ML20045G095
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| ML20045G095 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/02/1993 |
| From: | Bax R, Radloff N COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-93-011-02, LER-93-11-2, RLB-93-091, RLB-93-91, NUDOCS 9307120082 | |
| Download: ML20045G095 (8) | |
Similar Documents at Quad Cities | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E2061994-05-11011 May 1994
[Table view]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 Category:RO) MONTHYEARML20029E2061994-05-11011 May 1994
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]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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