caused by Inadequate Review of ASME Section Xi.Concluded That Valves Operable |
- on 890718,discovered That Plant Operated in Condition Prohibited by Tech Specs Re Cooling Water Valves. Caused by Inadequate Review of ASME Section Xi.Concluded That Valves Operable
| 10 CFR 50.73(a)(2)(i) |
| 05000382/LER-1989-015, :on 890728,containment Isolation Valve Found Inoperable Due to Inadequate Design & Procedure.Relay Test Procedure Revised & Sys Evaluated to Minimize Water Hammer Effects |
- on 890728,containment Isolation Valve Found Inoperable Due to Inadequate Design & Procedure.Relay Test Procedure Revised & Sys Evaluated to Minimize Water Hammer Effects
| 10 CFR 50.73(a)(2) |
| 05000382/LER-1989-016, :on 890802 & 04,loss of Electrical Power to Fuel Handling Bldg Isolation Radiation Monitor Resulted in Automatic Starts of Train B Filtration Unit.Caused by Personnel Error.Electrical Power Restored |
- on 890802 & 04,loss of Electrical Power to Fuel Handling Bldg Isolation Radiation Monitor Resulted in Automatic Starts of Train B Filtration Unit.Caused by Personnel Error.Electrical Power Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000382/LER-1989-017, :on 890819,automatic Reactor Trip of Unit Occurred While Operating at 23% Power.Caused by Equipment Malfunction.Repairs Made to Control Element Assembly Circuitry |
- on 890819,automatic Reactor Trip of Unit Occurred While Operating at 23% Power.Caused by Equipment Malfunction.Repairs Made to Control Element Assembly Circuitry
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000382/LER-1989-018, :on 890921,while Testing Main Steam Safety Valve,Lift Pressure Found to Be Below Tech Spec Allowable Value.Caused by Error in Judgement by Plant Supervisors. Event Will Be Discussed by Superintendent |
- on 890921,while Testing Main Steam Safety Valve,Lift Pressure Found to Be Below Tech Spec Allowable Value.Caused by Error in Judgement by Plant Supervisors. Event Will Be Discussed by Superintendent
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-019, :on 891012,4.16-kV Bus 3A2 Metering Potential Transformer Fuse Door Inadvertently Opened,Causing Feeder Breaker & Supply Breaker to Open & Load Sequencer to Reset. Caused by Personnel Error.Drawers Relabeled |
- on 891012,4.16-kV Bus 3A2 Metering Potential Transformer Fuse Door Inadvertently Opened,Causing Feeder Breaker & Supply Breaker to Open & Load Sequencer to Reset. Caused by Personnel Error.Drawers Relabeled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000382/LER-1989-020, :on 891031,containment Fan Cooler C Motor Ran in Reverse Direction Reducing Air Flow & Cooling Capacity. Caused by Personnel Not Performing Surveillance Testing. Motor Rewired for Correct Slow Speed Operation |
- on 891031,containment Fan Cooler C Motor Ran in Reverse Direction Reducing Air Flow & Cooling Capacity. Caused by Personnel Not Performing Surveillance Testing. Motor Rewired for Correct Slow Speed Operation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000382/LER-1989-021, :on 891116,emergency Diesel Generator a Declared Inoperable When Essential Svcs Chiller a Declared Inoperable W/O Verifying Availability of Offsite Ac Power. Caused by Personnel Error.Supervisor Counseled |
- on 891116,emergency Diesel Generator a Declared Inoperable When Essential Svcs Chiller a Declared Inoperable W/O Verifying Availability of Offsite Ac Power. Caused by Personnel Error.Supervisor Counseled
| 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-022, :on 891128,plant Operated in Condition Prohibited by Tech Specs When Emergency Diesel Generator a Inoperable More than 24 H.Caused by Personnel Error.Ltr Issued to All Shift Supervisors |
- on 891128,plant Operated in Condition Prohibited by Tech Specs When Emergency Diesel Generator a Inoperable More than 24 H.Caused by Personnel Error.Ltr Issued to All Shift Supervisors
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000382/LER-1989-023, :on 890927,MSIV 2MS-124B,determined to Have Broken Stem.Caused by MSIV Hydraulic Control Unit Thermal Valve Leakage.Replacement MSIV Stems W/Increased Blend Radius Designed to Decrease Stress Installed |
- on 890927,MSIV 2MS-124B,determined to Have Broken Stem.Caused by MSIV Hydraulic Control Unit Thermal Valve Leakage.Replacement MSIV Stems W/Increased Blend Radius Designed to Decrease Stress Installed
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| 05000382/LER-1989-024, :on 891223,reactor Trip Occurred Due to Loss of Feedwater Flow to Steam Generator.Caused by Anomaly in MFRV Pneumatic Control Sys Aggravated by Cold Water.Ia Task Force Reassembled |
- on 891223,reactor Trip Occurred Due to Loss of Feedwater Flow to Steam Generator.Caused by Anomaly in MFRV Pneumatic Control Sys Aggravated by Cold Water.Ia Task Force Reassembled
| 10 CFR 50.73(a)(2)(iv), System Actuation |