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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML19346G9701994-07-19019 July 1994 LER 94-006-00:on 940620,group 2 Isolation Occurred Due to Operator Turning Wrong Switch & Deenergizing Radiation Monitor.Operator Disciplined & Radiation Monitor Switches modified.W/940719 Ltr ML20029D7901994-05-0202 May 1994 LER 89-021-02:on 890916,crack Was Discovered on Upper Support Brace of One Jet Pump Riser.Caused by High Cycle Fatigue.Testing Has Demonstrated That Cracking Is Self limiting.W/940502 Ltr ML20029C7061994-04-22022 April 1994 LER 94-001-00:on 940323,missed Surveillance on SRV Low-Low Set Logic.Caused by Incorrect Surveillance Procedure Prerequisite.Corrective Action:Removed Incorrect Prerequisites,Trained on Procedure review.W/940422 Ltr ML20029C6921994-04-22022 April 1994 LER 94-002-00:on 940324,discovered That Breaker Tripped at Current Below Tolerance.Caused by Design of Breakers. Corrective Action:Circuit Breakers Revised for Further Classification for Testing Instantaneous trip.W/940422 Ltr ML20045G3241993-07-0606 July 1993 LER 93-007-00:on 930604,ESF Actuation Occurred Due to Loss of Reactor Protection Sys Power Supply.Replaced Failed Relay & Returned Motor Generator Set to svc.W/930706 Ltr ML20045B2601993-06-0909 June 1993 LER 93-006-01:on 930323,RPM Actuation Occurred from High Pressure Caused by Inadequate Procedure.Turbine Stop & Control Valve Tightness Test Procedures & Plant Simulator revised.W/930609 Ltr ML20044D5361993-04-14014 April 1993 LER 90-001-05:on 900313,design Deficiencies Noted in Emergency Filter Train Sys.On 930315,determined That Train B of CR Emergency Filtration Sys Could Not Provide Adequate Flow.Alternate Measuring Sys Method Implemented ML20044D5381993-04-14014 April 1993 LER 89-040-02:on 891219,secondary Containment Failed to Meet Operability Requirements During Special Test.Caused by Design Deficiencies.Operating Procedures Revised & Administrative Hold Placed on One Sys Component ML20024H2171991-05-22022 May 1991 LER 91-008-00:on 910422,cracking Discovered on Control Rod Drive Housing Flange Cap Screws.Caused by Inadequate Design of Screws.Four New,Original Equipment Cap Screws Installed & Reactor Vessel Hydro performed.W/910522 Ltr ML20028E8261983-01-21021 January 1983 LER 83-001/01T-0:on 830108,during Cold shutdown,post-LOCA Recombiner B Discharge Inboard Primary Containment Isolation Valve & Leak Test Valves Not Fully Closed.Caused by Contractor Error.Valves Closed ML20027D5031982-10-0909 October 1982 Updated LER 82-016/01T-1:on 821009,during Inservice Insp, Indication Found at 12 O'Clock Location on Recirculation safe-end to Pipe Weld E & at 3 O'Clock Location on 821020. Caused by Intergranular Stress Corrosion Cracking ML20052F9951982-05-0808 May 1982 LER 82-005/03L-0:on 820408,lead Lifted in Control Circuitry for Outboard Shutdown Cooling valve,MO-2030,rendering Valve Inoperable.Caused by Misinterpretation of Special Operating Procedure.Lead Reinstalled & Procedures Revised ML20052C2051982-04-23023 April 1982 LER 82-004/01T-0:on 820410,ASCO Inboard & Outboard Drywell Vent 3-way Solenoid Valves,Model 830064C64U,failed to Close Upon Hand Switch Activation When Coil de-energized.Probably Caused by Horizontally Mounted Solenoids.Valves Replaced ML20050B0531982-03-23023 March 1982 Updated LER 81-001/03X-1:on 810126,while Performing Surveillance Test Mo 2035,HPCI Outboard Steam Supply Isolation Valve Failed to Close.Caused by Opened Limitorque SMB-O,240-volt Dc & Torque Switches.Switches Replaced ML20042A4631982-03-12012 March 1982 LER 82-003/03L-0:on 820212,reactor Water Cleanup Primary Containment Inboard Isolation Valve MO-2397 Became Inoperable While in Full Open Position.Caused by Normally Energized Relay Coil 16A-K36 Shorting.Relay Replaced ML20040G7371982-02-0606 February 1982 LER 82-002/03L-0:on 820107,core Spray Pump 11 Start Time Delay Relay Failed to Operate.Caused by Loose Terminal Connection & Microswitch Contact Burned Open.New GE CR 2820 Relay Installed ML20040A5701982-01-15015 January 1982 LER 82-001/01T-0:on 820102,outboard Shutdown Cooling Suction Isolation Valve Found to Exceed Tech Spec Limits for Local Leak Rate Test.Caused by Valve Disc,Undersized by Extensive Lapping of Disc & Valve Body Seats,Traveling Too Far ML20039B2281981-12-10010 December 1981 LER 81-023/03L-0:on 811110,during Cold shutdown,4 Channel a Main Steam Line High Flow Switches Found Inoperable.Caused by Heating of Switching Element Due to Relay Coil Failure, Initially Reported in LER 81-021.Elements Replaced ML20027C2371981-08-24024 August 1981 LER 81-020/03L-0:on 810724,main Steam Leak Revealed in Drain Line to Condenser.Caused by Piping Leaking Immediately Downstream of 45 Degree Elbow Due to Erosion & Impingement Resulting from Steam & Water Flow from Restricting Orifice ML20009E4141981-07-20020 July 1981 LER 81-018/03L-0:on 810620,reactor Water Cleanup Sys Was Returned to Svc Following Maint W/Discharge Isolation Valve MO2399 Open & Inoperable.Caused by Torque Switch Failure. Motor & Torque Switch Replaced & Sys Returned to Svc ML20009D5671981-07-16016 July 1981 LER 81-017/03L-0:on 810617,cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup Heat Exchanger Piping,At Connection to Heat Exchanger.Caused by Poor fit-up & Welding Due to 3-inch Slag Line Near Root of Weld ML19332B3791980-09-22022 September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER 80-023/03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut ML1129007541980-06-26026 June 1980 LER 80-022/03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning ML1129007511980-06-12012 June 1980 LER 80-021/03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced ML1129007481980-06-0202 June 1980 Updated 79-015/03L-1:on 790712,during Routine Insp,Steam Leak from 13A Intermediate Pressure Feedwater Heater Was Detected.Insulation Removal Revealed through-wall Flaw in Heater Shell.Caused by erosion-corrosion ML1129007451980-05-27027 May 1980 LER 80-020/03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake ML1129007221980-05-0909 May 1980 LER 80-018/03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure ML1129007071980-04-11011 April 1980 LER 80-017/01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified ML1129006851980-04-10010 April 1980 LER 80-016/01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements ML1129006801980-03-27027 March 1980 LER 80-015/01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls ML1129006781980-03-26026 March 1980 LER 80-006/03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr ML1129006651980-03-21021 March 1980 LER 80-013/01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling ML1129006681980-03-20020 March 1980 LER 80-011/01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls ML1129006621980-03-14014 March 1980 LER 80-007/01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors ML1129009771980-01-18018 January 1980 LER 79-024/03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld ML1129009741980-01-14014 January 1980 Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review ML1129009551979-12-19019 December 1979 LER 79-021/03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts ML1129009031979-08-31031 August 1979 LER 79-017/03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage ML1129008891979-08-10010 August 1979 LER 79-015/03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell ML1129008831979-08-0707 August 1979 LER 79-013/03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced ML1129008801979-08-0606 August 1979 LER 79-014/03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired ML1129008771979-08-0101 August 1979 LER 79-012/03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced ML1129008561979-06-28028 June 1979 LER 79-011/03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line ML1127801511979-03-15015 March 1979 LER 79-003/01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled ML1127601481979-02-0909 February 1979 LER 79-002/03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error ML1127601201979-02-0202 February 1979 LER 79-001/03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 ML1127601181979-01-29029 January 1979 LER 78-016/03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device ML1127601131978-12-29029 December 1978 LER 78-030/01T-0 on 781218:during surveillance,MO-2-64A Recirculation Loop 11 Discharge Bypass Valve Would Not Close.Cause Is Unknown Due to Inaccessibility of Valve ML1127601431978-12-19019 December 1978 LER#78-028/03L-0 on 781124:during Normal Oper,Small Steam Leak Was Discovered in Weld of 45 Degree Elbow on HPCI Steam Supply Line 1 Inch Drain Line to Main Condenser Due to Corrrosion.Weld Repair Made at Leak.Awaiting Parts 1994-07-19
[Table view] Category:RO)
MONTHYEARML19346G9701994-07-19019 July 1994 LER 94-006-00:on 940620,group 2 Isolation Occurred Due to Operator Turning Wrong Switch & Deenergizing Radiation Monitor.Operator Disciplined & Radiation Monitor Switches modified.W/940719 Ltr ML20029D7901994-05-0202 May 1994 LER 89-021-02:on 890916,crack Was Discovered on Upper Support Brace of One Jet Pump Riser.Caused by High Cycle Fatigue.Testing Has Demonstrated That Cracking Is Self limiting.W/940502 Ltr ML20029C7061994-04-22022 April 1994 LER 94-001-00:on 940323,missed Surveillance on SRV Low-Low Set Logic.Caused by Incorrect Surveillance Procedure Prerequisite.Corrective Action:Removed Incorrect Prerequisites,Trained on Procedure review.W/940422 Ltr ML20029C6921994-04-22022 April 1994 LER 94-002-00:on 940324,discovered That Breaker Tripped at Current Below Tolerance.Caused by Design of Breakers. Corrective Action:Circuit Breakers Revised for Further Classification for Testing Instantaneous trip.W/940422 Ltr ML20045G3241993-07-0606 July 1993 LER 93-007-00:on 930604,ESF Actuation Occurred Due to Loss of Reactor Protection Sys Power Supply.Replaced Failed Relay & Returned Motor Generator Set to svc.W/930706 Ltr ML20045B2601993-06-0909 June 1993 LER 93-006-01:on 930323,RPM Actuation Occurred from High Pressure Caused by Inadequate Procedure.Turbine Stop & Control Valve Tightness Test Procedures & Plant Simulator revised.W/930609 Ltr ML20044D5361993-04-14014 April 1993 LER 90-001-05:on 900313,design Deficiencies Noted in Emergency Filter Train Sys.On 930315,determined That Train B of CR Emergency Filtration Sys Could Not Provide Adequate Flow.Alternate Measuring Sys Method Implemented ML20044D5381993-04-14014 April 1993 LER 89-040-02:on 891219,secondary Containment Failed to Meet Operability Requirements During Special Test.Caused by Design Deficiencies.Operating Procedures Revised & Administrative Hold Placed on One Sys Component ML20024H2171991-05-22022 May 1991 LER 91-008-00:on 910422,cracking Discovered on Control Rod Drive Housing Flange Cap Screws.Caused by Inadequate Design of Screws.Four New,Original Equipment Cap Screws Installed & Reactor Vessel Hydro performed.W/910522 Ltr ML20028E8261983-01-21021 January 1983 LER 83-001/01T-0:on 830108,during Cold shutdown,post-LOCA Recombiner B Discharge Inboard Primary Containment Isolation Valve & Leak Test Valves Not Fully Closed.Caused by Contractor Error.Valves Closed ML20027D5031982-10-0909 October 1982 Updated LER 82-016/01T-1:on 821009,during Inservice Insp, Indication Found at 12 O'Clock Location on Recirculation safe-end to Pipe Weld E & at 3 O'Clock Location on 821020. Caused by Intergranular Stress Corrosion Cracking ML20052F9951982-05-0808 May 1982 LER 82-005/03L-0:on 820408,lead Lifted in Control Circuitry for Outboard Shutdown Cooling valve,MO-2030,rendering Valve Inoperable.Caused by Misinterpretation of Special Operating Procedure.Lead Reinstalled & Procedures Revised ML20052C2051982-04-23023 April 1982 LER 82-004/01T-0:on 820410,ASCO Inboard & Outboard Drywell Vent 3-way Solenoid Valves,Model 830064C64U,failed to Close Upon Hand Switch Activation When Coil de-energized.Probably Caused by Horizontally Mounted Solenoids.Valves Replaced ML20050B0531982-03-23023 March 1982 Updated LER 81-001/03X-1:on 810126,while Performing Surveillance Test Mo 2035,HPCI Outboard Steam Supply Isolation Valve Failed to Close.Caused by Opened Limitorque SMB-O,240-volt Dc & Torque Switches.Switches Replaced ML20042A4631982-03-12012 March 1982 LER 82-003/03L-0:on 820212,reactor Water Cleanup Primary Containment Inboard Isolation Valve MO-2397 Became Inoperable While in Full Open Position.Caused by Normally Energized Relay Coil 16A-K36 Shorting.Relay Replaced ML20040G7371982-02-0606 February 1982 LER 82-002/03L-0:on 820107,core Spray Pump 11 Start Time Delay Relay Failed to Operate.Caused by Loose Terminal Connection & Microswitch Contact Burned Open.New GE CR 2820 Relay Installed ML20040A5701982-01-15015 January 1982 LER 82-001/01T-0:on 820102,outboard Shutdown Cooling Suction Isolation Valve Found to Exceed Tech Spec Limits for Local Leak Rate Test.Caused by Valve Disc,Undersized by Extensive Lapping of Disc & Valve Body Seats,Traveling Too Far ML20039B2281981-12-10010 December 1981 LER 81-023/03L-0:on 811110,during Cold shutdown,4 Channel a Main Steam Line High Flow Switches Found Inoperable.Caused by Heating of Switching Element Due to Relay Coil Failure, Initially Reported in LER 81-021.Elements Replaced ML20027C2371981-08-24024 August 1981 LER 81-020/03L-0:on 810724,main Steam Leak Revealed in Drain Line to Condenser.Caused by Piping Leaking Immediately Downstream of 45 Degree Elbow Due to Erosion & Impingement Resulting from Steam & Water Flow from Restricting Orifice ML20009E4141981-07-20020 July 1981 LER 81-018/03L-0:on 810620,reactor Water Cleanup Sys Was Returned to Svc Following Maint W/Discharge Isolation Valve MO2399 Open & Inoperable.Caused by Torque Switch Failure. Motor & Torque Switch Replaced & Sys Returned to Svc ML20009D5671981-07-16016 July 1981 LER 81-017/03L-0:on 810617,cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup Heat Exchanger Piping,At Connection to Heat Exchanger.Caused by Poor fit-up & Welding Due to 3-inch Slag Line Near Root of Weld ML19332B3791980-09-22022 September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER 80-023/03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut ML1129007541980-06-26026 June 1980 LER 80-022/03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning ML1129007511980-06-12012 June 1980 LER 80-021/03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced ML1129007481980-06-0202 June 1980 Updated 79-015/03L-1:on 790712,during Routine Insp,Steam Leak from 13A Intermediate Pressure Feedwater Heater Was Detected.Insulation Removal Revealed through-wall Flaw in Heater Shell.Caused by erosion-corrosion ML1129007451980-05-27027 May 1980 LER 80-020/03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake ML1129007221980-05-0909 May 1980 LER 80-018/03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure ML1129007071980-04-11011 April 1980 LER 80-017/01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified ML1129006851980-04-10010 April 1980 LER 80-016/01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements ML1129006801980-03-27027 March 1980 LER 80-015/01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls ML1129006781980-03-26026 March 1980 LER 80-006/03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr ML1129006651980-03-21021 March 1980 LER 80-013/01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling ML1129006681980-03-20020 March 1980 LER 80-011/01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls ML1129006621980-03-14014 March 1980 LER 80-007/01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors ML1129009771980-01-18018 January 1980 LER 79-024/03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld ML1129009741980-01-14014 January 1980 Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review ML1129009551979-12-19019 December 1979 LER 79-021/03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts ML1129009031979-08-31031 August 1979 LER 79-017/03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage ML1129008891979-08-10010 August 1979 LER 79-015/03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell ML1129008831979-08-0707 August 1979 LER 79-013/03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced ML1129008801979-08-0606 August 1979 LER 79-014/03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired ML1129008771979-08-0101 August 1979 LER 79-012/03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced ML1129008561979-06-28028 June 1979 LER 79-011/03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line ML1127801511979-03-15015 March 1979 LER 79-003/01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled ML1127601481979-02-0909 February 1979 LER 79-002/03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error ML1127601201979-02-0202 February 1979 LER 79-001/03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 ML1127601181979-01-29029 January 1979 LER 78-016/03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device ML1127601131978-12-29029 December 1978 LER 78-030/01T-0 on 781218:during surveillance,MO-2-64A Recirculation Loop 11 Discharge Bypass Valve Would Not Close.Cause Is Unknown Due to Inaccessibility of Valve ML1127601431978-12-19019 December 1978 LER#78-028/03L-0 on 781124:during Normal Oper,Small Steam Leak Was Discovered in Weld of 45 Degree Elbow on HPCI Steam Supply Line 1 Inch Drain Line to Main Condenser Due to Corrrosion.Weld Repair Made at Leak.Awaiting Parts 1994-07-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30
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4 Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 April 22, 1994 US Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 205;5 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Instantaneous Trip of 480 VAC MCCBs Do Not Meet Acceptance Criteria Due to Manufacturer's Desion The voluntary Licensee Event Report for this occurrence is attached. This letter contains no new NRC commitments, nor does it modify any prior commitments.
Please contact Marv Engen, Sr Licensing Engineer, at (612) 295-1291 if you require further information.
{
Roger O Anderson Director Licensing and Management Issues c Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota Attn: Kris Sanda l
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l MRC FORM* 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 r5M)
EXPIRES 5/31/95 EST! MATED BURDEN PER AESPONSE TO COMPLY WITH THis INT OPVATION COLLECTION REQUEST: 50.0 NRS. FOHWARD LICENSEE EVENT REPORT (LER) CCWNS REGMDING BURDEN EMNM TO NE WOHMATM AND RECORDS MANAGEMENT BRANCH (MNBB 77t4L U 5. NUCt'.AR REGULATORY CCMM6S10N. WASHINGTON, DC 2052 000 s, AN ) 10 THE PAFFTTWORK REPUCTION PROJECT {31540104, OF FiCf CF (See reverse for required number of digits / characters for each block) MANAGEMENT AND BUDGET, WASH!NGTON. DC 20503.
ECluTY NAME (t) DOCKET NMtBEH (2) PAGE (3)
MONTICELLO NUCLEAR GENERATING PLANT 05000 - 263 1 OF 5
" " ' Instantaneous Trip of 480 VAC MCCBs Do Not Meet Acceptance criterin Due to Manuhcturer's Desien EVENT DATE (5) LER NUMBER (6i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REVSON FAOLJYNAML DOCAEI NUMdEH MONTH DH YEAR YEAR "N" " "
P/ UMBER NUMBER 05000 I AQUI( NAME rX)CKET NUMBER
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03 24 94 94 002 00 04 22 94 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR i: (Check one or more) (11)
MODE (9) N 20 402(b) 20 405(c) 50 73(a H2)(iv) 73 71(b)
POWER 20 405(a)(1)(i) 50.36(c)(1) 50 73(a)(2)(v) 73.71(c)
LEVEL (10) 100 20 405(a)(1)(ii) 50.36!c)(2) 50.73(a)(2)(vul D OTHER 20.405(a)(1)(m) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) M*W 'n Atext 20 405(aM1)(iv) 50 73(a)(2)(ii) 50.73(a)(2)(vhi)(B) r 3 A) 20 405(a)(1)(v) 50.73(a)(2)(m) 50.73(a)(2)(x) Voluntary Rg :
LICENSEE CONTACT FOR THIS LER (12)
NAW TU.UNUNE NUV&H pnude Aies Coce)
Steve Porter (612) 295-1497 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SV57t M COMPCN NT MANUF ACTURE P CAUSE SYS'E M COMF'ONE NT MANUFACTURER O PD SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MON'" D" *R vEs SUBMISSION P yn, c<ma rwEcTEo susM:ssioN DATo X DATE (15)
ABSTRACT (Um:t to 1400 spaces,i e, approximately 15 single spaced typewritten lines) (16) l During routine plant preventative maintenance testing of a Klockner Moeller 480 VAC 3 phase molded case circuit breakers, it was discovered that the breaker tripped at a current below the lower tolerance for the instantaneous trip. Spare breakers of the same model number produced similar test results.
The tests results were verified by an independent testing laboratory. The cause is believed to be the design of the breakers. In all cases, sufficient
- margin exists above requirements to ensure successful load operation. Motor starting, reduced voltage conditions, and fuse / breaker coordination were all considered. This report is a voluntary report as this issue caused no safety problem at Monticello. An Institute For Nuclear Power Operations - Nuclear Network item was issued on March 28, 1994 to inform the industry of this issue.
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I NRC FORM 366 (S 971 i
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BLOCK NUMBER OF TITLE NUMBER DIGITS / CHARACTERS 1 UP TO 46 FACILITY NAME 2 DOCKET NUMBER 3 IN ADDITION TO 05000 3 VARIES PAGE NUMBER' f
4 UP TO 76 '{
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSicil APPROVED BY OMB NO. 3150-0104 i is-ori ll EXPlRES 5/31/95 -l ESTIMATED BURDEN PER RESPONSE TO COMPLY WrTH THIS INFORMATION COLLE73ON REQUEST 50 0 HRS. FORWARD
' LICENSEE EVENT REPORT (LER) COvvENTS ReaAnD:No BURDEN ESTiuiTE To rHE NFORuAToN TEXT CONTINUATION AND REC R S MANA EMENT B%CH MBS WWS. WCLEAR RuGUULTORY COMM:SSoN.1AASHINGTON. DC 20S55 0001, AND TO THE PAPERWORK REDUCToN PROJECT (3t50 0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON DC 205c3 F ACluTY NAME (1) DOCKET NUMBER (2) LER NUMBER W PAGE (3)
$EQUENhAi HE VISION NUMBER NUMBER 05000 - 263 OF Monticello Nuclear Generating Plant 94 - 002 -
00 2 5 TEXT pt more space us renwec, use envocat comes of NHC form assA; (17}
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Description:
On March 24, 1994, the plant was operating at 100% power when an anomaly associated with Klockner Moeller molded case circuit breaker (MCCBs)(EIIS Component Function Identifier - 52) was discovered. While performing routine testing of a class lE 480 VAC three phase, Klockner Moeller molded case circuit breaker (Model Number ZM6-33-200. obi-CNA, purchased in 1982), it was i observed that adjustment of the instantaneous trip (magnetic trip) did not result in the expected trip setpoint response.
During subsequent testing of the instantaneous trip, breakers were found to deviate from the trip setpoint at higher settings. The deviation was small for low set points and increased as the setpoint was increased (See attached Figure). The results were consistent for each pole (phase) tested. Spcre breakers of the same model number were tested; all of which produced nearly identical results. Two additional Klockner Moeller molded case circuit breaker models (including a breaker procured in 1993) were tested and exhibited similar characteristics. These other models, however, were not outside of allowed tolerances. The testing was performed by experienced plant electricians in accordance with the requirements of UL (Underwriters Laboratory) Standard 489. The results were confirmed by an independent testing laboratory.
These Klockner Moeller molded case circuit breakers are used in essential 4
motor control centers (EIIS System Code - EC). All essential Klockner Moeller molded case circuit breakers are included in the Monticello preventative maintenance program. This provides assurance that any future problems will also be identified.
Cause:
1 The primary cause of this event is believed to be the design of the molded case circuit breaker. All Klockner Moeller 480 VAC molded case circuit breakers exhibited the trend shown in the attached figure. The trend was consistent between phases, models and manufacturing period. Breakers manufactured by others did not exhibit this trend. The issue identified does not appear to be the result of degrading equipment. Breakers procured in 1993 j exhibited similar characteristics to those procured in 1982. Test data taken j in 1982 appears to correspond to current data. Test results were very consistent from pole to pole and from breaker to breaker. These facts lead to the conclusion that age is not a cause of this characteristic.
I NRC FORM M6A (5 92;
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 pri EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY Wf7H TH!S INFORMATcN COLLECTcN REQUEST: 60.0 HRS. FORWARD
' LICENSEE EVENT REPORT (LER) COMvENTS REoARoiNa BURDEN ESTiuATE TO THE i~FORuATcN TEXT CONTINUATION AN REC R S MANA EMENT BRANCH NNBB 7M4W5. NUCLEAR HEGULATORY COMMIS$cN, WASHINGTON DC 20555-0001. AND TO THE PAPERWORK REDUCTcN PRCUECT (3150-c1041 OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON. DC 20503 F ACluTY NAME D) DOCKET NUMBER (2) LER NUMBER (s) PAGE (3)
YEAR NUMBEA NUMBER 05000 - 263 OF Monticello Nuclear Generating Plant 94 - 002 -
00 3 5 Text g,,no,. ue. w<.e . .ouer cep... or usc *orm asuf o r, A contributing cause was the inadequate acceptance criteria specified during the initial motor control center breaker installation. During installation in 1982, the acceptance band provided was the adjustable range for the instantaneous over current trip, rather than being a function of the established retpoint. This inadequate acceptance criteria prevented the condition f: m being identified during initial motor control center breaker installatior.. Current acceptance testing methods would identify this problem.
The condition could have been identified during the 1991 breaker testing.
However, the testing procedure lacked sufficient detailed guidance to identify the anomaly.
Analysis:
The report is a voluntary report as this issue caused no safety problem at Monticello. It could, however, be of interest to the NRC. An Institute For Nuclear Power Operations - Nuclear Network item was issued on March 28, 1994 to inform the industry of this issue.
The discrepancy identified exists only where the instantaneous setpoint is set above the minimum setting. At settings greater than minimum, the trip would occur at currents below the setting. The primary concern of breakers tripping early (at a lower current than desired) is the resultant loss of equipment when no fault or electrical problem exists, for example, during a pump start.
Therefore, a review was conducted of those Klockner Moeller molded case circuit breakers with the instantaneous trip setpoints greater than minimum. l In all cases, sufficient margin exists al.c n requirements to ensure successful load operation even with the setpoint at minimum. Motor starting, reduced i voltage conditions, and fuse / breaker coordination were all considered. j Load operability has been demonstrated numerous times since the Klockner Moeller molded case circuit breakers were installed. Loads supplied by the molded case circuit breakers have been started many times for surveillance procedures. No problem with these breakers tripping unnecessarily has occurred. Operating history, therefore, provides further assurance of load operability. !
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NRC FORM 366A (542) j l
6 NGC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 5 82)
EXPIRES 5/31/95 ESTIMATCD BURDEN PER RESPONSE TO COMPLY wrTH THt$
INFORMATION COLLECTON REQUEST: 60 0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMvEes REGAc~G BuRoEN ESTiuATE TO inE woRuATON TEXT CONTINUATION AND REC R S MANA EMEW BRANCH ABB MHWS NUCLEAR REGULATORY COMMISSON, WASMrNGTON, DC 70$$50001. AND TO THE PAPERWORK REDUCTON PRCUECT (31504104. OFFICE OF MANAGEMENT AND BVDGET, W ASHINGTON. DC 70503 FACIUTY NAME (1) DOCAET NUMBER (2) LiR NUMBER (s) PAGE (3)
. aON YEAR NUMBER NUMBER 05000 - 263 Or Monticello Nuclear Generating Plant 94 - 002 -
00 4 5 TEXT ta we wace vowee. vue manova; cap.n or Nac rann asui o rp Corrective Action:
- 1) The industry was informed of this event via Nuclear Network.
- 2) Klockner.Moeller was informed of this issue and a breaker was shipped to them for testing. ,
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- 3) An independent laboratory has confirmed our test results on a Model ZM6-33-200. obi-CNA breaker.
- 4) The preventative maintenance procedure for the 480 VAC molded case circuit breakers was revised for further clarification for testing the instantaneous trip.
Additional Information: 1 Failed Component Identification: NONE Previous Similar Event: NONE j
ARC FORM 366A (S 92)
f,JRC FONM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 WS4 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WfTH THIS INFORMATON COLLECTON REQUEST; 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARCHNG BURDEN ESTIMATE TO THE INFORMATON TEXT CONTINUATION AND RECORDS MANAGEMENT B@NCH (MN89 7714). U S. NUCLEAR REcutATORv CoMuissON, wAsHiNoTON, oc rossS.cooi ANo TO THE PAPERWORK REDUCTION PROJECT (31504104), OFFICE OF M ANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
F ACILITY NAME (1) DOCKET NUMBEH (2) LER NUMBER (s) PAGE (3)
SEQUENllAL REVISOrd YUR NUMBER NUMBER 05000 - 263 OF Monticello Nuclear Generating Plant 94 - 002 -
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