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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E2061994-05-11011 May 1994 LER 93-025-01:on 931205,Loop a MSIVs Exceeded TS Leakage Limit.Caused by Failure of Fastner Locking Devices.Seating Surface of Main Disc in MSIV 1A Machined & Successfully Pass LLRT on 940116.W/940511 Ltr ML17352B2501993-10-0101 October 1993 LER 93-014-00:on 930902,discovered That IRM 11 & APRM Both in Bypassed Condition W/O Half Scram Being Inserted Due to Work Practices.Irm 11 Taken Out of Bypassed Condition & Individual Involved counselled.W/931001 Ltr ML17352B2511993-10-0101 October 1993 LER 93-019-00:on 930903,RHR Pump 1A Inadvertently Started Due to Personnel Error.Pump Immediately Secured & Individual Involved Counselled on Importance of self-check.W/931001 Ltr ML20046A1801993-07-21021 July 1993 LER 92-007-00:on 930624,Toxic Gas Analyzer Inoperable Due to Personnel Error Caused by Lack of Procedural Adherence. Isolated CR Ventilation,Restarted Sample Pump & Restored CR Ventilation Sys to Outside Air suction.W/930721 Ltr ML20045H5781993-07-13013 July 1993 LER 93-013-00:on 930613,internal Electrical Fault within Main Power Transformer Tripped & Caused Reactor Scram & Unexpected Group I Isolation.Caused by Turbine Stop Valve Closure.Transformer replaced.W/930713 Ltr ML20045G7291993-07-0909 July 1993 LER 93-005-00:on 930609,numerous Alarms Received in CR, Including HPCI Turbine Rupture Disc High Pressure Alarm. Caused by Ruptured Disk,Releasing Steam/Water Mixture. Test Will Be Conducted on Rupture disks.W/930709 Ltr ML20045G0951993-07-0202 July 1993 LER 93-011-00:on 930602,HPCI Declared Inoperable in Order to Perform Qcos 2300-13.Caused by MSC Stem & Stem Gear Being Scored & Worn from Age Causing Excessive Friction.C/As Include Disassembling Gearbox Every 10 yrs.W/930702 Ltr ML20045F3321993-06-30030 June 1993 LER 93-012-00:on 930601,U-2 DG Cooling Water Pump Inoperable Due to Inadequate lubrication.U-2 DG Cooling Water Pump replaced.W/930630 Ltr ML20045F3251993-06-28028 June 1993 LER 93-007-01:on 930307,B Loop MSIV Exceeded TS Leakage Limits for Containment Isolation Valves Caused by Damaged Flexitalic Bonnet Gasket.Replaced Bonnet Gasket & Valve Successfully Retested (WR Q061987).W/930622 Ltr ML20044E6171993-05-14014 May 1993 LER 93-006-00:on 930420,Unit 2 Nso Inadvertently Started Unit 1 DG When Attempting to Start Shared (1/2) Dg.Caused by Personnel Error.Unit 1 DG Shut Down & 1/2 DG Started & Loaded successfully.W/930514 Ltr ML20044C9511993-05-0707 May 1993 LER 93-009-00:on 930408,technician Discovered That Estimate of Sample Flow for U2 Reactor Bldg Vent Sampler Flow Rate Monitor Not Calculated.Caused by Personnel Error.Technician counseled.W/930428 Ltr ML20024G6811991-04-19019 April 1991 LER 91-008-00:on 910322,reactor Bldg Ventilation Isolation Occurred.Caused by Lightning Strike.Control Room Vents Reset & Toxic Gas Sample Point a Selected.Addl Trips Associated W/ Lightning Strike Immediately reset.W/910418 Ltr ML20029C1241991-03-0808 March 1991 LER 91-005-01:on 910131,1/2 B Standby Gas Treatment Sys Autostart During RPS B Power Swap Due to an Inadequate Procedure.Nso Reset 1/2 Scram & 1/2 Groups II & III isolations.W/910306 Ltr ML20029B5901991-03-0808 March 1991 LER 91-004-00:on 910211,standby Liquid Control Sys of Unit 1 & 2 Inoperable.Caused by Inadequate Mod Testing.Engineering Dept Evaluating Data & Temporary Procedure 6589 Generated. W/910308 Ltr ML20028H7841991-01-23023 January 1991 LER 90-032-00:on 901224,1/2A Diesel Fire Pump Taken out-of- Svc on 901217 & Not Returned to Svc Before Seven Day Time Allotment Expired.Caused by Mgt Deficiency.Fire Pump Successfully Tested & Returned to svc.W/910123 Ltr ML20028H6831991-01-21021 January 1991 LER 90-034-00:on 901223,high Chlorine Concentration Caused Control Room Ventilation Manual Isolation & ESF Actuation. Caused by Instrument Error Code & Misinterpretation of Analyzer Indication.Flow reduced.W/910121 Ltr ML20028G9141990-09-28028 September 1990 LER 90-018-00:on 900829,plant Outside Design Spec for Electrical Separation Criteria for Two Redundant Safety Sys. Caused by Inadequate Engineering Review During Leads installation.W/900928 Ltr ML20044B2401990-07-12012 July 1990 LER 90-012-00:on 900612,control Room Ventilation Emergency Air Filtration Unit Declared Inoperable.Caused by Heater Malfunction.Work Request initiated.W/900712 Ltr ML20044B0091990-07-11011 July 1990 LER 90-011-00:on 900611,diesel Fire Pump 1/2 a Out of Svc for Period Exceeding 7 Days Reporting Criteria,To Install New Suction Line.Caused by Required Maint Work.Repairs Completed & Pump Tested & Returned to svc.W/900711 Ltr ML20043H4831990-06-21021 June 1990 LER 90-010-00:on 900522,while Returning RWCU Sys to Svc, Nonregenerative HX High Temp Alarm Received,Challenging ESF Logic & Causing Group III Isolation.Caused by Leaking RWCU Check Valves.Work Requests issued.W/900621 Ltr ML20043H2931990-06-18018 June 1990 LER 90-009-00:on 900518,determined That Various Containment Vols Not Leak Rate Tested Due to Recent 10CFR50,App J Interpretation Re Licensing Design Criteria.Mod M4-1(2)-89-167 initiated.W/900618 Ltr ML20043H9521990-06-13013 June 1990 LER 90-016-01:on 900411,motor Control Ctr Relay 28/29-5 Setpoint Drift Occurred,Resulting in Analyzed Plant Condition.Caused by Utilizing Wrong Relay & Inadequate Review of GE Svc Info Ltr.Relay replaced.W/900613 Ltr ML20043E9121990-06-0707 June 1990 LER 90-006-00:on 900508,Unit 2 RCIC Declared Inoperable Due to Unstable Operation of RCIC Pump Flow Controller.Caused by Proportional Band of Controller Being Set to Respond to Changes in Flow Too Quickly.Flow controlled.W/900607 Ltr ML20043F2341990-06-0101 June 1990 LER 90-001-01:on 891208,seven Pathways Not Included in Type B & C Local Leak Rate Test Program.Caused by Misinterpretation of 10CFR50,App J Requirements.Required Vents & Test Taps Will Be installed.W/900601 Ltr ML20043F2161990-06-0101 June 1990 LER 89-024-01:on 891214,main Turbine Unexpectedly Tripped Following Isolation of Reactor Water Level Switch (Lits). Caused by Channel B Lits Having Been Previously Replaced W/ Switch That Operated Reverse function.W/900601 Ltr ML20042E4991990-04-17017 April 1990 LER 90-007-00:on 900318,ESF Actuation Occurred.Caused by Mgt Deficiency in Not Providing Sufficient Guidance for Review of Work Package After Scope Changed.New Work Package Preparation Procedures initiated.W/900417 Ltr ML20012C7231990-03-15015 March 1990 LER 90-004-00:on 900213,loss of Emergency Bus 23-1 Occurred Due to Shorted Conductor Cable While Performing Wiring Verification.Caused by Personnel Error & Improper Installation.Electric Power Supplies recovered.W/900315 Ltr ML20012C7171990-03-15015 March 1990 LER 90-003-00:on 900213,unit Diesel Generator Tripped on Overspeed Upon Manual Startup for Testing.Caused by Misadjustment of Diesel Generator Governor.Diesel Generator Equipment Reset & Governor adjusted.W/900315 Ltr ML20012B2931990-03-0505 March 1990 LER 90-002-00:on 900204,determined That Only Reactor Bldg Differential Pressure of 0.24-inch Water Vacuum Could Be Obtained,In Violation of Tech Spec Required 0.25 Inch.Caused by Testing Deficiency.Leak Paths sealed.W/900305 Ltr ML20012B2961990-03-0505 March 1990 LER 90-003-00:on 900205,determined That Leakage Rate for HPCI Sys Steam Exhaust Check Valve Exceeded Tech Spec Limits.Caused by Excessive Leakage.Check Valve Replaced W/ Mission Check Valve W/Carbon Steel springs.W/900305 Ltr ML20011E1821990-01-30030 January 1990 LER 90-002-00:on 900102,during Annual Water Sprinkler Sys Valve Position Insp,Discovered That Valve 2-4199-072 Not Cycled Per Tech Spec Surveillance Requirement 4.12.Caused by Procedural Deficiency.Procedure to Be revised.W/900130 Ltr ML19354D9431990-01-15015 January 1990 LER 89-025-00:on 891220,determined That Reactor Bldg Overhead Auxiliary Hook May Have Contacted Side of New Fuel Bundle on 891214,causing Extensive Damage.Caused by Personnel Error.Bundle Shipped Back to GE.W/900115 Ltr ML19354D9481990-01-15015 January 1990 LER 89-023-00:on 891219,identified Deficient Temporary Procedures Which Altered Intent of Original Procedure QAP 1100-7.Caused by Mgt Oversight in Preparation of Tech Spec Change.Temporary Procedures revised.W/900115 Ltr ML20005F5881990-01-0808 January 1990 LER 90-001-00:on 891208,seven Pathways Not Included in Type B & C Local Leak Rate Testing Program.Caused by Misinterpretation of 10CFR50,App J Testing Requirements.Mod of Sys to Be Performed as necessary.W/900108 Ltr ML20005G0231990-01-0202 January 1990 LER 88-020-01:on 880619,improper Valving Sequence Occurred Which Resulted in Various ESF Actuations.Caused by Inadequate Equipment out-of-svc Procedure.Procedure Revised & Training Lesson Plan developed.W/900102 Ltr ML20005E4531989-12-28028 December 1989 LER 89-022-00:on 891128,HPCI Declared Inoperable Following Unexpected Actuation of HPCI Pump Room Deluge Sys.Actuation Caused Dc Sys Grounds Due to Moisture Intrusion in Electrical Equipment.Equipment dried.W/891228 Ltr ML20005D9551989-12-22022 December 1989 LER 89-021-00:on 891124,HPCI Deluge Sys Functional Test Not Completed within Tech Spec Interval of 6 Months.Caused by Mgt Deficiency & Insufficient Procedure.Procedures Revised to Better Control Tech Specs.W/891222 Ltr ML19351A6391989-12-15015 December 1989 LER 89-020-00:on 891117,full Reactor Scram Occurred Due to Simultaneous Loss of Power to 1A & 1B 24/48-volt Distribution Panels During Panel Transfer.Caused by Personnel Error.Personnel Trained Re event.W/891215 Ltr ML19332E7581989-12-0505 December 1989 LER 89-019-00:on 891105,half Group II & III Isolation Occurred While Performing Valve Flow Check Surveillance. Caused by Leaky Isolation Valve on Transmitter.Surveillance Methods Will Be Reviewed & Procedures revised.W/891205 Ltr ML19332C7581989-11-20020 November 1989 LER 89-017-00:on 891022,discovered That 6-month Functional Test Procedure Qos 500-3 Re Functional Test for Reactor Protection Sys Electrical Assemblies Not Completed in Required Time.Caused by Mgt deficiency.W/891120 Ltr ML19327C0701989-11-0909 November 1989 LER 89-018-00:on 891012,notification Given of Potential Single Failure of Diesel Generator Voltage Regulator That Could Result in Loss of All But One ECCS Loop.Caused by Design Deficiency.New Procedure developed.W/891109 Ltr ML19327C0951989-11-0404 November 1989 LER 89-005-00:on 891012,reactor Scram Occurred Due to Turbine Stop Valve Closure.Caused by Personnel Error in That Work Analyst Overlooked Removal of Two Connections on Limit Switch.Maint Workers Immediately counseled.W/891104 Ltr ML19327C2631989-11-0101 November 1989 LER 87-009-01:on 870801,reactor Scram Occurred from Turbine Generator Load Mismatch Due to Generator Trip.Caused by Electrical Fault in Main Transformer C Phase Windings.Main Transformer Replaced w/spare.W/891103 Ltr ML19325E8261989-10-30030 October 1989 LER 87-012-01:on 870918,while Performing Qos 1600-1, Vacuum Breaker 2-1601-33E Remained Open After Testing.Caused by Binding in Test Cylinder Portion of Vacuum Breaker. Nuclear Work Requests completed.W/891030 Ltr ML19325E5921989-10-24024 October 1989 LER 87-017-01:on 870805,Group IV Isolation Received Which Resulted in Closure of HPCI Steam Supply Valves.Caused by Failed HPCI Steamline Differential Pressure Transmitter Due to Loss of Oil in Sensing cell.W/891024 Ltr ML19325E5971989-10-24024 October 1989 LER 88-003-01:on 880301,while Performing RCIC Monthly Test, RCIC Pump Could Only Achieve 400 Gpm Against Discharge Pressure of 500 Psig.Caused by Failed Hydraulic Actuator on Turbine Governor Valve.Actuator replaced.W/891024 Ltr ML19327B7901989-10-18018 October 1989 LER 89-016-00:on 890921,during Transfer of New Fuel,Fuel Assembly Released from Refueling Grapple & Fell Upon Spent Fuel Racks.Caused by Personnel Error & Procedural Deficiency.Fuel Handling Procedures Revised ML19327B0491989-10-16016 October 1989 LER 89-015-00:on 890916,during Transfer,Loss of Power to Off Gas Monitor a Caused Contacts to Open Giving Upscale Radiation Signal,Thus Starting Off Gas Timer.Caused by Inadequate Procedures.Off Gas Sys reset.W/891016 Ltr ML19325C5341989-10-0202 October 1989 LER 89-014-00:on 890910,determined That Combined Leakage Rate from All Penetrations & Valves Exceeded Tech Spec Limit.Root Cause Unknown.No Corrective Action Taken. Supplemental Rept Will Be issued.W/891002 Ltr ML18052B5541987-08-24024 August 1987 LER 87-015-00:on 870731,capacitor Failed on 1B Reactor Bldg & Refuel Floor Radiation Monitors Resulting in Safety Feature Actuation.Caused by Normal Aging.Capacitor replaced.W/870825 Ltr 1994-05-11
[Table view] Category:RO)
MONTHYEARML20029E2061994-05-11011 May 1994 LER 93-025-01:on 931205,Loop a MSIVs Exceeded TS Leakage Limit.Caused by Failure of Fastner Locking Devices.Seating Surface of Main Disc in MSIV 1A Machined & Successfully Pass LLRT on 940116.W/940511 Ltr ML17352B2501993-10-0101 October 1993 LER 93-014-00:on 930902,discovered That IRM 11 & APRM Both in Bypassed Condition W/O Half Scram Being Inserted Due to Work Practices.Irm 11 Taken Out of Bypassed Condition & Individual Involved counselled.W/931001 Ltr ML17352B2511993-10-0101 October 1993 LER 93-019-00:on 930903,RHR Pump 1A Inadvertently Started Due to Personnel Error.Pump Immediately Secured & Individual Involved Counselled on Importance of self-check.W/931001 Ltr ML20046A1801993-07-21021 July 1993 LER 92-007-00:on 930624,Toxic Gas Analyzer Inoperable Due to Personnel Error Caused by Lack of Procedural Adherence. Isolated CR Ventilation,Restarted Sample Pump & Restored CR Ventilation Sys to Outside Air suction.W/930721 Ltr ML20045H5781993-07-13013 July 1993 LER 93-013-00:on 930613,internal Electrical Fault within Main Power Transformer Tripped & Caused Reactor Scram & Unexpected Group I Isolation.Caused by Turbine Stop Valve Closure.Transformer replaced.W/930713 Ltr ML20045G7291993-07-0909 July 1993 LER 93-005-00:on 930609,numerous Alarms Received in CR, Including HPCI Turbine Rupture Disc High Pressure Alarm. Caused by Ruptured Disk,Releasing Steam/Water Mixture. Test Will Be Conducted on Rupture disks.W/930709 Ltr ML20045G0951993-07-0202 July 1993 LER 93-011-00:on 930602,HPCI Declared Inoperable in Order to Perform Qcos 2300-13.Caused by MSC Stem & Stem Gear Being Scored & Worn from Age Causing Excessive Friction.C/As Include Disassembling Gearbox Every 10 yrs.W/930702 Ltr ML20045F3321993-06-30030 June 1993 LER 93-012-00:on 930601,U-2 DG Cooling Water Pump Inoperable Due to Inadequate lubrication.U-2 DG Cooling Water Pump replaced.W/930630 Ltr ML20045F3251993-06-28028 June 1993 LER 93-007-01:on 930307,B Loop MSIV Exceeded TS Leakage Limits for Containment Isolation Valves Caused by Damaged Flexitalic Bonnet Gasket.Replaced Bonnet Gasket & Valve Successfully Retested (WR Q061987).W/930622 Ltr ML20044E6171993-05-14014 May 1993 LER 93-006-00:on 930420,Unit 2 Nso Inadvertently Started Unit 1 DG When Attempting to Start Shared (1/2) Dg.Caused by Personnel Error.Unit 1 DG Shut Down & 1/2 DG Started & Loaded successfully.W/930514 Ltr ML20044C9511993-05-0707 May 1993 LER 93-009-00:on 930408,technician Discovered That Estimate of Sample Flow for U2 Reactor Bldg Vent Sampler Flow Rate Monitor Not Calculated.Caused by Personnel Error.Technician counseled.W/930428 Ltr ML20024G6811991-04-19019 April 1991 LER 91-008-00:on 910322,reactor Bldg Ventilation Isolation Occurred.Caused by Lightning Strike.Control Room Vents Reset & Toxic Gas Sample Point a Selected.Addl Trips Associated W/ Lightning Strike Immediately reset.W/910418 Ltr ML20029C1241991-03-0808 March 1991 LER 91-005-01:on 910131,1/2 B Standby Gas Treatment Sys Autostart During RPS B Power Swap Due to an Inadequate Procedure.Nso Reset 1/2 Scram & 1/2 Groups II & III isolations.W/910306 Ltr ML20029B5901991-03-0808 March 1991 LER 91-004-00:on 910211,standby Liquid Control Sys of Unit 1 & 2 Inoperable.Caused by Inadequate Mod Testing.Engineering Dept Evaluating Data & Temporary Procedure 6589 Generated. W/910308 Ltr ML20028H7841991-01-23023 January 1991 LER 90-032-00:on 901224,1/2A Diesel Fire Pump Taken out-of- Svc on 901217 & Not Returned to Svc Before Seven Day Time Allotment Expired.Caused by Mgt Deficiency.Fire Pump Successfully Tested & Returned to svc.W/910123 Ltr ML20028H6831991-01-21021 January 1991 LER 90-034-00:on 901223,high Chlorine Concentration Caused Control Room Ventilation Manual Isolation & ESF Actuation. Caused by Instrument Error Code & Misinterpretation of Analyzer Indication.Flow reduced.W/910121 Ltr ML20028G9141990-09-28028 September 1990 LER 90-018-00:on 900829,plant Outside Design Spec for Electrical Separation Criteria for Two Redundant Safety Sys. Caused by Inadequate Engineering Review During Leads installation.W/900928 Ltr ML20044B2401990-07-12012 July 1990 LER 90-012-00:on 900612,control Room Ventilation Emergency Air Filtration Unit Declared Inoperable.Caused by Heater Malfunction.Work Request initiated.W/900712 Ltr ML20044B0091990-07-11011 July 1990 LER 90-011-00:on 900611,diesel Fire Pump 1/2 a Out of Svc for Period Exceeding 7 Days Reporting Criteria,To Install New Suction Line.Caused by Required Maint Work.Repairs Completed & Pump Tested & Returned to svc.W/900711 Ltr ML20043H4831990-06-21021 June 1990 LER 90-010-00:on 900522,while Returning RWCU Sys to Svc, Nonregenerative HX High Temp Alarm Received,Challenging ESF Logic & Causing Group III Isolation.Caused by Leaking RWCU Check Valves.Work Requests issued.W/900621 Ltr ML20043H2931990-06-18018 June 1990 LER 90-009-00:on 900518,determined That Various Containment Vols Not Leak Rate Tested Due to Recent 10CFR50,App J Interpretation Re Licensing Design Criteria.Mod M4-1(2)-89-167 initiated.W/900618 Ltr ML20043H9521990-06-13013 June 1990 LER 90-016-01:on 900411,motor Control Ctr Relay 28/29-5 Setpoint Drift Occurred,Resulting in Analyzed Plant Condition.Caused by Utilizing Wrong Relay & Inadequate Review of GE Svc Info Ltr.Relay replaced.W/900613 Ltr ML20043E9121990-06-0707 June 1990 LER 90-006-00:on 900508,Unit 2 RCIC Declared Inoperable Due to Unstable Operation of RCIC Pump Flow Controller.Caused by Proportional Band of Controller Being Set to Respond to Changes in Flow Too Quickly.Flow controlled.W/900607 Ltr ML20043F2341990-06-0101 June 1990 LER 90-001-01:on 891208,seven Pathways Not Included in Type B & C Local Leak Rate Test Program.Caused by Misinterpretation of 10CFR50,App J Requirements.Required Vents & Test Taps Will Be installed.W/900601 Ltr ML20043F2161990-06-0101 June 1990 LER 89-024-01:on 891214,main Turbine Unexpectedly Tripped Following Isolation of Reactor Water Level Switch (Lits). Caused by Channel B Lits Having Been Previously Replaced W/ Switch That Operated Reverse function.W/900601 Ltr ML20042E4991990-04-17017 April 1990 LER 90-007-00:on 900318,ESF Actuation Occurred.Caused by Mgt Deficiency in Not Providing Sufficient Guidance for Review of Work Package After Scope Changed.New Work Package Preparation Procedures initiated.W/900417 Ltr ML20012C7231990-03-15015 March 1990 LER 90-004-00:on 900213,loss of Emergency Bus 23-1 Occurred Due to Shorted Conductor Cable While Performing Wiring Verification.Caused by Personnel Error & Improper Installation.Electric Power Supplies recovered.W/900315 Ltr ML20012C7171990-03-15015 March 1990 LER 90-003-00:on 900213,unit Diesel Generator Tripped on Overspeed Upon Manual Startup for Testing.Caused by Misadjustment of Diesel Generator Governor.Diesel Generator Equipment Reset & Governor adjusted.W/900315 Ltr ML20012B2931990-03-0505 March 1990 LER 90-002-00:on 900204,determined That Only Reactor Bldg Differential Pressure of 0.24-inch Water Vacuum Could Be Obtained,In Violation of Tech Spec Required 0.25 Inch.Caused by Testing Deficiency.Leak Paths sealed.W/900305 Ltr ML20012B2961990-03-0505 March 1990 LER 90-003-00:on 900205,determined That Leakage Rate for HPCI Sys Steam Exhaust Check Valve Exceeded Tech Spec Limits.Caused by Excessive Leakage.Check Valve Replaced W/ Mission Check Valve W/Carbon Steel springs.W/900305 Ltr ML20011E1821990-01-30030 January 1990 LER 90-002-00:on 900102,during Annual Water Sprinkler Sys Valve Position Insp,Discovered That Valve 2-4199-072 Not Cycled Per Tech Spec Surveillance Requirement 4.12.Caused by Procedural Deficiency.Procedure to Be revised.W/900130 Ltr ML19354D9431990-01-15015 January 1990 LER 89-025-00:on 891220,determined That Reactor Bldg Overhead Auxiliary Hook May Have Contacted Side of New Fuel Bundle on 891214,causing Extensive Damage.Caused by Personnel Error.Bundle Shipped Back to GE.W/900115 Ltr ML19354D9481990-01-15015 January 1990 LER 89-023-00:on 891219,identified Deficient Temporary Procedures Which Altered Intent of Original Procedure QAP 1100-7.Caused by Mgt Oversight in Preparation of Tech Spec Change.Temporary Procedures revised.W/900115 Ltr ML20005F5881990-01-0808 January 1990 LER 90-001-00:on 891208,seven Pathways Not Included in Type B & C Local Leak Rate Testing Program.Caused by Misinterpretation of 10CFR50,App J Testing Requirements.Mod of Sys to Be Performed as necessary.W/900108 Ltr ML20005G0231990-01-0202 January 1990 LER 88-020-01:on 880619,improper Valving Sequence Occurred Which Resulted in Various ESF Actuations.Caused by Inadequate Equipment out-of-svc Procedure.Procedure Revised & Training Lesson Plan developed.W/900102 Ltr ML20005E4531989-12-28028 December 1989 LER 89-022-00:on 891128,HPCI Declared Inoperable Following Unexpected Actuation of HPCI Pump Room Deluge Sys.Actuation Caused Dc Sys Grounds Due to Moisture Intrusion in Electrical Equipment.Equipment dried.W/891228 Ltr ML20005D9551989-12-22022 December 1989 LER 89-021-00:on 891124,HPCI Deluge Sys Functional Test Not Completed within Tech Spec Interval of 6 Months.Caused by Mgt Deficiency & Insufficient Procedure.Procedures Revised to Better Control Tech Specs.W/891222 Ltr ML19351A6391989-12-15015 December 1989 LER 89-020-00:on 891117,full Reactor Scram Occurred Due to Simultaneous Loss of Power to 1A & 1B 24/48-volt Distribution Panels During Panel Transfer.Caused by Personnel Error.Personnel Trained Re event.W/891215 Ltr ML19332E7581989-12-0505 December 1989 LER 89-019-00:on 891105,half Group II & III Isolation Occurred While Performing Valve Flow Check Surveillance. Caused by Leaky Isolation Valve on Transmitter.Surveillance Methods Will Be Reviewed & Procedures revised.W/891205 Ltr ML19332C7581989-11-20020 November 1989 LER 89-017-00:on 891022,discovered That 6-month Functional Test Procedure Qos 500-3 Re Functional Test for Reactor Protection Sys Electrical Assemblies Not Completed in Required Time.Caused by Mgt deficiency.W/891120 Ltr ML19327C0701989-11-0909 November 1989 LER 89-018-00:on 891012,notification Given of Potential Single Failure of Diesel Generator Voltage Regulator That Could Result in Loss of All But One ECCS Loop.Caused by Design Deficiency.New Procedure developed.W/891109 Ltr ML19327C0951989-11-0404 November 1989 LER 89-005-00:on 891012,reactor Scram Occurred Due to Turbine Stop Valve Closure.Caused by Personnel Error in That Work Analyst Overlooked Removal of Two Connections on Limit Switch.Maint Workers Immediately counseled.W/891104 Ltr ML19327C2631989-11-0101 November 1989 LER 87-009-01:on 870801,reactor Scram Occurred from Turbine Generator Load Mismatch Due to Generator Trip.Caused by Electrical Fault in Main Transformer C Phase Windings.Main Transformer Replaced w/spare.W/891103 Ltr ML19325E8261989-10-30030 October 1989 LER 87-012-01:on 870918,while Performing Qos 1600-1, Vacuum Breaker 2-1601-33E Remained Open After Testing.Caused by Binding in Test Cylinder Portion of Vacuum Breaker. Nuclear Work Requests completed.W/891030 Ltr ML19325E5921989-10-24024 October 1989 LER 87-017-01:on 870805,Group IV Isolation Received Which Resulted in Closure of HPCI Steam Supply Valves.Caused by Failed HPCI Steamline Differential Pressure Transmitter Due to Loss of Oil in Sensing cell.W/891024 Ltr ML19325E5971989-10-24024 October 1989 LER 88-003-01:on 880301,while Performing RCIC Monthly Test, RCIC Pump Could Only Achieve 400 Gpm Against Discharge Pressure of 500 Psig.Caused by Failed Hydraulic Actuator on Turbine Governor Valve.Actuator replaced.W/891024 Ltr ML19327B7901989-10-18018 October 1989 LER 89-016-00:on 890921,during Transfer of New Fuel,Fuel Assembly Released from Refueling Grapple & Fell Upon Spent Fuel Racks.Caused by Personnel Error & Procedural Deficiency.Fuel Handling Procedures Revised ML19327B0491989-10-16016 October 1989 LER 89-015-00:on 890916,during Transfer,Loss of Power to Off Gas Monitor a Caused Contacts to Open Giving Upscale Radiation Signal,Thus Starting Off Gas Timer.Caused by Inadequate Procedures.Off Gas Sys reset.W/891016 Ltr ML19325C5341989-10-0202 October 1989 LER 89-014-00:on 890910,determined That Combined Leakage Rate from All Penetrations & Valves Exceeded Tech Spec Limit.Root Cause Unknown.No Corrective Action Taken. Supplemental Rept Will Be issued.W/891002 Ltr ML18052B5541987-08-24024 August 1987 LER 87-015-00:on 870731,capacitor Failed on 1B Reactor Bldg & Refuel Floor Radiation Monitors Resulting in Safety Feature Actuation.Caused by Normal Aging.Capacitor replaced.W/870825 Ltr 1994-05-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30
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/,,NJ: Commonwealth Edison :
) ouad Cit:cs Nuclear Power Station
.'l ' , j ,
. i, g lj 22710 206 Avenue North '
,' -% Cordova. Illinois 61242 9740
' \ Telephone 309/654 2241
'RLB-89-223 -
i i<
October 24, 1989 {
U. $.. Nuclear Regulatory Commission Document, Control Desk ,
. Washington, DC .20555 <
l
Reference:
Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER)88-003, Revision 01, for-Quad Cities Nuclear Power Station.
This report.is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(v), which requires the i reporting of any event or condition that alone could have prevented the
' fulfillment of the safety function of structures or systems that are needed to
. remove residual heat. -
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Respectfully, l.
COMMONWEALTH EDISON COMPANY QgAD CITIES UC POWER STATION .
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- l. R. L. x t
- . Station Manager L.
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- l. Enclosure E
-cc: R. Stols R. Higgins INPO Records Center NRC Region III
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2318H/0683Z 8911080074 891024 PDR->cADOCK.05000265
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[ LICENSEE EVENT REPORT (LER)
Facility,Name (1) Docket Number (2) Ploe (1) 6 Quad Eities Unit Two 01 El ol of ol 21 61 5 1 of al3 l Tit.le (4)
Elf Inanarable Due to Failed Governor Actuator
,_ Event Data fE1 LE W er (6) Reoort Date (71 Othe* Facilitiet Involved (B)
Month Day Year Year /// Sequential / Revision Month Day Year Facility Names Docket Numby ft) l j/j,/
/ h ar //j/j j/
/ Number l
of El of of of I l
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of 3 01 1 al a al a oIo13 o11 1 Io 214 al 9 ofElol01of I I I THIS REPORT !$ SUBMITTED PUR$UANT TO THE REQUIREMENTS OF 10CFR OPEUN fCheck one or more of the followinal f11) 4 20.402(b) ,, 20.405(c) ,_ 50.73(a)(2)(iv) ___ 73.71(b)
POWER 20.405(a)(1)(1) 50.36(c)(1) _X_ 50.73(a)(2)(v) _._ 73.71(c)
LIVEL ___. 20.405(a)(1)(11) __ 50.36(c)(2) _ 50.73(a)(2)(v11) _ Other (Specify (101 ol9l6 _._ 20.405(a)(1)(iii) 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) in Abstract
/////////////u/////////// _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) below and in
/////////////'/////////////
j _ 20.405(a)(1)(v) _ 50.73(a)(2)(itt) _._. 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR THIS LER f12)
Came TELEPHONE NUMBER AREA CODE K. J. Hill. Technical staff Enoineer. Fxt. 2150 1loI9 61 El al -l 21 21 41 COMPLETE ONE LINE FOR EACH COM FAILURE DESCRIBED IN THIS REPORT f131
- CAUSE SYSTEM COMPONFNT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER 70 WPRDS X aiN I il El wl 21 91 o 1 I 1 1 I I I I l l l l l l l 1 1 I I I I t SUPPLEMENTAL REPORT EXPECTED (141 Expected Mor.th l Day l Ygg Submission lyes (If ves. conclete EXPECTED SUBMISSION DATEl X l No I I l ABSTRACT (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten lines) (16)
ABSTRACT:
On March 1, 1988, Unit Two was in the RUN mode at approximately 96 percent power.
At 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, while performing QOS 300-1, " Reactor Core Isolation Cooling (RCIC)
Monthly Test," it was found that the RCIC pump [P) could only achieve 400 gpm (rated) against a discharge pressure of 500 psig with a turbine speed of 3,000 rpm. Normal pressure and speed is 1,250 psig at 4,500 rpm. RCIC was declared inoperable and NRC notification of this event was completed at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> per 10CFR50.72. Work Request Q64717 was written to investigate the problem and to make repairs. ,
It was determined that the cause of this event was due to a failed hydraulic actuator [15] on the turbine [TRB] governor [65] valve (V). The actuator was replaced on March 2, 1988, and RCIC was successfully tested at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />. The failed actuator was sent to the manufacturer who determined that the problem was an electronic failure. This report is provided per 10CFR50.73(a)(2)(v)(B).
2317H/06832
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev 2.0 FACILITY NAME-(1) DOCKET NUMBER (2) LER NUMBER f61 Pace (3) s Year seguential Revisicn g//
/ Number g//
/ Num*1t_
W Citlet Unit Two oIE!Ol0lol21615 Bl8 . Ol013 - 0i 1 012 0F 013 TEXT Energy Industry Identification SystNn (E!!S) codes are identified in the text as (Xx) ;
PLANT AND SYSTEM IDENTIFICATION: ,
General Electric - Bolling Water Reactor - 2511 MWt rated core thermal power.
EV_ENT 10ENTIFICATION: RCIC Inoperable Due to Failed Governor Actuator A.. CONDITIONS PRIOR TO EVENT:
Unit: Two Event Date: March 1, 1988 Event Time: 1100 Reactor Mode: 4 Mode Name: RUN Power Level: 96%
This report was initiated by Deviation Report 0-4-2-88-009.
RUN Mode (4) - In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRM protection and RBM interlocks in service (excluding the 15% high flux scram).
- 8. DESCRIPTION OF EVENT:
At 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br /> on March 1, 1988 Unit Two was operating in the RUN mode at approximately 96 percent of rated core thermal power. The Unit Two Nuclear. Station Operator (NS0) was in the process of performing QOS 1300-1, Reactor Core Isolation Cooling (RCIC)[BN] Monthly Test. This test employs a " fast start" testing method as described in General Electric Service Information Letter (GE SIL) 336. During this test, the RCIC system normally achieves full pump [P) flow of 400 gallons per 01nute (gpm) against a pump discharge pressure of 1,250 psig with turbine [TRB]
speed at approximately 4,500 rpm. However, in this event, the RCIC system was only able to achieve a pump flow of 400 gpm against a discharge pressure of 500 psig at I
a turbine speed of 3,000 rpm. Operating personnel in the RCIC room during turbine operation noted that the turbine governor-[65) valve [V) which is normally full open during standby operation, was closing satisfactorily upon turbine initiation but failed to open after the initial speed transient to increase turbine speed. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, RCIC was declared inoperable due to the inability of the RCIC pump to deliver at least 400 gpm against a system head corresponding to a reactor vessel l [RPV) pressure of 1,150 psig as required by Technical Specification Section 4.5.E.1. RCIC Outage Report, QOS 1300-01, was immediately initiated. NRC notification of the event via the Emergency Notification System (ENS) phone system was completed at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> to comply with the requirements of 10CFR50.72. Work l
Request Q64717 was written to investigate the problem and make repairs. The test was repeated at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> and at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on March 1, 1988. IM personnel were L in attendance to check operation of the flow controller [FC] in the control room L and the turbine governor valve and governor actuator in the RCIC room. IM l personnel determined that the cause of the turbine failing to increase speed was 1 due to a failed hydraulic actuator on the turbine governor valve.
1 The actuator was replaced on March 2, 1988, and QOS 1300-1 was successfully completed at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on March 2, 1988. The RCIC system was declared operable and the outage survelliances terminated.
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L 2317H/06832 l
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,, LICENSEE EVENT REPORT fLER) TEXT CQRTINUATION Form Rev 2.0 i DOCKET hupetR (2) LER NUMBER f6) L Paae (3)
FACILIJY NAME (1)t
,/pj $equential
// RevistGn
'i y
/// Number j///jj/ Number h j-Guad cities unit Two 0lEl010 1 0 1 21 61 E aia - O l013 - 0l1 013 0F 013.
TEXT Energy Industry Identification system (E!!s) codes are identified in the text as (XX] t C. APPARENT CAUSE OF EVENT:
This event is being reported according to 10CFR50.73(a)(2)(v)(B), which requires the reporting of any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat.
The cause of this event is component failure. The hydraulic actuator on the RCIC turbine governor closed satisfactorily but failed to open to increase turbine speed. The actuator was sent to the manufacturer, who determined that the problem was due to an electronic failure.
D. SAFETY ANALYSIS OF EVENT:
The safety of the plant and public was not affected during this event. The RCIC .
system is a standby safety system used to pump make-up water to the reactor vessel in the event of a reactor isolation accompanied by a loss of flow from the reactor feedwater system [S)). The RCIC system supplies sufficient make-up water to replace the water lost by steam generation as a product of core fission decay
< heat. The RCIC system will automatically initiate upon receipt of a reactor vessel low-low water level (-59 inches)[JE). If a low-low water level had occurred, all other Emergency Core Cooling Systems (ECCS) were available to bring the reactor to a safe shutdown condition.
E. CORRECTIVE ACTIONS:
The actuator was replaced line-for-like under Work Request Q64717. No problems were found with either the governor valve or the remote hydraulic servo which is
! hydraulically connected to the actuator and positions the governor valve. Since there are no previous reported fallures of this component, it is considered to be y an isolated incident. .No further corrective action is necessary.
l~ F.- PREVIOUS EVENTS There are no previous events similar to this one at Quad Cities Station. A search of the Nuclear Product Reliability Data System found no similar occurrences of failure of the hydraulic actuator on a turbine governor, u
G. COMPONENT FAILURE DATA:
, The hydraulic actuator is manufactured by Woodwaro Governor Company. It is a 1 Hoodward EG-R actuator and is supplied as an accessory for the GS Model Terry 1: Turbines.
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l 2317H/06832 l-
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