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September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER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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