LER 80-013/01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to RefuelingML112900665 |
Person / Time |
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Site: |
Monticello |
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Issue date: |
03/21/1980 |
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From: |
Myrabo A Northern States Power Co |
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To: |
NRC/OI/RGN-III/FO |
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Shared Package |
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ML112900666 |
List: |
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References |
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LER-80-013-01T, LER-80-13-1T, NUDOCS 8003240564 |
Download: ML112900665 (4) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029C6921994-04-22022 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 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 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 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 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September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER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 ML1127601381978-12-15015 December 1978 LER#78-022/03L-0 on 781117:steam Leak Was Discovered in a 1 Wye Strainer,YS-4002,on the Main Steam Equalizer Drain Line. Leak Caused by a Defective Casting & Dev After Two Days of Svc ML1127601401978-12-14014 December 1978 LER#78-021/03L-0 on 781114:during Refueling Outage While Testing RHR SW Sys,A Pinhole Leak Was Discovered in CV-1729, RHR SW Differential Pressure Control Valve.Caused by Corrosion & Erosion of Upper Valve Body 1994-04-22
[Table view] Category:RO)
MONTHYEARML20029C6921994-04-22022 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 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 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 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 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 ML1127601381978-12-15015 December 1978 LER#78-022/03L-0 on 781117:steam Leak Was Discovered in a 1 Wye Strainer,YS-4002,on the Main Steam Equalizer Drain Line. Leak Caused by a Defective Casting & Dev After Two Days of Svc ML1127601401978-12-14014 December 1978 LER#78-021/03L-0 on 781114:during Refueling Outage While Testing RHR SW Sys,A Pinhole Leak Was Discovered in CV-1729, RHR SW Differential Pressure Control Valve.Caused by Corrosion & Erosion of Upper Valve Body 1994-04-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2061999-10-12012 October 1999 Safety Evaluation Supporting Amend 106 to License DPR-22 ML20217D1261999-09-30030 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 05000263/LER-1999-007, :on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With1999-07-0909 July 1999
- on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With
05000263/LER-1999-006-01, :on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With1999-07-0202 July 1999
- on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With
ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With 05000263/LER-1999-005, :on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With1999-06-0707 June 1999
- on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With
ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With 05000263/LER-1999-004-01, :on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With1999-05-24024 May 1999
- on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With
05000263/LER-1999-003-01, :on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With1999-05-12012 May 1999
- on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With
05000263/LER-1999-002-01, :on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With1999-05-11011 May 1999
- on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.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 ML20205C1651999-03-19019 March 1999 Safety Evaluation Supporting Amend 105 to License DPR-22 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 05000263/LER-1999-001-02, :on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With1999-03-17017 March 1999
- on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With
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 ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.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 ML20198M8221998-12-24024 December 1998 Safety Evaluation Supporting Amend 104 to License DPR-22 ML20198M6901998-12-23023 December 1998 Safety Evaluation Supporting Amend 103 to License DPR-22 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 05000263/LER-1998-005-01, :on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve1998-10-21021 October 1998
- on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve
05000263/LER-1998-004-02, :on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked1998-10-0909 October 1998
- on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked
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 ML20151T0981998-08-28028 August 1998 Safety Evaluation Supporting Amend 101 to License DPR-22 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 05000263/LER-1998-003-01, :on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced1998-05-14014 May 1998
- on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced
05000263/LER-1998-002-02, :on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed1998-05-14014 May 1998
- on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed
ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant 05000263/LER-1998-001-02, :on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment1998-04-22022 April 1998
- on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment
ML20217E9611998-04-20020 April 1998 Safety Evaluation Supporting Amend 100 to License DPR-22 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 1999-09-30
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REGULATORY oORMATION DISTRIBUTION SY-*M (RIDS)
ACCESSION NBR:8003240564 DOC,DATE: 80/03/21 NOTARIZED: NO DOCKET #
FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHOR AFFILIATION MYRABO,A,L, Northern States Power Co.
RECIP.NAME RECIPIENT AFFILIATION MYRA8OAL. Region 3, Chicago, Office of the Director
SUBJECT:
LER 80-013/01Tw0:on 800309,during refueling operationsrod withdrawn block not received when refueling bridge traversed core.Caused by actuating arm out of adjustmentComponents readjusted & interlocks tested prior to,refueling.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR . 1 ENCL 4 SIZE:._J J ...
TITLE: Incident Reports NOTES: ----------------------------.---------------------- -------------
RECIPIENT C OPIES RECIPIENT COPIES ID CODE/NAME L TTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC 4 4 INTERNAL: EG FIL 1 02 NRC PDR 1 1 09 2 11 MPA 3 3 14 TA/EDO 1 15 NOVAK/KNIEL 1 31 16 EES 1 17 AD FOR ENGR 1 1
18 PLANT SYS BR 1 19 I&C SYS BR 1 1 20 AD PLANT SYS 1 22 REAC SAFT BR 1 1
23 ENGR BR 1 24 KREGER 1 1 25 PWR SYS BR 1 26 AD/SITE ANAL 1 1 27 OPERA LIC BR 1 28 ACDENT ANLYS 1 29 AUX SYS BR 1 AD/ORP-DOR 1 1
AEOD 1 DOUG MAY-TERA 1 HANAUERrS, 1 IRELAND,R,. 3 3 JORDANE,/IE 1 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 29 ACRS 16 16 TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL 52
1" 0 4SIP 0 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 March 21, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen E11yn, IL 60137
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Refueling Rod Block Interlock Failure The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.
This event is reported 'in accordance with Technical Specification 6.7.B.1.g. in that the condition (limit switch out of adjustment) required refueling operations to be stopped in accordance with Technical Specification 3.10.A.
Yours very truly, N"
L 01 M Ma ager of Nuclear Support Services LOM/JAG/ak cc: &..Director, IE, USNRC (40)
Director, MIPC, USNRC (3)
MPCA Attn: J W Ferman
-over 75 0
NRC FORM 366 U. S. NUCLEAR ItEGULATO;IY COMMISSION (7-77)
LICENSEE EVENT REPORT CONTROL BLOCK: [ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
IMIN I MINI P1 110101 01 -ll 01ol olol-l ol ol@ 4 1 1111 11 0 LLJ0 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 8 9 LICENSEE CODE 14 15 CON'T REPORT RCEL j@1 05 1 01 0 1NUMBER 01 21 61 3() 01 31 01 91 81 01@1 0 3l1 2 1 8l1 7 8 60 61 DOCKET 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (3 lAt 0605, it was discovered that a rod withdrawal block was not received when the refi1-i ling bridge traversed the core during refueling operations. Technical Specification I 3.10.A requires the refueling interlocks to be operable during core alterations, InterF Ilocks had successfully been tested at 0400 the previous day. Records for that period confirmed that no control rods had been moved while fuel was moved. The event had no jeffect on the public health or safety. One previous occurrence. AO-75-02.
L 00 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE LF.LDJ@ LW1O@ LA] 12 I1INI SIT IRjU 13 18 19 L1 19 LzI@
20 7 8 9 10 11 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO. CODE TYPE NO.
8[ REPORTSI 1C1131 EUTAO O URRN R RVS 21 22 23 24 26 27 28 29 30 31 32 A"TION FUTURE EFFECT SHUTDOWN ATTACHMENT NPAD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM bUB. SUPPLIER MANUFACTURER IE1 33 34 F 35 z1 36 ZJO 10 l0 l0 l1 l 37 40 N
41 1Nj J 42 43 1j LG 44 108 10 l 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 2 S1 IRefueling operations were immediately stopped. Investigation revealed that the actu- I Iating arm of the limit .switch ( which opens when the bridge is over the core) was out I of adjustment, preventing the switch from operating properly. The components were I readjusted & interlocks tested prior to resuming refueling. Modifications of the j i components are being considered. METHO 7 8 9 80 FACILITY METHO 0 OF STATUS % POWER OTHER STATUS DISCOV ERY DISCOVERY DESCRIPTION LHH j0 10 10 1(51 1 NA I 4A (2i) Operator observation 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
[ D[6 1 Lz[J0l NA 1 1 NA l 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE. DESCRIPTION NA I 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION EEo1 010 @1 NA I 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION E
7 8 LJ@I 9 10 NA 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION 7 8 ILNJ1 9 10 NA 68 I l 69 IIl l I l I l l l l 80 0
NAME OF PREPARER A. IggbMyrabo PH 612/295-5151 x-266 "'
w 80032,A n5 /
NFAC FO RM 366 U. S. NUCLEAR IREUULAOU'iY COMMISSION rJi F C
CE NS3E E EVE NT R EPO0R T
- CONTROL BLOCK: OPLEASE
' PRINT OR TYPE AL L REQUIRED INFORMATION) 9 MAIN I MINI P il I 0 LICENSEE CODE 14 iS
-0 0,LICENSE NUMBER 01 c0 cII0-1014 10 25 26 1LICENSE 11 1O1O111OLLJ0 TYPE 30 57 CAT 6s CONT REPORT _L 01 510101 01 21 61 3)1 013101918 10 01312,1j.1.1D1j0o(
SOUR CE CLI\_________________
7 8 60 61 DOCKET NUMBER 6F 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES jAt 0605, it was discovered that a rod withdrawal block was not received when the refuel -1 ling bridge traversed the core during refueling oDerations. Technical Specification I 3 .10.A requires the refueling interlocks to be operable during core alterations. Interi jocks had successfully been tested at 0400 the previous day. Records for that period ponfirmed tt no c 1 os h-ad been mo.-ved~ w fulihile was moved. The event had no i ieffect on the public health or safety. One previous occurrence. AO-75-02.
H- I 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7
0 8 9 I D 10 LJ 11 Ll@j 12 II1NI SIT IR jU 1 LsJS 13 18 19 Lj@
20 OCCURRENCE REPORT REVISION SEQUENTIAL LE/OfEVENT YEAR REPORT NO. CODE TYPE NO.
0 1 1 31 L--- 1 01 1I LTJI 1---_ E REPORT N 21 8 22 23-- 24 26 27 28 29 30 31 32 A!TION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 0 F0E 34 I 35 Z] 00 6 36
( 37 l0 0 3Nj 0 40 41 I
42
[NN j 43 IG 1018 1010 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0 Refueling operations were immediately stopped. Investigation revealed that the actu- I lating arm of the limit switch ( which opens when the bridge is over the core) was out I 2of adjustment, preventing the switch from operating properly. The components were j 1 readjusted & interlocks tested prior to resuming refueling. Modifications of the I 4 components are being considered.
7 8 9 80 FACILITY METHOD OF STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 2 1 5 LJ 10 l10 10 15 NA I L J(3I Operator observation 7 B 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
_0I EI W 1G O LJ@ JgDlNA I @A NA 7 8 9 10 11 44 so PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7 8 9 1010 0 11 12 Z(a 13 NA 80 1
PERSONNEL INJURIES NUMBER DESCRIPTION 7 8 9 010 0 1 11 12 NA 80 1
LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION IDI Z 11 I 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION 7 N6 1A I 69l ll 7 8 9 10 68 69 80o 0
NAME OF PREPARER A. L. Myrabo PHONE: 612/295-5151 x-266 PHNE J--