|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML19346G9701994-07-19019 July 1994 LER 94-006-00:on 940620,group 2 Isolation Occurred Due to Operator Turning Wrong Switch & Deenergizing Radiation Monitor.Operator Disciplined & Radiation Monitor Switches modified.W/940719 Ltr ML20029D7901994-05-0202 May 1994 LER 89-021-02:on 890916,crack Was Discovered on Upper Support Brace of One Jet Pump Riser.Caused by High Cycle Fatigue.Testing Has Demonstrated That Cracking Is Self limiting.W/940502 Ltr ML20029C7061994-04-22022 April 1994 LER 94-001-00:on 940323,missed Surveillance on SRV Low-Low Set Logic.Caused by Incorrect Surveillance Procedure Prerequisite.Corrective Action:Removed Incorrect Prerequisites,Trained on Procedure review.W/940422 Ltr ML20029C6921994-04-22022 April 1994 LER 94-002-00:on 940324,discovered That Breaker Tripped at Current Below Tolerance.Caused by Design of Breakers. Corrective Action:Circuit Breakers Revised for Further Classification for Testing Instantaneous trip.W/940422 Ltr ML20045G3241993-07-0606 July 1993 LER 93-007-00:on 930604,ESF Actuation Occurred Due to Loss of Reactor Protection Sys Power Supply.Replaced Failed Relay & Returned Motor Generator Set to svc.W/930706 Ltr ML20045B2601993-06-0909 June 1993 LER 93-006-01:on 930323,RPM Actuation Occurred from High Pressure Caused by Inadequate Procedure.Turbine Stop & Control Valve Tightness Test Procedures & Plant Simulator revised.W/930609 Ltr ML20044D5361993-04-14014 April 1993 LER 90-001-05:on 900313,design Deficiencies Noted in Emergency Filter Train Sys.On 930315,determined That Train B of CR Emergency Filtration Sys Could Not Provide Adequate Flow.Alternate Measuring Sys Method Implemented ML20044D5381993-04-14014 April 1993 LER 89-040-02:on 891219,secondary Containment Failed to Meet Operability Requirements During Special Test.Caused by Design Deficiencies.Operating Procedures Revised & Administrative Hold Placed on One Sys Component ML20024H2171991-05-22022 May 1991 LER 91-008-00:on 910422,cracking Discovered on Control Rod Drive Housing Flange Cap Screws.Caused by Inadequate Design of Screws.Four New,Original Equipment Cap Screws Installed & Reactor Vessel Hydro performed.W/910522 Ltr ML20028E8261983-01-21021 January 1983 LER 83-001/01T-0:on 830108,during Cold shutdown,post-LOCA Recombiner B Discharge Inboard Primary Containment Isolation Valve & Leak Test Valves Not Fully Closed.Caused by Contractor Error.Valves Closed ML20027D5031982-10-0909 October 1982 Updated LER 82-016/01T-1:on 821009,during Inservice Insp, Indication Found at 12 O'Clock Location on Recirculation safe-end to Pipe Weld E & at 3 O'Clock Location on 821020. Caused by Intergranular Stress Corrosion Cracking ML20052F9951982-05-0808 May 1982 LER 82-005/03L-0:on 820408,lead Lifted in Control Circuitry for Outboard Shutdown Cooling valve,MO-2030,rendering Valve Inoperable.Caused by Misinterpretation of Special Operating Procedure.Lead Reinstalled & Procedures Revised ML20052C2051982-04-23023 April 1982 LER 82-004/01T-0:on 820410,ASCO Inboard & Outboard Drywell Vent 3-way Solenoid Valves,Model 830064C64U,failed to Close Upon Hand Switch Activation When Coil de-energized.Probably Caused by Horizontally Mounted Solenoids.Valves Replaced ML20050B0531982-03-23023 March 1982 Updated LER 81-001/03X-1:on 810126,while Performing Surveillance Test Mo 2035,HPCI Outboard Steam Supply Isolation Valve Failed to Close.Caused by Opened Limitorque SMB-O,240-volt Dc & Torque Switches.Switches Replaced ML20042A4631982-03-12012 March 1982 LER 82-003/03L-0:on 820212,reactor Water Cleanup Primary Containment Inboard Isolation Valve MO-2397 Became Inoperable While in Full Open Position.Caused by Normally Energized Relay Coil 16A-K36 Shorting.Relay Replaced ML20040G7371982-02-0606 February 1982 LER 82-002/03L-0:on 820107,core Spray Pump 11 Start Time Delay Relay Failed to Operate.Caused by Loose Terminal Connection & Microswitch Contact Burned Open.New GE CR 2820 Relay Installed ML20040A5701982-01-15015 January 1982 LER 82-001/01T-0:on 820102,outboard Shutdown Cooling Suction Isolation Valve Found to Exceed Tech Spec Limits for Local Leak Rate Test.Caused by Valve Disc,Undersized by Extensive Lapping of Disc & Valve Body Seats,Traveling Too Far ML20039B2281981-12-10010 December 1981 LER 81-023/03L-0:on 811110,during Cold shutdown,4 Channel a Main Steam Line High Flow Switches Found Inoperable.Caused by Heating of Switching Element Due to Relay Coil Failure, Initially Reported in LER 81-021.Elements Replaced ML20027C2371981-08-24024 August 1981 LER 81-020/03L-0:on 810724,main Steam Leak Revealed in Drain Line to Condenser.Caused by Piping Leaking Immediately Downstream of 45 Degree Elbow Due to Erosion & Impingement Resulting from Steam & Water Flow from Restricting Orifice ML20009E4141981-07-20020 July 1981 LER 81-018/03L-0:on 810620,reactor Water Cleanup Sys Was Returned to Svc Following Maint W/Discharge Isolation Valve MO2399 Open & Inoperable.Caused by Torque Switch Failure. Motor & Torque Switch Replaced & Sys Returned to Svc ML20009D5671981-07-16016 July 1981 LER 81-017/03L-0:on 810617,cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup Heat Exchanger Piping,At Connection to Heat Exchanger.Caused by Poor fit-up & Welding Due to 3-inch Slag Line Near Root of Weld ML19332B3791980-09-22022 September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER 80-023/03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut ML1129007541980-06-26026 June 1980 LER 80-022/03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning ML1129007511980-06-12012 June 1980 LER 80-021/03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced ML1129007481980-06-0202 June 1980 Updated 79-015/03L-1:on 790712,during Routine Insp,Steam Leak from 13A Intermediate Pressure Feedwater Heater Was Detected.Insulation Removal Revealed through-wall Flaw in Heater Shell.Caused by erosion-corrosion ML1129007451980-05-27027 May 1980 LER 80-020/03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake ML1129007221980-05-0909 May 1980 LER 80-018/03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure ML1129007071980-04-11011 April 1980 LER 80-017/01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified ML1129006851980-04-10010 April 1980 LER 80-016/01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements ML1129006801980-03-27027 March 1980 LER 80-015/01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls ML1129006781980-03-26026 March 1980 LER 80-006/03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr ML1129006651980-03-21021 March 1980 LER 80-013/01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling ML1129006681980-03-20020 March 1980 LER 80-011/01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls ML1129006621980-03-14014 March 1980 LER 80-007/01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors ML1129009771980-01-18018 January 1980 LER 79-024/03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld ML1129009741980-01-14014 January 1980 Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review ML1129009551979-12-19019 December 1979 LER 79-021/03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts ML1129009031979-08-31031 August 1979 LER 79-017/03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage ML1129008891979-08-10010 August 1979 LER 79-015/03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell ML1129008831979-08-0707 August 1979 LER 79-013/03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced ML1129008801979-08-0606 August 1979 LER 79-014/03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired ML1129008771979-08-0101 August 1979 LER 79-012/03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced ML1129008561979-06-28028 June 1979 LER 79-011/03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line ML1127801511979-03-15015 March 1979 LER 79-003/01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled ML1127601481979-02-0909 February 1979 LER 79-002/03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error ML1127601201979-02-0202 February 1979 LER 79-001/03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 ML1127601181979-01-29029 January 1979 LER 78-016/03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device ML1127601131978-12-29029 December 1978 LER 78-030/01T-0 on 781218:during surveillance,MO-2-64A Recirculation Loop 11 Discharge Bypass Valve Would Not Close.Cause Is Unknown Due to Inaccessibility of Valve ML1127601431978-12-19019 December 1978 LER#78-028/03L-0 on 781124:during Normal Oper,Small Steam Leak Was Discovered in Weld of 45 Degree Elbow on HPCI Steam Supply Line 1 Inch Drain Line to Main Condenser Due to Corrrosion.Weld Repair Made at Leak.Awaiting Parts 1994-07-19
[Table view] Category:RO)
MONTHYEARML19346G9701994-07-19019 July 1994 LER 94-006-00:on 940620,group 2 Isolation Occurred Due to Operator Turning Wrong Switch & Deenergizing Radiation Monitor.Operator Disciplined & Radiation Monitor Switches modified.W/940719 Ltr ML20029D7901994-05-0202 May 1994 LER 89-021-02:on 890916,crack Was Discovered on Upper Support Brace of One Jet Pump Riser.Caused by High Cycle Fatigue.Testing Has Demonstrated That Cracking Is Self limiting.W/940502 Ltr ML20029C7061994-04-22022 April 1994 LER 94-001-00:on 940323,missed Surveillance on SRV Low-Low Set Logic.Caused by Incorrect Surveillance Procedure Prerequisite.Corrective Action:Removed Incorrect Prerequisites,Trained on Procedure review.W/940422 Ltr ML20029C6921994-04-22022 April 1994 LER 94-002-00:on 940324,discovered That Breaker Tripped at Current Below Tolerance.Caused by Design of Breakers. Corrective Action:Circuit Breakers Revised for Further Classification for Testing Instantaneous trip.W/940422 Ltr ML20045G3241993-07-0606 July 1993 LER 93-007-00:on 930604,ESF Actuation Occurred Due to Loss of Reactor Protection Sys Power Supply.Replaced Failed Relay & Returned Motor Generator Set to svc.W/930706 Ltr ML20045B2601993-06-0909 June 1993 LER 93-006-01:on 930323,RPM Actuation Occurred from High Pressure Caused by Inadequate Procedure.Turbine Stop & Control Valve Tightness Test Procedures & Plant Simulator revised.W/930609 Ltr ML20044D5361993-04-14014 April 1993 LER 90-001-05:on 900313,design Deficiencies Noted in Emergency Filter Train Sys.On 930315,determined That Train B of CR Emergency Filtration Sys Could Not Provide Adequate Flow.Alternate Measuring Sys Method Implemented ML20044D5381993-04-14014 April 1993 LER 89-040-02:on 891219,secondary Containment Failed to Meet Operability Requirements During Special Test.Caused by Design Deficiencies.Operating Procedures Revised & Administrative Hold Placed on One Sys Component ML20024H2171991-05-22022 May 1991 LER 91-008-00:on 910422,cracking Discovered on Control Rod Drive Housing Flange Cap Screws.Caused by Inadequate Design of Screws.Four New,Original Equipment Cap Screws Installed & Reactor Vessel Hydro performed.W/910522 Ltr ML20028E8261983-01-21021 January 1983 LER 83-001/01T-0:on 830108,during Cold shutdown,post-LOCA Recombiner B Discharge Inboard Primary Containment Isolation Valve & Leak Test Valves Not Fully Closed.Caused by Contractor Error.Valves Closed ML20027D5031982-10-0909 October 1982 Updated LER 82-016/01T-1:on 821009,during Inservice Insp, Indication Found at 12 O'Clock Location on Recirculation safe-end to Pipe Weld E & at 3 O'Clock Location on 821020. Caused by Intergranular Stress Corrosion Cracking ML20052F9951982-05-0808 May 1982 LER 82-005/03L-0:on 820408,lead Lifted in Control Circuitry for Outboard Shutdown Cooling valve,MO-2030,rendering Valve Inoperable.Caused by Misinterpretation of Special Operating Procedure.Lead Reinstalled & Procedures Revised ML20052C2051982-04-23023 April 1982 LER 82-004/01T-0:on 820410,ASCO Inboard & Outboard Drywell Vent 3-way Solenoid Valves,Model 830064C64U,failed to Close Upon Hand Switch Activation When Coil de-energized.Probably Caused by Horizontally Mounted Solenoids.Valves Replaced ML20050B0531982-03-23023 March 1982 Updated LER 81-001/03X-1:on 810126,while Performing Surveillance Test Mo 2035,HPCI Outboard Steam Supply Isolation Valve Failed to Close.Caused by Opened Limitorque SMB-O,240-volt Dc & Torque Switches.Switches Replaced ML20042A4631982-03-12012 March 1982 LER 82-003/03L-0:on 820212,reactor Water Cleanup Primary Containment Inboard Isolation Valve MO-2397 Became Inoperable While in Full Open Position.Caused by Normally Energized Relay Coil 16A-K36 Shorting.Relay Replaced ML20040G7371982-02-0606 February 1982 LER 82-002/03L-0:on 820107,core Spray Pump 11 Start Time Delay Relay Failed to Operate.Caused by Loose Terminal Connection & Microswitch Contact Burned Open.New GE CR 2820 Relay Installed ML20040A5701982-01-15015 January 1982 LER 82-001/01T-0:on 820102,outboard Shutdown Cooling Suction Isolation Valve Found to Exceed Tech Spec Limits for Local Leak Rate Test.Caused by Valve Disc,Undersized by Extensive Lapping of Disc & Valve Body Seats,Traveling Too Far ML20039B2281981-12-10010 December 1981 LER 81-023/03L-0:on 811110,during Cold shutdown,4 Channel a Main Steam Line High Flow Switches Found Inoperable.Caused by Heating of Switching Element Due to Relay Coil Failure, Initially Reported in LER 81-021.Elements Replaced ML20027C2371981-08-24024 August 1981 LER 81-020/03L-0:on 810724,main Steam Leak Revealed in Drain Line to Condenser.Caused by Piping Leaking Immediately Downstream of 45 Degree Elbow Due to Erosion & Impingement Resulting from Steam & Water Flow from Restricting Orifice ML20009E4141981-07-20020 July 1981 LER 81-018/03L-0:on 810620,reactor Water Cleanup Sys Was Returned to Svc Following Maint W/Discharge Isolation Valve MO2399 Open & Inoperable.Caused by Torque Switch Failure. Motor & Torque Switch Replaced & Sys Returned to Svc ML20009D5671981-07-16016 July 1981 LER 81-017/03L-0:on 810617,cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup Heat Exchanger Piping,At Connection to Heat Exchanger.Caused by Poor fit-up & Welding Due to 3-inch Slag Line Near Root of Weld ML19332B3791980-09-22022 September 1980 LER 80-027/03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable ML1129007601980-07-0101 July 1980 LER 80-023/03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut ML1129007541980-06-26026 June 1980 LER 80-022/03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning ML1129007511980-06-12012 June 1980 LER 80-021/03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced ML1129007481980-06-0202 June 1980 Updated 79-015/03L-1:on 790712,during Routine Insp,Steam Leak from 13A Intermediate Pressure Feedwater Heater Was Detected.Insulation Removal Revealed through-wall Flaw in Heater Shell.Caused by erosion-corrosion ML1129007451980-05-27027 May 1980 LER 80-020/03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake ML1129007221980-05-0909 May 1980 LER 80-018/03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure ML1129007071980-04-11011 April 1980 LER 80-017/01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified ML1129006851980-04-10010 April 1980 LER 80-016/01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements ML1129006801980-03-27027 March 1980 LER 80-015/01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls ML1129006781980-03-26026 March 1980 LER 80-006/03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr ML1129006651980-03-21021 March 1980 LER 80-013/01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling ML1129006681980-03-20020 March 1980 LER 80-011/01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls ML1129006621980-03-14014 March 1980 LER 80-007/01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors ML1129009771980-01-18018 January 1980 LER 79-024/03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld ML1129009741980-01-14014 January 1980 Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review ML1129009551979-12-19019 December 1979 LER 79-021/03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts ML1129009031979-08-31031 August 1979 LER 79-017/03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage ML1129008891979-08-10010 August 1979 LER 79-015/03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell ML1129008831979-08-0707 August 1979 LER 79-013/03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced ML1129008801979-08-0606 August 1979 LER 79-014/03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired ML1129008771979-08-0101 August 1979 LER 79-012/03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced ML1129008561979-06-28028 June 1979 LER 79-011/03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line ML1127801511979-03-15015 March 1979 LER 79-003/01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled ML1127601481979-02-0909 February 1979 LER 79-002/03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error ML1127601201979-02-0202 February 1979 LER 79-001/03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 ML1127601181979-01-29029 January 1979 LER 78-016/03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device ML1127601131978-12-29029 December 1978 LER 78-030/01T-0 on 781218:during surveillance,MO-2-64A Recirculation Loop 11 Discharge Bypass Valve Would Not Close.Cause Is Unknown Due to Inaccessibility of Valve ML1127601431978-12-19019 December 1978 LER#78-028/03L-0 on 781124:during Normal Oper,Small Steam Leak Was Discovered in Weld of 45 Degree Elbow on HPCI Steam Supply Line 1 Inch Drain Line to Main Condenser Due to Corrrosion.Weld Repair Made at Leak.Awaiting Parts 1994-07-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30
[Table view] |
Text
Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 554011927 Telephone (612) 330-5500 I
April 22, 1994 Report Required by 10 CFR Part 50, Section 50.73 (a)(2)(1)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Missed Surveillance due to Procedural Error The Licensee Event Report for this occurrence is attached. This report contains the following new NRC commitments:
- 1. The plant administrative directive that provides guidance on review of procedures will be revised to add guidance on review of prerequisites.
- 2. Training on the procedure review and temporary change processes will be provided to the engineering staff at a future Engineering Technical Staff Training session.
Please contact Terry Coss, Sr Licensing Engineer, at (612) 295-1449 if you require further information.
1cC?
.Ro er O Anderson Director Licensing and Management Issues c: Regional Administrator - III NRC Sr Resident Inspector, NRC ;
NRR Project Manager, NRC '
State of Minnesota, Attn: Kris Sanda Attachment q
n es ., 4 yn .
C.Du1xJ 9404260358 940422 qL I I
PDR ADOCK 05000263 [/,gG S PDR V E;b
WC FOHM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMH NO. 3150-0104 SM EXPIRES $/31/95
( STIMA TED DDHOE N PE R nf. 5PONSE 10 COM11Y Writi THIS
!N6 0nMAfiON COLLI CTION HCQtTS1 *a0 0 H 70HWAHO LICENSEE EVENT REPORT (LER) ceMw Nrs nr uAnnm oune nmMm m ,OR ,< imonucoN AND nt COHOS MANAGt MtNT EARANCH tMN00 77141,U S Nucl.t AR Hf Gut Atony COMMISSION, W ASH'NGTON, DC 2CM5 0001 AND TO ilE PAPHlWONA HtDUCTION HUJECT (330 0104L Ol FICE Or (St'0 fttverse f0f fequired number Of rhgitS/ Characters for each block) MANA01 Ut NT AND UUDGL1, WAWNGTON OC M03 f ACH.iTV NAMF p)
DOCKE I NUMitLH (?) PAGE (1)
MONTICELLO NUCI. EAR GENERATlNC PLANT 05000 - 263 1OF4 11tLE (4)
Missed Surveillance Due to Procedural Error EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) scoutNnA: ntvsos ' Avon nam mi suMulH MON TH DAY YEA 4 % AR MONT H DAY Y( AR mq gug p 05000 6 AULilY NAML DOCATT NUMfit 4
~~
03 23 94 94 "94-001 00 04 22 94 05000 OPERATING THIS REPORT IS SUDMirTED PURSUANT TO 1HE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11)
MODE (9) N 20 402(b) 20.405(c) 50 73(a)(2)(ivl 7311(b)
POWER 20 40$(a)(1)(1) 50 36(c)(1) 5013(a)(2)(v) 73 71(c)
L EVEL (10) 100 20 405(a)(1)(ii) 50 36lc)(2) 5013(a)(2)(vil) 01HER 20 405(a)(1)(ui) XX 50 73(a)(2)(i) 50.73(a)(2)(vin)(A) M* W ' nab 8b"I t,.a and in 1,4 taic 20 405(a)(1)(iv) 50 73(a)(2)(u) 50.73(a)(2)(vin)(B) rum 3e6Al 20 405(a)(1)(v) 50 73(a)(2)(m) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
NAVt tt Lt PtkJNL NuMH(.H (Irviude A'e4 Gotle)
Tom Parker (612) 295-1014 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) nsuu CAusr_ coMPoNr NT MANorActunta , CAust sYsTIM coumNE NT MANuracTunEn
^[
SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MD* " D^Y "^"
vra SUBMISSION P ps. ceum m CTE D SUPMSDON DAM ) "
X DATE (15)
~dbSTRACT (Lirnit to 1400 spaces, i es approximately 15 sinhe-spaced typeWntten hnes) (16)
A missed surveillance on the SRV Low-Low set Logic was discovered while performing verification of the Reactor Pressure Relief System design basis document. The surveillance procedure contained incorrect prerequisites.
During a reactor shutdown, the surveillance procedure was not performed as the procedural prerequisites were not met. Following discovery of the error, the '
surveillance was successfully completed at power using a special procedure.
The surveillance procedure has been revised.
l
)
we ronv w, o m i
, , - .~
4-REQUIRED NUMBER OF DIGITS / CHARACTERS FOR EACH BLOCK -
BLOCK NUMBER OF -
=
TITLE NUMBER DIGITS / CHARACTERS l
1 UP TO 48 FACILITY NAME 8 TCTAL DOCKET NUMBER 3 IN ADDITION TO 05000 ,
3 VARIES PAGE NUMBER I
4 UP TO 78 TITLE r
6 TOTAL EVENT DATE 2 PER BLOCK 7 TOTAL ,
2 FOR YEAR LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 6 TOTAL 7 REPORT DATE 2 PER BLOCK UP TO 18 - FACILITY NAME O ER FACIUTIES INNED 8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 0 1 OPERATING MODE 10 3 POWER LEVEL 11 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES .
UP TO 50 FOR NAME 12 14 FOR TELEPHONE
" "^
CAUSE VARIES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VAR ES I4 CHECK BOX THAT APPLIES SW D 6 TOTAL 15 EXPECTED SUBM!SSION DATE 2 PER BLOCK 4
l NRQ FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 is 92)
EXPlRES 5/31/95 ESTtMATED BURDEN PER RESPONSE TO COMPLY WrTH THis INFORMATION COLLECToN REQU 50 0 HRS. F ORW ARD LICENSEE EVENT REPORT (LER) CouutNTs REoiRoNo BunoEN EES,T: 7uATE TO TsE NroRuAroN TEXT CONTINUATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714L U S. NUCLEAR REovuTonY couu1SSoN. wASwwaTON, oC rossswot ANo to THE PAPERWORK REDUCTON PRCUECT (31540104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503 F ACluTY NAME (1) DOC 9tET NUMBER (2) Lf R NUMBER (s) PAGE (3) gg SEQUENitAL REVI3oN NUMBE R NUMBER 05000 - 263 OF Monticello Nuclear Generating Plant 94 - 001 -
00 2 4 Text wmw. w.c vow a sae naaww coes or mc rwm xn o r)
Description:
On March 23, 1994, with the plant operating at 100% power, a missed surveillance on the SRV Low-Low Set Logic was discovered. While performing verification of the Reactor Pressure Relief System design basis document, it was discovered that the Reactor Scram sensing portion of the Safety / Relief Valve Low-Low set Logic surveillance was not done as required during a shutdown on July 31 and August 1, 1993.
The Technical Specifications for the Reactor Scram sensing require a test frequency of "Once/ Shutdown (Note 8)" where Note 8 states "Once/ shutdown if not tested during previous 3 month period."
During the subsequent startup on August 1, 1993, this surveillance was not' performed as the prerequisites for the surveillance procedure were not met.
The prerequisites were incorrect and the test should have been performed.
This was discovered on March 23, 1994. Special procedures were approved to perform this test at power. These special procedures were successfully performed on March 23 and 24, 1994.
Cause:
The cause of the missed surveillance was an incorrect surveillance procedure prerequisite. The Technical Specification requirement for this surveillance procedure was issued on November 16, 1984. The test was first performed on January 4, 1985. In December, 1987, the prerequisite was incorrectly revised to state that (the underlined part was added):
Plant in shutdown or refuel mode,_ reactor pressure < 110 osio and temperature < 345 Jde._greesi F.
This is not a valid prerequisite for this surveillance. The prerequisite was-included in this surveillance procedure with the addition of other Low-Low Set surveillances to this procedure. This was a cognitive error during the procedure revision.
During the August 1993 shutdown, the plant did not go below 110 peig and 345 degrees F and the surveillance was not done because the prerequisites were not met.
NRC FORht 26A (5 92)
NH9 FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 H21 EXPIRES 5/31/95 EST1 MATED BURDEN PER RESPONSE TO COMPLY WrTH TH'S INC OAV ATION cod.ECT10N REQUEST: 50 0 HRS. FORW ARD LICENSEE EVENT REPORT (LER) comas AtGAnDe BUnDEN EsTiuATE 10 T E ,NFORMATiON TEXT CONTINUATION AND RECORDS MANAGEMENT BRANCH (MN99 7714h U S, NUCLEAA REGUMTORY COMM:SS ON W ASMNGTON, DC 2m6&O, AND TO THE FAPERWORK REDUCTtON PROJECT (3150 0104), OFFICE OF MANAGEMENT AND BUDOET, WASHINGTON, DC 20S03 F ACILliY NAME (1) DOCKET NUMBER (21 LEM NUMBER (t) PAGE p)
SEQUENT;A;. REv$0N yg NUMBER NUMBER 05000 - 263 OF Monticello Nuclear Generating Plant 94 - 001 -
00 3 4 rw m n. n.c. ., ,,w.a a .xw. co., a wc m xs o n During the review of all shutdowns since December, 1987, which was initiated following the discovery of this missed surveillance, it was determined that the surveillance procedure had been temporarily changed to eliminate the incorrect prerequisites on two separate occasions by operations personnel.
The first of these temporary changes tassociated with a December 16, 1988 shutdown) was incorrectly interpreted during review and identified as a non-permanent change. No subsequent action was taken to incorporate the change permanently into the procedure. Administrative controls on temporary changes have been revised since then. The permanency decision for temporary changes is now better scrutinized. It is unlikely that a similar repeat error will occur.
The second temporary change (associated with an April 20, 1992 shutdown) was identified as a permanent change to the procedure and slated for immediate incorporation into the existing procedure. However, this procedure was in the revision process at that time. The revision consisted of separating the surveillance that is the subject of this report from other surveillances on Safety / Relief Valve Low-Low Set and making it a separate surveillance procedure. The person making the revision was notified to incorporate the temporary change. A document change notice was also placed in the existing procedure's file, giving notice to potential users of the temporary change.
This notice stated that it was only applicable to the current revision since the surveillance requirement to which the temporary change applied was being removed in the new revision. The temporary change was not incorporated into the newly created procedure due to cognitive personnel error.
Analysis:
The failure to do a surveillance is a violation of the Monticello Technical Specifications and is being reported under 10 CFR Part 50, 50.73(a)(2)(1)(B).
The function of the Low-Low Set System is to minimize the possibility of a safety / relief valve reopening while an elevated water leg is in its discharge line. The logic invokes lower setpoints for three of the Safety / Relief valves following a scram. In Low-Low Set, the system pressure blowdown range is larger (80 psi) and a time delay prevents the valve from reopening for 10 seconds. Following valve closure, the steam in the discharge line condenses and draws torus water up into the discharge line. A vacuum breaker opens to allow the water to drain to torus water level. If the Safety / Relief valve were to reopen with an elevated water leg in the discharge line, damage could 1 be done to the Safety / Relief valve discharge line or torus. The 10 second delay time is sufficient time for the discharge line to drain to torus water level. Each of the three Safety / Relief valves can be opened by either of two independent trains of logic.
NnC FORu mA (s.ea
NRC PORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31504104 3 sh EXPlRES $/31/95 ESTWIATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFOAMATON COLLECTION RE QUE ST; 50 0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMVDCS REGARDWG BURDEN ESTIMATE TO THE INFORMATION 1 TE COMWUA rmN ' AND nEeORDS MANroEutur sRANcH iuNeu rri4i. u s NUCLEAR REGULATORY COMV $ SON. WASH!NG'ON DC 20Sh$-0001, ANO TO THE PAPERWOR4 REDLCTION PRCULO.T (3150 0104), OFFICE OF MANAOEMENT AND BUDGET, W ASHING 10N. DC 70$03 f ACILITY NAME (O DOCRET NUMBE R p) LER NUMBLR (4) PAQt p)
YEAR NUMBER NUMBfR 05000 - 263 OF MOnticello Nuclear Generating Plant 94 001 00 4 4 Tus p n, an.co v.w.a a. euw. cap.., or wc nm, xs o n Prior to discovery of this event, the Reactor Scram sensing portion of the SRV Low-Low Set Logic was last tested on March 16, 1993. Upon discovery of the missed surveillance, it was promptly performed on March 23 and 24, 1994. The logic was tested satisfactorily.
The scram sensing portion of the SRV Low-Low Set Logic is very reliable and has never failed this surveillance test. Had a failure of a relay occurred between August 1993 and March of 1994, no inoperability would have occurred as one relay failure would affect only one division of the Low-Low Set Logic.and the system would still have performed as designed.
Corrective Action:
- 1. The Reactor Scram sensing surveillance of the SRV Low-Low Set Logic was successfully completed on March 23 and 24, 1994.
- 2. The Reactor Scram sensing surveillance procedure was revised to remove the incorrect prerequisite.
- 3. The plant administrative directive that provides guidance on review of procedures will be revised to add guidance on review of prerequisites.
- 4. Training on the procedure review and temporary change processes I will be provided to the engineering staff at a future Engineering Technical Staff Training session.
S. A review of other Technical Specification required surveillance !
tests was conducted. All surveillance procedures not routinely scheduled were reviewed for the last ten years. No other problems were identified in this review.
Additional Informatical Failed Component Identification NONE Previous Similar Event: NONE NRC FOMM 366A (S-97)
- _ _,