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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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Conimonw;alth Edison - '!
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ouad Citts Nuciear Power Stttion _)b . :
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ryj 22710 206 Avenue North -
Cordova, lihnots 61242-9740,
'- ( Telephone 309/654 2241.
RLB-91-073
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' March 6, 1991-U. S. Nuclear Regulatory Commission.
Document Control. Desk ~~
Hashington,.DC120555=
e
Reference:
-Quad lC) ties Nuclear Power Station Docket Number 50-254, DPR-29, Unit One i k Enclosed is Licensee Event, Report (LER)91-005, kevision 01, for Quad C1 ties Nuclear-Power Station.
b Respectfully, .
COMMONHEALT!i EDISON ' COMPANY (QUAD CITIES NUCLEAR POWER STATION
.g y
- R. L. Bat -
Station Manager
- RLB/TB/kas-4 l-Enclosure
.cc: R. Stols. /
- i. T. Taylor /
, .INPO Records Center NRC Region III.
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.STMGR 55 9103260175 910308 -
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Y .: t.ICENSEE EVENT REPOR7-(LER)
F e Rev 2 1 Facility Name (1) Docket Number (3) ~ _f.ARIL f 31 ad cities
- Unit One 01 El 01 01 01 21 51 4 1 of 0 5 Title'(4) 1/2 B SBGT Unernected Autostart Durino RPS B Power Swan Due To An Inadeauate Proeggure Event Date fE1 LER Number (61 Recort Date (7) Other racilities Involved _fB1 Month Day Year Year /,/p/ sequential ,/p,/ / Revision Month. Day Year Facility Names Docket Numbarfs)
/// Number /// Number 01 51 of 01 01 I l
~~~ ~~
01 1 31 1 91 1 91=1 0 1 0-l 5 0l1 013 ol 8 91 1 01 El 01 01_01 1 1 OPERATING' l.C.bigk one or more of the followina) i111 1 20.402(b) __ 20.405(c) X., 50.73(a)(2)(iv) 73.71(b)
POWER ,,, 20.405(a)(1)(1) 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c)
LEVEL 20.405(a)(1)(11) __ 50.36(c)(2) __ 50.73(a)(2)(vii) Other (specify f101 0! 01 0 20.4!)S(a)(1)(iii) 50.73(a)(2)(1) _, 50.73(a)(2)(v111)(A) in Abstract
///////////////,/////////// 20.405(a)(1)(iv) 50.73(a)(2)(li) _ 50.73(a)(2)(viii)(B) bel a and in
///////////////'j/////////// 20.405(a)(1)(v) _ 50.73(a)(2)(111) ,__ 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR THIS LER f121
.Name TELEPHONE NUMBER AREA CODE David Harmon.-Technical Staff Enaineer Ext. 2116 3 10l9 61SI41-l2121411 COMPLETE ONE LINE FOR EACH COM T FAILURE DESCRIBED IN THIS REPORT (131 CAusE SYSTEM COMPONENT MANuFAC- REPORTABLE CAuSE SYSTEM COMPONENT. MANurAC- REPORTABLE
///%/ f TURER TO NPRDS TURER TO NPROS ^/
I I I I I i 1 1 1 1 I I i 1 //
j, l 1 I I I i 1 '/ 1 I I I I I I //
SUPPLEMENTAL REPORT EXPECTED f141 Expected Month l Day l Year submission lyes fif ves. comolete EXPECTED SUBMISSION DATE) X l No l ll ll A8sTRACT (Limit to 1400 spaces i.e. approximately fif teen single-space typewritten lines) (16)
ABSTRACT:
'On January 31, 1991, at 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br />, Unit One was in SHUTDOHN mode and Unit Two was
'in_RUN mode at 94 percent!of rated core thermal power. Operating personnel .
performed a Reactor Protection System (RPS) power supply transfer. As expected, it caused a 1/2 scram and-1/2 Group II and III isolations, which resulted in the 1/2 B Standby Gas Treatment System (SBGTS) autostart timer starting.
The NSO reset the 1/2 scram. 1/2_B SBGTS unexpectedly autostarted before the NSO l reset the-1/2 group-II and III isolt.tions. The NSO secured 1/2 B-SBGTS and L operability-tested 1/2 A SBGTS.
l An Emergency Notification System (ENS) phone notification was completed at 0001
- . hours on February 1, 1991, under 10CFR50.72(b)(2)(11).
'Both units entered a 7 day LCO intil Operating personnel verified the accuracy of-the.1/2 8 SBGTS 25 second autostart timer. Operating personnel determined-that RPS and SBGTS functioned as-designed.
The cause of the event was-that the procedure failed to specify that the NSO must reset the 1/2 group II and III isolations within.25 seconds of loss of power to RPS in order to prevent autostart of 1/2 B SBGTS. A procedure correction was implemented.
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l' LICENSELLyENT REPORT f LtRi TEX 7 C0_NTINUATION Form Rev 2.0_
DOCKET NUMBER (2) LER NUMBER f61 Pace (31 p . FACILITY NAME (1)
Year /// sequential l /// Revision p/,/j/ Number j/// Number
_00Ad Cities Unit One 0 1 5 1 0 1 0 1 0 1 21 El 4 9l 1 010l $ - 0l i el 2 0F 01 5 TEXT Energy Industry Identification system (Ells) codes are identified in the text as (Xx) i PLANT AND SYSTEM IDENTIFICATION:
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT IDENTIFICATION: 1/2 B SBGT Unexpected Autostart During RPS B Power Swap Due To An Inadequate Procedure A. CONDITIONS PRIOR TO EVENT:
Unit: One Event Date: January 31, 1991 Event Time: 2015 Reactor Mode: 1 Mode Name: SHUTDOWN Power Level: 00%
This report was initiated by Deviation Report D-4-1-91-025 SHUTDOWN Mode (1) - In this position, a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection trip systems have been deenergized for 10 seconds prior to permissive for manual reset.
B.. DESCRIPTION OF EVENT:
On January 31, 1991, at 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br />, Unit One was in SHUTDOWN mode for scheduled refueling outage QlRil and Unit Two was in RUN mode at 94 percent of rated core thermal power. Operating (0P) personnel perfornied procedure QOP 7000-1, Reactor Protection System [JC) (RPS) Motor [MO) Generator [ GEN) (MG) Sets. Immediately thereafter, the 1/2 B train of Standby Gas Treatment Sytem (BH] (SBGTS), which was in STANDBY mode, unexpectedly autostarted.
Prior to this, at approximately 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on January 31, 1991, OP personnel began performing QOP 7000-1. This procedure instructs OP personnel on how to energize, de-energize, and switch RPS power supplies [UJX) between normal and reserve power.
At 2013:31 hours, an Equipment Operator (EO) switched the power supply to RPS Channel B (RPS B) from reserve to normal power. This power supply switching caused an expected momentary loss of power to RPS B which de-energized Primary Containment Isolation (PCI) Group II B relay (RLY) logic. This logic de-energization, in turn, started the 1/2 B SBGTS 25 second autostart timer CTMR). At the same time, the Unit One Nuclear Station Operator (NS0) received a 1/2 scram signal on the 901-5 panel, and PCI 1/2 Group II and III isolation signals on the 901-5 panel. All of these signals normally occur on de-energization of an RPS bus [BU). The NSO restored normal power to RPS B ana reset the 1/2 scram at 2013:32 hours.
1/2 A SBGTL was in PRIMARY at the start of the event and remained nonactive during
/ the event as designed. At approximately 2013:56 hours, 1/2 B SBGTS autostarted unexpectedly. Review of the logic later showed that 1/2 A SBGTS did not receive an autostart signal, and that 1/2 B SBGTS autostarted as designed (when the 25 second autostart timer timed-out.)
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4 LICENSEE EVENT REPORT fLER1 TEX 7 CONTINUATION _ EQIhLRtwM FACILITY NAME (1) DOCKET NUMBER (3) L E R NUME E'2 ( 6 )
Pace (1) j Year p//
/ sequential' /// Revtsion
- /j/j/ _ N_ umber
,/j/j/ Numbgr._
Ouad Cities Unit One 0l51010l0 1 21 El 4 9l 1 - 010 15 - 0l 1 01._3 0F 01 5 TEXT Energy Industry Identification system (E!!s) cooes are identified in the trixt as (XX)
At approximately 2014:00 hours, the NSO reset the 1/2 Group II and III isolations using the isolation reset switch, ISOL RESET, on the 901-5 panel. This also reset the 1/2 B SBGTS autostart signal and autostart timer.
At 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br />, the NSO shut down 1/2 B SBGTS and returned it to STAND 0Y mode.
The Shift Engineer (SE) directed the NSO to perform procedure Q05 7500-S, SBGTS Monthly Operability Test, to verify operability of 1/2 A SBGTS. Technical Specifications (Tech Specs) section 3.7.B.1 requirec that one SBGTS train be demonstrated operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of finding the other train inoperable. This operability verification was intentionally conservative to the intent of Tecn Specs since 1/2 B SBGTS had not been declared inoperable. At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, the HSO began to perform the test, which takes a minimum cf 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete.
At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, the SE initiated a Deviation Report (DVR). Operating personnel continued to investigate the event due to uncertainty about the 1/2 B SBGTS autostart timer. The exact time at which 1/2 B SBGTS autostarted was not available on the computer.
An Emergency Notification System (ENS) phone notification was completed at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on February 1, 1991, under 10CFR50.72(o)(2)(li).
At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on February 1, 1991, the SE declared 1/2 B SBGTS inoperable and initiated outage report QOS 7500-01, SBGTS One Circuit Operation Outage Report 7 Day Limitation. OP personnel were still uncertain about the 1/2 B SBGTS autostart timer. Both units entered a 7 day Limiting Condition for Operation (LCO) retroactive to 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br /> on January 31, 1991.
At 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on February 1,1991, Operating personnel concluded that RPS and 1/2 B SBGTS had functioned as designed, and that the autostart occurred because the NSO did not reset the 1/2 Group II and III isolations within 25 seconds of the power supply switching. Because the procedure had been successfully performed prior to this event, they suspected that the autostart timer may have timed-out early. To test the accuracy of the 1/2 B SBGTS autostart timer, OP personnel decided to perform step 3 of QOS 7500-4, Standby Gas Auto Initiation and Reactor Building Ventilation Auto Isolation. This test would place both units in a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO per Tech Spec section 3.7.B.I.b-At 1723 hours0.0199 days <br />0.479 hours <br />0.00285 weeks <br />6.556015e-4 months <br />, OP personnel olaced both units in a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO and performed the test. They timed the 1/2 B SBGTS timer to actuate at 24.75 seconds, which is within accep;able tolerance limits.
OP personnel completed the test by 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br /> and concluded that RPS and SBGTS functione) as designed throughout the event. The 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO for both SBGTS trains inoperab e and the 7 day LCO for B SBGTS train incoerable were terminated.
3408H
1 r LICENSEE EVENT REPOR7 (LER) TEXV CONTINUATION Form Rev 2.0 FAc1LITY NAME (1) DOCKE7 NUMBER (2) LER NUMBER g) Pace f3) j Year /// sequential // Revision p/jj/ / Wumber
/p/p/,
/ humber--
l Ouad Cities Unit One 01510 1 0 1 0 1 21 51_ L9 1 i I - 010 15 - 0 l 1 01 4 0F 01 5 TEXT Energy Industry Identification system (Ells) codes are identified in the text as (XX]
C. APPARENT CAUSE OF EVENT:
751s report is being submitted to comply with 10CFR50.73(a)(2)(iv). It requires the licensee report any event or condition that resulted in manual or automatic actuation of an) Engineered Safety Feature [JE] (ESF), including the RPS, except an actuation which is part of a preplanned sequence during testing or reactor operation. SBGTS is an ESF and the autostart was not preplanned.
The apparent cause of the event is an inadequate procedure. QOP 7000-1 does not adequately caution the NSO concerning the SBGTS autostart timer. QOP 7000-1 provided no information concerning SBGTS and referred the NSO to Q0A 7000-1, 120 Volts Alternating Current (TAC) Reactor Protection Bus [BU) Failure (One or Both Buses), for additional a;iomatic actuations associated with RPS bus transfers.
00A '000-1 step B.3.1. stated, "B SBGTS will start after 25 seconds if in STANDBY and power is not restored to B RPS within 25 seconds " The procedure did not stipulate that the 1/2 Group II isolation must be reset within 25 seconds to prevent 1/2 B SBG15 from autostarting.
D. SAFETY ANALYSIS OF EVENT:
The safety of the public and plant personnel were not affected by this event. RPS and SBGTS functionid as designed throughout the event.
OP personnel placed both units in a 7 day LC0 to be conservative to Tech Specs section 3.7.B.I.a. because they were un'ertain about the 1/2 B SBGTS autostart timer. Tech Specs section 3.7 B.I.a. also required a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO if both SBGTS chanra.s are inoperable. OP personnel placed both units in a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO to test the 1/2 B SBGTS autostart timer and terminated both LCO's immediately after the timer test, which took about two minutes.
E. CORRECTIVE ACTIONS:
The immediate corrective actions taken by the NSO were to reset the 1/2 scram and 1/2 ,roup II and III isolations, and to return 1/2 B SBGTS to STAN0BY mode.
The NSO verified tne operability of 1/2 SBGTS A in compliance with Tech Specs. The accuracy of the 1/2 B SBGTS autostart timer was also verifled.
OP personnel implemented a procedure change to 00A 7000-1 which corrected step B.3.1 to say "B SBGTS will start after 25 seconds if in STANDBY and power is not restored to B RPS and Group II is not reset within 25 seconds." 1/2 Group II and III isolations are retet using the ISOL RESET switch on 901-5 panel. Using this switch will also reset the 1/2 B SBGTS autostart timer.
{
340eM
4 LICENSEE EVENT REPORT (LER) TEX M 71NUAT10N Form;P'Ay 2.0
' LER NUMBER (6) Pard 3 )
., . FACILITY CAME (1)' DOCKE7 NUMBER (2)
Year sequer.t tal /// Revision 8
- )f
///) Number / Number __
Ouad citie? Unit one 0 l E I o 1 0 1 0 1 21 51 4 911 - 01015 - 01 1 .01 Sl 0F !01s TEXT Energy Industry identification system (Ells) codes are identified in the text as [XX)
F. PREVIOUS EVENTS:
There have been no similar previous events reported. As this event did not involve a component failure, a Nuclear Plant Reliability Data System (NPRDS) search was not conducted.
Y G. COMPONENT FAILURE DATA:
There is no component failure associated with this event.
a 6
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