| | | Reporting criterion |
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| 05000259/LER-1984-001, :on 840103,RHR Pump 1D Started W/O Receiving Automatic Signal or Manual Start Signal from Control Room. Caused by Laborers Performing Decontamination Work.Laborers Cautioned |
- on 840103,RHR Pump 1D Started W/O Receiving Automatic Signal or Manual Start Signal from Control Room. Caused by Laborers Performing Decontamination Work.Laborers Cautioned
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-001-01, :on 840103,during Monthly Operability Test, Diesel Generator 3ED Overheated.Caused by Overchlorination of Emergency Equipment Cooling Water Sys Header.Main Header Piping Flushed |
- on 840103,during Monthly Operability Test, Diesel Generator 3ED Overheated.Caused by Overchlorination of Emergency Equipment Cooling Water Sys Header.Main Header Piping Flushed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000260/LER-1984-001, :on 840108,during RCIC Flow Testing,Rcic Failed to Reach Rated Flow in Required 30 S.Caused by Probable Setpoint Drift.Electronic Governor Control Sys Recalibr |
- on 840108,during RCIC Flow Testing,Rcic Failed to Reach Rated Flow in Required 30 S.Caused by Probable Setpoint Drift.Electronic Governor Control Sys Recalibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000296/LER-1984-001, :on 840103,emergency Diesel Generator Overheated.Caused by Clam Shells Blocking Emergency Equipment Cooling Water Sys Inlet Tube Sheet.Flushing of Main Header Established |
- on 840103,emergency Diesel Generator Overheated.Caused by Clam Shells Blocking Emergency Equipment Cooling Water Sys Inlet Tube Sheet.Flushing of Main Header Established
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000259/LER-1984-002-05, :on 840103,setpoint Value of Pressure Switches PS-64-57A-D Found Above Tech Spec 3.2.B. Limits.Caused by Static O-ring Model 12N-AA4 Setpoint Drift.Switches Recalibr.Surveillance Test Revised |
- on 840103,setpoint Value of Pressure Switches PS-64-57A-D Found Above Tech Spec 3.2.B. Limits.Caused by Static O-ring Model 12N-AA4 Setpoint Drift.Switches Recalibr.Surveillance Test Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000260/LER-1984-002-01, :on 840121,during Surveillance Testing,Operator Did Not Ensure Channel B Primary Containment Isolation Sys Reset Before Testing Channel C.Caused by Operator Error. Operator Counseled |
- on 840121,during Surveillance Testing,Operator Did Not Ensure Channel B Primary Containment Isolation Sys Reset Before Testing Channel C.Caused by Operator Error. Operator Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-002-03, :on 840125,Div I Logic Initiated & Secondary Containment Isolation Alarms Received.Caused by Primary Logic Relay Failing in Conservative Direction.Relays Replaced & Div Logic Returned to Svc |
- on 840125,Div I Logic Initiated & Secondary Containment Isolation Alarms Received.Caused by Primary Logic Relay Failing in Conservative Direction.Relays Replaced & Div Logic Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000259/LER-1984-002, LER BFRO-50-259/84006 Will Not Be Used.Event Being Combined W/Ler 50-296/84002 | LER BFRO-50-259/84006 Will Not Be Used.Event Being Combined W/Ler 50-296/84002 | |
| 05000259/LER-1984-003-01, :on 840117,during Testing of Standby Gas Treatment (SBGT) Trains,One of Three Trains Had Flow Below Design Due to Misadjusted Discharge Dampers on Trains a & C. Cause of Misalignment Unknown |
- on 840117,during Testing of Standby Gas Treatment (SBGT) Trains,One of Three Trains Had Flow Below Design Due to Misadjusted Discharge Dampers on Trains a & C. Cause of Misalignment Unknown
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000259/LER-1984-003, :on 840117,one of Three Standby Gas Treatment Trains Had Flow Below Design.Caused by Manual Discharge Dampers on Trains a & C Being Off Marked Positions.Dampers Returned to Proper Positions |
- on 840117,one of Three Standby Gas Treatment Trains Had Flow Below Design.Caused by Manual Discharge Dampers on Trains a & C Being Off Marked Positions.Dampers Returned to Proper Positions
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000296/LER-1984-003-03, :on 840129,during Transfer of 4 Kv Start Bus 1B from Alternate to Normal Feed,Normal Feed Breaker Failed to Close,Resulting in Momentary Loss of Voltage & Automatic Start of Diesel Generators 3C & 3D |
- on 840129,during Transfer of 4 Kv Start Bus 1B from Alternate to Normal Feed,Normal Feed Breaker Failed to Close,Resulting in Momentary Loss of Voltage & Automatic Start of Diesel Generators 3C & 3D
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000260/LER-1984-003-04, :on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment |
- on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000260/LER-1984-004-03, :on 840222,during Startup,Reactor Scrammed. Caused by High Flux Spike on Channels C & F of Intermediate Range Monitors.Plant Written Procedures & Nuclear Engineer Qualification Program Revised |
- on 840222,during Startup,Reactor Scrammed. Caused by High Flux Spike on Channels C & F of Intermediate Range Monitors.Plant Written Procedures & Nuclear Engineer Qualification Program Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-004-01, Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl | Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000296/LER-1984-004-02, :on 840228,RHR Outboard Loop II Isolation Valve Steam Found Broken.Probably Caused by Overstress or Extreme Load.Limitorque,Limitorque Switches & Valve Discs Investigated.Followup Rept by 840615 |
- on 840228,RHR Outboard Loop II Isolation Valve Steam Found Broken.Probably Caused by Overstress or Extreme Load.Limitorque,Limitorque Switches & Valve Discs Investigated.Followup Rept by 840615
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000259/LER-1984-004, :on 840106,during Manual Shutdown of Main Turbine,Control Rods Inserted to Reduce Power.Reactor Mode Switch Moved from Run to Startup,Resulting in Half Scram. Caused by Personnel Error.Personnel Counseled |
- on 840106,during Manual Shutdown of Main Turbine,Control Rods Inserted to Reduce Power.Reactor Mode Switch Moved from Run to Startup,Resulting in Half Scram. Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(1) |
| 05000259/LER-1984-004-01, Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override | Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override | 10 CFR 50.73(a)(2)(1) |
| 05000260/LER-1984-005-04, :on 840525,RHR Pump 2C Started Inadvertently While Performing Surveillance Instruction 4.2.B.45A.Caused by Operator Error & Poorly Written Procedure.Procedure & Similar Instructions Will Be Revised |
- on 840525,RHR Pump 2C Started Inadvertently While Performing Surveillance Instruction 4.2.B.45A.Caused by Operator Error & Poorly Written Procedure.Procedure & Similar Instructions Will Be Revised
| |
| 05000296/LER-1984-005-02, :on 840402,during Induction Heat Stress Improvement Program,Linear Root Indication in Heat Affected Zone Found on 6-inch Pipe Weld in Reactor Water Cleanup Sys. Cause Undetermined.Weld Will Be Left as Is |
- on 840402,during Induction Heat Stress Improvement Program,Linear Root Indication in Heat Affected Zone Found on 6-inch Pipe Weld in Reactor Water Cleanup Sys. Cause Undetermined.Weld Will Be Left as Is
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000259/LER-1984-005-01, :on 840122,during Surveillance Testing, Setpoints for Pressure Switches PS-64-56B & C Not within Tech Spec 3.2.A Limits.Caused by Setpoint Drift.Procedures Revised |
- on 840122,during Surveillance Testing, Setpoints for Pressure Switches PS-64-56B & C Not within Tech Spec 3.2.A Limits.Caused by Setpoint Drift.Procedures Revised
| |
| 05000296/LER-1984-006, :on 840517,welds Inspected on Jet Pump Instrument Nozzles.Two Welds Needed Repair.Welds Will Be Repaired by Overlay Procedure Prior to Startup.Insp Plan Underway During Refueling Outage |
- on 840517,welds Inspected on Jet Pump Instrument Nozzles.Two Welds Needed Repair.Welds Will Be Repaired by Overlay Procedure Prior to Startup.Insp Plan Underway During Refueling Outage
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000260/LER-1984-006-03, :on 840616,reactor Scrammed When Main Turbine Tripped on False Main Turbine Oil Tank Low Level Signal. Caused by Inadvertent Actuation of Oil Tank Level Switch. Procedure OI-47 Revised |
- on 840616,reactor Scrammed When Main Turbine Tripped on False Main Turbine Oil Tank Low Level Signal. Caused by Inadvertent Actuation of Oil Tank Level Switch. Procedure OI-47 Revised
| |
| 05000296/LER-1984-006-02, :on 840517,two Welds on Jet Pump Instrument Nozzles Determined to Need Repair.Caused by High Carbon Content,Leading to More Susceptibility for Sensitization Areas.Weld Will Be Repaired Prior to Startup |
- on 840517,two Welds on Jet Pump Instrument Nozzles Determined to Need Repair.Caused by High Carbon Content,Leading to More Susceptibility for Sensitization Areas.Weld Will Be Repaired Prior to Startup
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000259/LER-1984-007-01, Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised | Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000296/LER-1984-007-03, :on 840616,during Performance of Special Electrical Maint Instruction 37,diesel Generator 3B Inadvertently Started.Caused by Personnel Error &/Or Procedural Deficiency.Procedure Revised |
- on 840616,during Performance of Special Electrical Maint Instruction 37,diesel Generator 3B Inadvertently Started.Caused by Personnel Error &/Or Procedural Deficiency.Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000260/LER-1984-007-04, :on 840922,MSIVs B & C Had Excessive Leakage Above Tech Spec Limits.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating. Also Reportable Per Part 21 |
- on 840922,MSIVs B & C Had Excessive Leakage Above Tech Spec Limits.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating. Also Reportable Per Part 21
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000296/LER-1984-007-01, :on 840616,diesel Generator 3B Inadvertently Started During Performance of Maint Instruction 37.Caused by Two Relays Shorting Together.Caused by Personnel Error & Procedural Deficiency.Procedure Revised |
- on 840616,diesel Generator 3B Inadvertently Started During Performance of Maint Instruction 37.Caused by Two Relays Shorting Together.Caused by Personnel Error & Procedural Deficiency.Procedure Revised
| |
| 05000260/LER-1984-007-02, :on 840922,excessive Leakage Occurred on Main Steam Line Isolation Valves B & C.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating & Acceptable Leakage |
- on 840922,excessive Leakage Occurred on Main Steam Line Isolation Valves B & C.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating & Acceptable Leakage
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| 05000296/LER-1984-008-03, :on 840727,during Core Spray Logic Functional Test Surveillance Instruction,All Eight Diesel Generators Started.Caused by Improper Interpretation & Use of Procedure Instructions.Generators Reset to Standby |
- on 840727,during Core Spray Logic Functional Test Surveillance Instruction,All Eight Diesel Generators Started.Caused by Improper Interpretation & Use of Procedure Instructions.Generators Reset to Standby
| |
| 05000260/LER-1984-008-04, :on 841129,IGSCC Indications Found in Recirculation Piping Reactor Water Cleanup Piping & Jet Pump Instrument Nozzles.Affected Welds Will Be Repaired Before Startup |
- on 841129,IGSCC Indications Found in Recirculation Piping Reactor Water Cleanup Piping & Jet Pump Instrument Nozzles.Affected Welds Will Be Repaired Before Startup
| |
| 05000259/LER-1984-008, :on 840129,trouble Alarms Annunciated in Reactor Protection Sys Analog Trip Units Due to Downscale Failure of Differential Transmitters.Caused by Instrument Sensing Line Snubbers.Snubbers Removed |
- on 840129,trouble Alarms Annunciated in Reactor Protection Sys Analog Trip Units Due to Downscale Failure of Differential Transmitters.Caused by Instrument Sensing Line Snubbers.Snubbers Removed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000259/LER-1984-008-01, :on 840129,during Normal Operation,One or More Pressure Differential Transmitter Instrumentation 1-25A Through D Failed in Downscale Direction,Causing Trouble Alarm.Cause Unknown.Instruments Recalibr |
- on 840129,during Normal Operation,One or More Pressure Differential Transmitter Instrumentation 1-25A Through D Failed in Downscale Direction,Causing Trouble Alarm.Cause Unknown.Instruments Recalibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000259/LER-1984-009, :on 840130,factor Kf Used in Critical Power Ratio Calculations by Process Computer in Error by Approx 2.5% at Recirculation Flows of Approx 75%.Caused by Loading Core Dump Generated Prior to Factor Correction w/840217 Ltr |
- on 840130,factor Kf Used in Critical Power Ratio Calculations by Process Computer in Error by Approx 2.5% at Recirculation Flows of Approx 75%.Caused by Loading Core Dump Generated Prior to Factor Correction w/840217 Ltr
| 10 CFR 50.73(a)(2) |
| 05000296/LER-1984-009-03, :on 840913,RHR Pumps,Core Spray Pumps & Emergency Diesel Generators Inadvertently Started During Surveillance Testing.Caused by Improper Instrument Isolation by Personnel During Test |
- on 840913,RHR Pumps,Core Spray Pumps & Emergency Diesel Generators Inadvertently Started During Surveillance Testing.Caused by Improper Instrument Isolation by Personnel During Test
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-010-04, :on 841010,during Surveillance Test on Diesel Generators,Electrician Accidently Bumped Logic Relay in Testing Relay Panel & Two Diesel Generators Received Start Signals.Personnel Counseled |
- on 841010,during Surveillance Test on Diesel Generators,Electrician Accidently Bumped Logic Relay in Testing Relay Panel & Two Diesel Generators Received Start Signals.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000259/LER-1984-010-01, :on 840203,operator Observed hydrogen-oxygen Analyzer B Isolated.Caused by Faulty Group 6 Isolation Relay Signal.Signal Reset & Hi & Low Relays Replaced |
- on 840203,operator Observed hydrogen-oxygen Analyzer B Isolated.Caused by Faulty Group 6 Isolation Relay Signal.Signal Reset & Hi & Low Relays Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-011-03, :on 841002,RHR Testable Check Valves FCV-74-68 & 54 Failed Local Leak Rate Test.Caused by Misalignment of Valve Disc & Seating Surfaces Due to Hinge Arm End Play. Valves Modified.Also Reportable Per Part 21 |
- on 841002,RHR Testable Check Valves FCV-74-68 & 54 Failed Local Leak Rate Test.Caused by Misalignment of Valve Disc & Seating Surfaces Due to Hinge Arm End Play. Valves Modified.Also Reportable Per Part 21
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000259/LER-1984-011-01, :on 840209,during Routine Surveillance Testing, Automatic Scram Initiated.Caused by Failure of MSIV Dc Solenoid.Failure Considered Random Event.Solenoid Coils Checked Weekly for Operability |
- on 840209,during Routine Surveillance Testing, Automatic Scram Initiated.Caused by Failure of MSIV Dc Solenoid.Failure Considered Random Event.Solenoid Coils Checked Weekly for Operability
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000259/LER-1984-012, :on 840214,alert Declared.Caused by Unavailability of Shutdown Cooling Sys Due to Failure of Phase B Winding of Motor on Valve FCV-74-48.Alert Canceled After Valve Opened Manually.Shutdown Restored |
- on 840214,alert Declared.Caused by Unavailability of Shutdown Cooling Sys Due to Failure of Phase B Winding of Motor on Valve FCV-74-48.Alert Canceled After Valve Opened Manually.Shutdown Restored
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| 05000259/LER-1984-012-01, :on 840214,RHR Valve FCV-1-74-48 Failed to Open,Making Normal Method Cold Shutdown Impossible to Achieve.Possibly Caused by Failure of Phase B Motor Winding. Next Rept Will Be Submitted by 840901 |
- on 840214,RHR Valve FCV-1-74-48 Failed to Open,Making Normal Method Cold Shutdown Impossible to Achieve.Possibly Caused by Failure of Phase B Motor Winding. Next Rept Will Be Submitted by 840901
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| 05000296/LER-1984-012-03, :on 841120,reactor Scrammed by Reactor Operator When Control Room Indication Showed Low Water Level Scram Setpoint Exceeded.Caused by Procedural Inadequacy.Procedures Revised |
- on 841120,reactor Scrammed by Reactor Operator When Control Room Indication Showed Low Water Level Scram Setpoint Exceeded.Caused by Procedural Inadequacy.Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-013-03, :on 841122,HPCI Inoperable When Outboard Steam Supply Isolation Valve Failed to Open.Caused by Motor Pinion Gear to Isolation Valve Being Installed Backwards. Gears Correctly Repositioned |
- on 841122,HPCI Inoperable When Outboard Steam Supply Isolation Valve Failed to Open.Caused by Motor Pinion Gear to Isolation Valve Being Installed Backwards. Gears Correctly Repositioned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000259/LER-1984-013-01, :on 840213,air & Vacuum Release Valves Found Underrated for Surge Check Valve Svc Application.Caused by Misapplication of Valve.New Valves,W/Proper Design & Pressure Rating,Installed |
- on 840213,air & Vacuum Release Valves Found Underrated for Surge Check Valve Svc Application.Caused by Misapplication of Valve.New Valves,W/Proper Design & Pressure Rating,Installed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000296/LER-1984-013, :on 841122,during Startup After Cycle 5 Refueling,Hpci Outboard Steam Supply Isolation Valve Failed to Open.Caused by Motor Pinion Gears Being Installed Backwards.Gears Replaced in Proper Direction |
- on 841122,during Startup After Cycle 5 Refueling,Hpci Outboard Steam Supply Isolation Valve Failed to Open.Caused by Motor Pinion Gears Being Installed Backwards.Gears Replaced in Proper Direction
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000296/LER-1984-013-01, :on 841122,during Startup After Cycle 5 Refueling Outage,Hpci Outboard Steam Supply Isolation Valve Would Not Open,Rendering HPCI Sys Inoperable.Caused by Motor Pinion Gear Installed Backwards |
- on 841122,during Startup After Cycle 5 Refueling Outage,Hpci Outboard Steam Supply Isolation Valve Would Not Open,Rendering HPCI Sys Inoperable.Caused by Motor Pinion Gear Installed Backwards
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000296/LER-1984-014-02, :on 841206,split Ring,Retaining Ring & Snap Ring Missing from Limitorque Valve Operator.Retaining Rings for Worn Shaft Gear Installed.Operator & Drive Motor Reassembled |
- on 841206,split Ring,Retaining Ring & Snap Ring Missing from Limitorque Valve Operator.Retaining Rings for Worn Shaft Gear Installed.Operator & Drive Motor Reassembled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000259/LER-1984-014-01, Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised | Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised | |
| 05000259/LER-1984-014, :on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/ Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Will Be Revised |
- on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/ Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Will Be Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000296/LER-1984-015-03, :on 841209,manual Scram of Reactor Occurred When Feeder Breaker for Condensate Pump Motor 3A Failed to Trip.Caused by Burned Up Trip Coil.Condensate Pump Breaker & Motor Repaired |
- on 841209,manual Scram of Reactor Occurred When Feeder Breaker for Condensate Pump Motor 3A Failed to Trip.Caused by Burned Up Trip Coil.Condensate Pump Breaker & Motor Repaired
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| 05000259/LER-1984-016-01, :on 840229,while at 95% Power,During Installation of Ground Connector on Reactor Protection Panel 25-6B,w/common Leg to Panel 25-183,unit Scrammed. Caused by Vibration During Installation |
- on 840229,while at 95% Power,During Installation of Ground Connector on Reactor Protection Panel 25-6B,w/common Leg to Panel 25-183,unit Scrammed. Caused by Vibration During Installation
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