| | | Reporting criterion |
|---|
| 05000387/LER-1985-001-01, :on 850213,while Removing Jumpers from Refuel Floor Wall Duct Trip Units,Zone III Isolated on High Radiation Signal.Caused by Reactor Bldg Recirculation Fans Not Starting.Investigation Continuing |
- on 850213,while Removing Jumpers from Refuel Floor Wall Duct Trip Units,Zone III Isolated on High Radiation Signal.Caused by Reactor Bldg Recirculation Fans Not Starting.Investigation Continuing
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-001, :on 850112,HPCI Turbine Failed to Trip During Hot Functional Test HF-252-011.Caused by Broken Stop Valve Actuator Shaft.Actuator Shaft Replaced |
- on 850112,HPCI Turbine Failed to Trip During Hot Functional Test HF-252-011.Caused by Broken Stop Valve Actuator Shaft.Actuator Shaft Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000387/LER-1985-002-01, :on 850121,diesel Generators a & D Failed to Start in Violation of Tech Spec Requirements.Caused by Cold Temp Problems.Diesel Generator Outside Air Supply Dampers Repaired |
- on 850121,diesel Generators a & D Failed to Start in Violation of Tech Spec Requirements.Caused by Cold Temp Problems.Diesel Generator Outside Air Supply Dampers Repaired
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1985-002, :on 850112,nonlicensed,nonutility Electrician Caused Reactor Protection Sys Motor Generator M-G Set to Trip When Wrench Came in Contact W/Energized Conductor. Caused by Failure to Isolate Equipment |
- on 850112,nonlicensed,nonutility Electrician Caused Reactor Protection Sys Motor Generator M-G Set to Trip When Wrench Came in Contact W/Energized Conductor. Caused by Failure to Isolate Equipment
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-003-01, :on 850124,unit Scrammed on Main Turbine Control Valve Fast Closure Signal Resulting from Main Generator Lockout.Caused by Ice Formations in Main Generator a & C Isophase Bus Ducts at Low Point in Ducts |
- on 850124,unit Scrammed on Main Turbine Control Valve Fast Closure Signal Resulting from Main Generator Lockout.Caused by Ice Formations in Main Generator a & C Isophase Bus Ducts at Low Point in Ducts
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-003, :on 850119,reactor Scrammed on Turbine Control Valve Fast Closure.Caused by Main Turbine Trip on High Vibration During Turbine Control Valve Testing.Vibration Reduced After Rebalancing |
- on 850119,reactor Scrammed on Turbine Control Valve Fast Closure.Caused by Main Turbine Trip on High Vibration During Turbine Control Valve Testing.Vibration Reduced After Rebalancing
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-004-01, :on 850129,diesel Generator B Tripped After 8 Minutes of Operation.Caused by Actuation of Connecting Rod Bearing High Temp Detector Vent Valve.Maint Personnel Will Perform Addl Insp |
- on 850129,diesel Generator B Tripped After 8 Minutes of Operation.Caused by Actuation of Connecting Rod Bearing High Temp Detector Vent Valve.Maint Personnel Will Perform Addl Insp
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1985-005, :on 850119,following Reactor Scram Due to Turbine High Vibration,Suppression Chamber Vacuum Breaker Surveillance Test Completed After Tech Spec Time Limit. Caused by Cognitive Error |
- on 850119,following Reactor Scram Due to Turbine High Vibration,Suppression Chamber Vacuum Breaker Surveillance Test Completed After Tech Spec Time Limit. Caused by Cognitive Error
| 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-005-01, :on 850213,verification of 6 Plus or Minus 1 Simulated Thermal Power Time Constant Inadvertently Omitted from Routine Surveillance Testing for Aprms.Time Constant Since Verified |
- on 850213,verification of 6 Plus or Minus 1 Simulated Thermal Power Time Constant Inadvertently Omitted from Routine Surveillance Testing for Aprms.Time Constant Since Verified
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1985-006, :on 850129,w/unit in Hot Shutdown,Rhr Sys Shutdown Cooling Suction Inboard Isolation Valve Closed Unexpectedly.Possibly Caused by Faulty Pressure Switch. Switch May Be Replaced Pending Evaluation |
- on 850129,w/unit in Hot Shutdown,Rhr Sys Shutdown Cooling Suction Inboard Isolation Valve Closed Unexpectedly.Possibly Caused by Faulty Pressure Switch. Switch May Be Replaced Pending Evaluation
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-006-01, :on 850213,monthly Composite Sample Analyses Not Completed.Caused by Dec Aliquots Added to Wrong Monthly Composite Container.Procedure Changes Made to Prevent Recurrence |
- on 850213,monthly Composite Sample Analyses Not Completed.Caused by Dec Aliquots Added to Wrong Monthly Composite Container.Procedure Changes Made to Prevent Recurrence
| 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-007-02, :on 850216,breaker Supplying Instrument Bus Opened,Causing Isolation of Reactor Water Cleanup Sys on False Signal.Caused by Loss of Power to Temp Sensor Trip Circuitry.Addl Training for Operators Provided |
- on 850216,breaker Supplying Instrument Bus Opened,Causing Isolation of Reactor Water Cleanup Sys on False Signal.Caused by Loss of Power to Temp Sensor Trip Circuitry.Addl Training for Operators Provided
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-007, :on 850129,RHR Sys Shutdown Cooling Suction Valve Closed Unexpectedly.Cause Not Stated.Pressure Switch Checked & Shutdown Cooling Established.Switch May Be Replaced Pending Evaluation |
- on 850129,RHR Sys Shutdown Cooling Suction Valve Closed Unexpectedly.Cause Not Stated.Pressure Switch Checked & Shutdown Cooling Established.Switch May Be Replaced Pending Evaluation
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-007-01, :on 850130,during Purge of Containment,One Train of Standby Gas Treatment Sys Became Inoperable.Caused by Annunciation of Standby Gas Treatment Sys B Heater Failure Alarm.Event Reviewed W/Operators |
- on 850130,during Purge of Containment,One Train of Standby Gas Treatment Sys Became Inoperable.Caused by Annunciation of Standby Gas Treatment Sys B Heater Failure Alarm.Event Reviewed W/Operators
| |
| 05000388/LER-1985-008, :on 850216,logic Power Lost to HPCI & Loop B of Core Spray.Caused by Broken Lug on Negative Terminal.Lug Replaced.Power Restored |
- on 850216,logic Power Lost to HPCI & Loop B of Core Spray.Caused by Broken Lug on Negative Terminal.Lug Replaced.Power Restored
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-008-01, :on 850302,standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Actuated.Caused by Electricians Working on Mod to Reactor Protection Sys B Alternate Power Source Transformer |
- on 850302,standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Actuated.Caused by Electricians Working on Mod to Reactor Protection Sys B Alternate Power Source Transformer
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-009, :on 850212,setpoints for Three Reactor Water Level Switches Found to Be Outside Acceptance Criteria During Performance of Scheduled Surveillance.Caused by Instrument Drift.Instruments Recalibr |
- on 850212,setpoints for Three Reactor Water Level Switches Found to Be Outside Acceptance Criteria During Performance of Scheduled Surveillance.Caused by Instrument Drift.Instruments Recalibr
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000387/LER-1985-009-01, :on 850310,11 & 28,inadvertent ESF Actuations Occurred.Caused by Welding in Vicinity of Detectors,Inducing Noise in Instrumentation.Radiation Loop Reset & Tested |
- on 850310,11 & 28,inadvertent ESF Actuations Occurred.Caused by Welding in Vicinity of Detectors,Inducing Noise in Instrumentation.Radiation Loop Reset & Tested
| |
| 05000387/LER-1985-010-01, :on 850313,during Cavity Draining Process, Refuel Floor High Exhaust Radiation Monitor Channel a Tripped.Caused by Shine Associated W/Lowering Reactor Cavity Water Level.Caution Added to Procedures |
- on 850313,during Cavity Draining Process, Refuel Floor High Exhaust Radiation Monitor Channel a Tripped.Caused by Shine Associated W/Lowering Reactor Cavity Water Level.Caution Added to Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-010, :on 850223,ESF Actuation Occurred.Caused by Tripped Reactor Protection Sys Power Supply Breaker.Breaker Reset & Affected Sys Restored |
- on 850223,ESF Actuation Occurred.Caused by Tripped Reactor Protection Sys Power Supply Breaker.Breaker Reset & Affected Sys Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-011-01, :on 850323 & 0402,refuel Floor Radiation Monitors Tripped & Started ESF Sys.Caused by Radiographic Testing.Esf Starts Unavoidable Due to Detector Location Near Testing.Testing Suspended & HVAC Sys Restored |
- on 850323 & 0402,refuel Floor Radiation Monitors Tripped & Started ESF Sys.Caused by Radiographic Testing.Esf Starts Unavoidable Due to Detector Location Near Testing.Testing Suspended & HVAC Sys Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-011, :on 850310,damper in Standby Gas Treatment Sys Train a Malfunctioned.Caused by Damaged Damper Actuator. Actuator Replaced & Damper Operation Verified to Be Correct on 850312 |
- on 850310,damper in Standby Gas Treatment Sys Train a Malfunctioned.Caused by Damaged Damper Actuator. Actuator Replaced & Damper Operation Verified to Be Correct on 850312
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-012, :on 850404,determined That Four Fire Dampers in Standby Gas Treatment Sys Ductwork Not Included in Surveillance Procedures & Fire Watch Not Verified.Fire Watch Implemented |
- on 850404,determined That Four Fire Dampers in Standby Gas Treatment Sys Ductwork Not Included in Surveillance Procedures & Fire Watch Not Verified.Fire Watch Implemented
| 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1985-012, :on 850316,power Supply to Standby Gas Treatment Sys Exhaust Vent Process Radiation Monitor Momentarily Shortened When Component Removed During Calibr. Caused by Malfunctioning Dampers |
- on 850316,power Supply to Standby Gas Treatment Sys Exhaust Vent Process Radiation Monitor Momentarily Shortened When Component Removed During Calibr. Caused by Malfunctioning Dampers
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-013-01, :on 850416,alternate Sampling for Turbine Bldg Lost Once & for Reactor Bldg Lost Twice.Caused by Circuit Overload,Resulting in Tripped Circuit Powering Sample Pumps. Alternate Power Supplies Being Investigated |
- on 850416,alternate Sampling for Turbine Bldg Lost Once & for Reactor Bldg Lost Twice.Caused by Circuit Overload,Resulting in Tripped Circuit Powering Sample Pumps. Alternate Power Supplies Being Investigated
| 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1985-013, :on 850327,standby Liquid Control Pump a Failed 92-day Flow Verification Surveillance Test.Caused by Faulty Suction & Discharge Valves Internal to Positive Displacement Pump.Repairs Completed |
- on 850327,standby Liquid Control Pump a Failed 92-day Flow Verification Surveillance Test.Caused by Faulty Suction & Discharge Valves Internal to Positive Displacement Pump.Repairs Completed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1985-014, :on 850417,RCIC Sys Inboard Steam Supply Valve Isolated on Equipment Area High Temp.Caused by Malfunction of Temp Indicating Switch E51-N600B.Switch Replaced on 850418 & Isolation Signal Cleared |
- on 850417,RCIC Sys Inboard Steam Supply Valve Isolated on Equipment Area High Temp.Caused by Malfunction of Temp Indicating Switch E51-N600B.Switch Replaced on 850418 & Isolation Signal Cleared
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-014-01, :on 850413,loss of Power Initiated Isolation of HVAC Zone III & Started Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Train A.Caused by Open Circuit Breaker.Breaker Closed |
- on 850413,loss of Power Initiated Isolation of HVAC Zone III & Started Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Train A.Caused by Open Circuit Breaker.Breaker Closed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-015-01, :on 850421,spray Pond Bypass Valve HV-01222A Did Not Automatically Open When Emergency Svc Water Pump a Started.Caused by Two Open Sliding States Link Terminal Blocks in Relay Panel.Links Evaluated |
- on 850421,spray Pond Bypass Valve HV-01222A Did Not Automatically Open When Emergency Svc Water Pump a Started.Caused by Two Open Sliding States Link Terminal Blocks in Relay Panel.Links Evaluated
| 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-015, :on 841213,portions of Upper Cable Spreading Room Structural Steel Found W/O Requisite 3 H Fire Proofing. Caused by Intentional Cutouts to Facilitate Installation. Fire Watch Established on 850409 |
- on 841213,portions of Upper Cable Spreading Room Structural Steel Found W/O Requisite 3 H Fire Proofing. Caused by Intentional Cutouts to Facilitate Installation. Fire Watch Established on 850409
| 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-016, :on 850425,five Emergency Svc Water & Control Structure Chilled Water Sys Suveillances Completed Late. Caused by Mods to Sys & Problems W/Weekly Surveillance Schedule.Schedule Revised |
- on 850425,five Emergency Svc Water & Control Structure Chilled Water Sys Suveillances Completed Late. Caused by Mods to Sys & Problems W/Weekly Surveillance Schedule.Schedule Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1985-016-01, :on 850427,water Hammer Caused Reactor Water Level Transient.Caused by Rapid Filling of Partially Drained RHR Piping from Reactor Vessel.Operating Procedure for RHR Being Revised |
- on 850427,water Hammer Caused Reactor Water Level Transient.Caused by Rapid Filling of Partially Drained RHR Piping from Reactor Vessel.Operating Procedure for RHR Being Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-017, :on 850505,reactor Water Cleanup Sys Containment Outboard Isolation Valve Closed on High Flow Signal Causing Unanticipated ESF Actuation.Caused by Higher Differential Pressure When Sys Runs Cold |
- on 850505,reactor Water Cleanup Sys Containment Outboard Isolation Valve Closed on High Flow Signal Causing Unanticipated ESF Actuation.Caused by Higher Differential Pressure When Sys Runs Cold
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-017-01, :on 850530,drywell Sump Inleakage of About 10 Gpm Caused Reactor Shutdown.Shutdown Completed on 850531. Caused by Severe Packing Leak in Reactor Recirculation Pump Discharge Bypass Valve A.Valve Repaired |
- on 850530,drywell Sump Inleakage of About 10 Gpm Caused Reactor Shutdown.Shutdown Completed on 850531. Caused by Severe Packing Leak in Reactor Recirculation Pump Discharge Bypass Valve A.Valve Repaired
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1985-018, :on 850529,circuit Breaker 8B in Reactor Protection Sys Distribution Panel 2Y201B Tripped.Caused by Loose Load Side Connection Leading to Overheating of Terminal Lug.Breaker Replaced |
- on 850529,circuit Breaker 8B in Reactor Protection Sys Distribution Panel 2Y201B Tripped.Caused by Loose Load Side Connection Leading to Overheating of Terminal Lug.Breaker Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-018, :on 850513 & 14,unanticipated Actuation of Reactor Protection Sys Ocurred When Intermediate Range Monitor Spuriously Tripped Upscale.Caused by Shorting Links Being Removed from Reactor Protection Sys |
- on 850513 & 14,unanticipated Actuation of Reactor Protection Sys Ocurred When Intermediate Range Monitor Spuriously Tripped Upscale.Caused by Shorting Links Being Removed from Reactor Protection Sys
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-018-01, :on 850529,three ESF Actuations Occurred Due to Tripping of Reactor Protection Sys Power Supply Breaker W/Unit at 100% Power.First Two Events Caused by Loose Connection.New Breaker Installed |
- on 850529,three ESF Actuations Occurred Due to Tripping of Reactor Protection Sys Power Supply Breaker W/Unit at 100% Power.First Two Events Caused by Loose Connection.New Breaker Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-019, :on 850516,reactor Protection Sys Actuation Occurred When Intermediate Range Monitor C Mistakenly Taken Out of Bypass.Caused by Telcon Misunderstanding.Personnel Counseled |
- on 850516,reactor Protection Sys Actuation Occurred When Intermediate Range Monitor C Mistakenly Taken Out of Bypass.Caused by Telcon Misunderstanding.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-019-01, :on 850524,Limiting Condition for Operation 3.0.3, Motherhood Clause, Declared & Standby Gas Treatment Sys Suction Ductwork Access Doors Opened.Entry Required to Perform Fire Damper Surveillance |
- on 850524,Limiting Condition for Operation 3.0.3, Motherhood Clause, Declared & Standby Gas Treatment Sys Suction Ductwork Access Doors Opened.Entry Required to Perform Fire Damper Surveillance
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1985-020-01, :on 850531,lightning Strike Caused Voltage Transient.Caused by Loss of Motive or Control Power. Malfunctioning Damper Actuator Replaced |
- on 850531,lightning Strike Caused Voltage Transient.Caused by Loss of Motive or Control Power. Malfunctioning Damper Actuator Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-021-01, :on 850630,neutral Overvoltage Occurred in Main Generator,Causing Primary Lockout.Caused by Failure of Phase C Main Transformer Low Voltage Bushing.Bushing Replaced W/Spare Component |
- on 850630,neutral Overvoltage Occurred in Main Generator,Causing Primary Lockout.Caused by Failure of Phase C Main Transformer Low Voltage Bushing.Bushing Replaced W/Spare Component
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-022, :on 850528,loss of Zone I & Zone III Reactor Bldg Ventilation Occurred,Causing Automatic ESF Actuation. Caused by Communication Error Between Personnel Conducting 18-month Logic Sys Test.Personnel Counseled |
- on 850528,loss of Zone I & Zone III Reactor Bldg Ventilation Occurred,Causing Automatic ESF Actuation. Caused by Communication Error Between Personnel Conducting 18-month Logic Sys Test.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-022-01, :on 850703,instrumentation & Controls Technician Inadvertently Connected Test Equipment to Electronics Module for Reactor Water Cleanup Sys.Technician Counseled.Rear Input Wires Labeled |
- on 850703,instrumentation & Controls Technician Inadvertently Connected Test Equipment to Electronics Module for Reactor Water Cleanup Sys.Technician Counseled.Rear Input Wires Labeled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-023-01, :on 850805,unit Scrammed Due to Turbine Control Valve Fast Closure Trip.Caused by Technician Error.Rcic Manually Initiated to Maintain Vessel Level.Special Rept to Be Filed Per Tech Spec 4.7.3d |
- on 850805,unit Scrammed Due to Turbine Control Valve Fast Closure Trip.Caused by Technician Error.Rcic Manually Initiated to Maintain Vessel Level.Special Rept to Be Filed Per Tech Spec 4.7.3d
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-023, :on 850611,manual Isolation Valve 141005 Found Open.Caused by Inability to Perform Required Surveillance Testing on Excess Flow Check Valve XV-141F009.Procedures Revised |
- on 850611,manual Isolation Valve 141005 Found Open.Caused by Inability to Perform Required Surveillance Testing on Excess Flow Check Valve XV-141F009.Procedures Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1985-024, :on 850609,HPCI Declared Inoperable Due to Inability to Meet Flow & Discharge Pressure Requirements. Caused by Incorrect High Speed Setting of Turbine Control Sys.High Level Signal cut-off Raised |
- on 850609,HPCI Declared Inoperable Due to Inability to Meet Flow & Discharge Pressure Requirements. Caused by Incorrect High Speed Setting of Turbine Control Sys.High Level Signal cut-off Raised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1985-024-01, :on 850807,reactor Water Cleanup Containment (RWCU) Inboard Isolation Valve Closed on High Sys Flow Signal.Caused by Fast Opening of Filter/Demineralizer Inlet Valve.Rwcu Operating Procedure Revised |
- on 850807,reactor Water Cleanup Containment (RWCU) Inboard Isolation Valve Closed on High Sys Flow Signal.Caused by Fast Opening of Filter/Demineralizer Inlet Valve.Rwcu Operating Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-025, :on 850619,B Trains of Standby Gas Treatment & Control Room Emergency Outside Air Supply Sys Actuated Due to Trip of Exhaust Duct Radiation Detector B.Caused by Buildup of Contaminated Particles |
- on 850619,B Trains of Standby Gas Treatment & Control Room Emergency Outside Air Supply Sys Actuated Due to Trip of Exhaust Duct Radiation Detector B.Caused by Buildup of Contaminated Particles
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1985-025-01, :on 851005,phase-to-ground Fault Occurred on 500 Kv Transmission Lines Due to Lightning Strike.Failure of Auxiliary Relay Resulted in Isolation of Generator.Caused by Stuck Relay.Relay Repaired |
- on 851005,phase-to-ground Fault Occurred on 500 Kv Transmission Lines Due to Lightning Strike.Failure of Auxiliary Relay Resulted in Isolation of Generator.Caused by Stuck Relay.Relay Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1985-026, :on 850624,during Testing of HPCI Sys,Oil Leak Discovered on HPCI Steam Stop Valve Oil Supply Flange. Caused by Loose Nuts Securing Stop Valve Oil Supply Flange. Nuts Torqued & Leak Test Performed |
- on 850624,during Testing of HPCI Sys,Oil Leak Discovered on HPCI Steam Stop Valve Oil Supply Flange. Caused by Loose Nuts Securing Stop Valve Oil Supply Flange. Nuts Torqued & Leak Test Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |