ML20044D538
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| ML20044D538 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/14/1993 |
| From: | Scott D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20044D531 | List: |
| References | |
| LER-89-040-01, LER-89-40-1, NUDOCS 9305190271 | |
| Download: ML20044D538 (2) | |
Similar Documents at Monticello | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML19346G9701994-07-19019 July 1994
[Table view]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 Category:RO) MONTHYEARML19346G9701994-07-19019 July 1994
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217D1261999-09-30030 September 1999
[Table view]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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