Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17352B2501993-10-0101 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 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 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 ML19277H2921984-06-25025 June 1984 LER 84-006-00:on 840601,discovered Weekly Power Operation Surveillance,Qis 60,not Executed within Tech Spec Limits. Caused by Personnel Error.Surveillance Test Immediately Performed.Weekly Summary Sheet displayed.W/840625 Ltr ML20024A4671983-06-0707 June 1983 LER 83-008/03L-0:on 830520,RHR Pump 2B Room Watertight Door Could Not Be Shut Tightly.Caused by Bent Pivot Arm.Arm Repaired & RHR B Loop Declared operable.W/830607 Ltr ML20028E2971983-01-12012 January 1983 LER 82-026/03L-1:on 820906,while Performing Cycle 7 Refueling Outage Local Leak Rate Test Program,Several Valves & Penetrations Found to Have Leakage in Excess of Tech Spec Limit.Causes & Corrective Actions Summarized in Encl Table ML20052H3001982-05-12012 May 1982 LER 82-007/03L-0:on 820415,during Surveillance Test Qos 1000-2,D Residual Heat Removal Svc Water Booster Pump Outboard Bearing Failed & Pump Declared Inoperable.Caused by Leakage from Adjacent Packing.Bearing & Packing Replaced ML20052E5471982-04-22022 April 1982 LER 82-006/03L-0:on 820412,pressure Switch PS-1-1001-89B Found Inoperable.Caused by Instrument Setpoint Drift of O Ring PS-1-1001-89B.Pressure Switch Recalibr & Functionally Tested ML20041B2441982-02-10010 February 1982 LER 82-001/03L-0:on 820113,during Routine Calibr of ECCS Level Switches,Switch LIS-1-263-72A Was Damaged.Caused by Instrument Personnel Not Being Familiar W/Tech Spec Requirements for Switches.Switch Repaired ML20040A5951982-01-0808 January 1982 LER 81-025/03L-0:on 811216,two Pipe Hangers for a Standby Gas Treatment Sys Declared Inoperable Due to Seismic Loading Design Deficiency.Caused by Change to Design Analysis Criteria.Pipe Hangers Redesigned & Installed ML20039G1631981-12-29029 December 1981 LER 81-019/03L-1:on 810929,penetrations on RHR Svc Water Pumps Found to Be Leaking.Caused by Pipe Vibration & Loosening of Penetration Seal Bolts.Penetrations Cleaned & Caulked & Seal Bolts Tightened as Needed ML20039G1661981-12-21021 December 1981 LER 81-017/03L-1:on 810907,relief Valve 2-203-3E in auto- Depressurization Sys Failed to Open.Caused by Grooves Worn in Disc Guide Sleeve by Rings of Main Valve Disc as Result of High Vibration ML20039C3231981-12-14014 December 1981 LER 81-020/03L-0:on 811121,water Found Entering Turbine Elevator Shaft at Approx 32 Ft from Bottom.Cause Unknown. Underground Section of Piping Isolated W/Cooling Water Being Supplied to Unit 1 a Loop from Unit 1 to Unit 2 Crosstie ML20038C2851981-12-0303 December 1981 LER 81-023/03L-0:on 811106,while Performing Functional Testing of Offgas Sys,Offgas Isolation Valves Failed to Close within Tech Spec Limit.Caused by Setpoint Drift.Timer Recalibr & Functionally Tested on 811201 ML20038B0051981-11-17017 November 1981 LER 81-024/03L-0:on 811019,temp Switches 2-1360-17B,16C & 17C Found to Trip in Excess of Tech Specs.Caused by Instrument Setpoint Drift.Switches Replaced ML20011A5271981-10-0202 October 1981 LER 81-016/03L-0:on 810902,required Surveillance Testing Not Performed Prior to Making Sgtts Train Inoperable.Caused by Personnel Error.Individuals Instructed on Need to Adhere to Procedures ML20009B9811981-07-0101 July 1981 LER 81-011/03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps ML20038B3901981-04-14014 April 1981 LER 81-008/03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed ML20038B3841981-04-14014 April 1981 LER 81-007/03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve ML20008F7221981-04-0606 April 1981 LER 81-006/03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced ML19345E9331981-01-21021 January 1981 LER 81-003/03L-0:on 810114,pressure Switch PS-1-1001-90D Tripped High.Caused by Instrument Setpoint Drift.Switch Recalibr ML20002C0861980-12-19019 December 1980 Fourth of Six Updated LERs 80-021/03L-0:on 800901,during Main Steam Line Drain Local Leak Rate Test,Valve MO-1-220-1 Found to Have Leakage in Excess of Tech Specs.Caused by Worn Seal Ring.Seal Replaced,Valve Repacked & Stroked ML20002C0921980-12-19019 December 1980 Sixth of Six Updated LERs 80-021/03L-1:on 800919,during Feedwater Check Valve Local Leak Rate Test,Leakage Through Feedwater Check Valve 1-220-62A Found Excessive.Caused by Dirty Valve Internals.Valve Retested ML19339B9031980-10-29029 October 1980 LER 80-027/01T-0:on 801015,during IE Bulletin 79-14 Reanalysis of safety-related Piping,Ten Pipes Failed to Meet Operability Criteria.Caused by Improper Const.Pipes Will Be Modified to Meet Requirements Prior to Startup ML19339B9191980-10-23023 October 1980 LER 80-024/03L-0:on 801010,valve MO-2-1-1001-34A Would Only Open Far Enough to Give Dual Position Indication.Caused by Limit Switches on Valve Operator Being Out of Adjustment. Limit Switches Adjusted & Control Switch Cleaned ML19347B3661980-09-29029 September 1980 LER 80-023/03L-0:on 800910,fire Barrier Penetrations Found W/O Sealing in Floor Between Cable Spreading Room & Auxiliary Electric Room.Caused by Const Personnel Failure to Follow Core Bore Procedure.Penetrations Sealed ML19338F0091980-09-24024 September 1980 LER 80-020/03L-0:on 800831,during Electromatic Relief Valve Operability Surveillance Qos 201-1,electromatic Relief Valve 1-203-3B Failed to Close.Caused by Steam Cutting of Pilot Valve Allowing Steam to Leak Out Exhaust Port ML19347B9901980-09-19019 September 1980 First of Five LERs 80-021/03L-0:on 800901,during Main Steam Line Local Rate Test,Valves AO 1-0203-2A,AO 1-0203-1B, AO 1-0203-2B,AO 1-0203-1D & AO 1-0203-2D Found to Have Leakage Rates in Excess of Tech Specs.Cause Not Stated ML19338C9481980-08-12012 August 1980 LER 80-017/03L-0:on 800724,during Testing,Pressure Switch PS-2-1622B Was Found to Actuate at 20.3 Rather than 13.8 Inches of Water.Caused by Setpoint Drift.Switch Replaced ML19321A7221980-07-22022 July 1980 LER 80-014/03L-0:on 800623,during Surveillance Check on HPCI Emergency Oil Pump,Found Oil Leak on Discharge Line.Caused by Cracked Threads on Pipe Nipple.Pipe Nipple Cut & Rethreaded ML19321A4571980-07-22022 July 1980 LER 79-021 Has Been Cancelled ML19321A7181980-07-21021 July 1980 LER 80-016/03L-0:on 800621,during Startup & Shutdown,Valve 1-203-2C Failed to Close While Testing.Caused by Improper Adjustment of Exhaust Restrictor on Pilot Valve.Pilot Valve Dismantled & Adjusted ML19320A8861980-06-26026 June 1980 LER 80-015/03L-0:on 800604,leak Found in HPCI Steam Supply Line.Caused by Thermal Cycling During Normal Operation, Weakening Small Section of Fillet Weld.Hpci Sys Taken Out of Svc,Weld Ground Out & Welded.Sys Returned to Svc ML19318B6611980-06-10010 June 1980 LER 80-010/03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted ML19318A5811980-06-0909 June 1980 LER 80-015/03L-0:on 800511,during Manual Operation of Relief Valves,Valve 1-203-3B Failed to Open.Hpci & Other Valves Operable.Caused by Dirty Contact on Valve Operator hold-in Coil Switch.Switch Replaced & Valve Returned to Svc 800512 ML19316B1401980-05-27027 May 1980 LER 80-013/03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts ML19316B1021980-05-27027 May 1980 LER 80-011/03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced ML19316B1151980-05-27027 May 1980 LER 80-012/03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor 1993-10-01
[Table view] Category:RO)
MONTHYEARML17352B2501993-10-0101 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 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 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 ML19277H2921984-06-25025 June 1984 LER 84-006-00:on 840601,discovered Weekly Power Operation Surveillance,Qis 60,not Executed within Tech Spec Limits. Caused by Personnel Error.Surveillance Test Immediately Performed.Weekly Summary Sheet displayed.W/840625 Ltr ML20024A4671983-06-0707 June 1983 LER 83-008/03L-0:on 830520,RHR Pump 2B Room Watertight Door Could Not Be Shut Tightly.Caused by Bent Pivot Arm.Arm Repaired & RHR B Loop Declared operable.W/830607 Ltr ML20028E2971983-01-12012 January 1983 LER 82-026/03L-1:on 820906,while Performing Cycle 7 Refueling Outage Local Leak Rate Test Program,Several Valves & Penetrations Found to Have Leakage in Excess of Tech Spec Limit.Causes & Corrective Actions Summarized in Encl Table ML20052H3001982-05-12012 May 1982 LER 82-007/03L-0:on 820415,during Surveillance Test Qos 1000-2,D Residual Heat Removal Svc Water Booster Pump Outboard Bearing Failed & Pump Declared Inoperable.Caused by Leakage from Adjacent Packing.Bearing & Packing Replaced ML20052E5471982-04-22022 April 1982 LER 82-006/03L-0:on 820412,pressure Switch PS-1-1001-89B Found Inoperable.Caused by Instrument Setpoint Drift of O Ring PS-1-1001-89B.Pressure Switch Recalibr & Functionally Tested ML20041B2441982-02-10010 February 1982 LER 82-001/03L-0:on 820113,during Routine Calibr of ECCS Level Switches,Switch LIS-1-263-72A Was Damaged.Caused by Instrument Personnel Not Being Familiar W/Tech Spec Requirements for Switches.Switch Repaired ML20040A5951982-01-0808 January 1982 LER 81-025/03L-0:on 811216,two Pipe Hangers for a Standby Gas Treatment Sys Declared Inoperable Due to Seismic Loading Design Deficiency.Caused by Change to Design Analysis Criteria.Pipe Hangers Redesigned & Installed ML20039G1631981-12-29029 December 1981 LER 81-019/03L-1:on 810929,penetrations on RHR Svc Water Pumps Found to Be Leaking.Caused by Pipe Vibration & Loosening of Penetration Seal Bolts.Penetrations Cleaned & Caulked & Seal Bolts Tightened as Needed ML20039G1661981-12-21021 December 1981 LER 81-017/03L-1:on 810907,relief Valve 2-203-3E in auto- Depressurization Sys Failed to Open.Caused by Grooves Worn in Disc Guide Sleeve by Rings of Main Valve Disc as Result of High Vibration ML20039C3231981-12-14014 December 1981 LER 81-020/03L-0:on 811121,water Found Entering Turbine Elevator Shaft at Approx 32 Ft from Bottom.Cause Unknown. Underground Section of Piping Isolated W/Cooling Water Being Supplied to Unit 1 a Loop from Unit 1 to Unit 2 Crosstie ML20038C2851981-12-0303 December 1981 LER 81-023/03L-0:on 811106,while Performing Functional Testing of Offgas Sys,Offgas Isolation Valves Failed to Close within Tech Spec Limit.Caused by Setpoint Drift.Timer Recalibr & Functionally Tested on 811201 ML20038B0051981-11-17017 November 1981 LER 81-024/03L-0:on 811019,temp Switches 2-1360-17B,16C & 17C Found to Trip in Excess of Tech Specs.Caused by Instrument Setpoint Drift.Switches Replaced ML20011A5271981-10-0202 October 1981 LER 81-016/03L-0:on 810902,required Surveillance Testing Not Performed Prior to Making Sgtts Train Inoperable.Caused by Personnel Error.Individuals Instructed on Need to Adhere to Procedures ML20009B9811981-07-0101 July 1981 LER 81-011/03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps ML20038B3901981-04-14014 April 1981 LER 81-008/03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed ML20038B3841981-04-14014 April 1981 LER 81-007/03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve ML20008F7221981-04-0606 April 1981 LER 81-006/03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced ML19345E9331981-01-21021 January 1981 LER 81-003/03L-0:on 810114,pressure Switch PS-1-1001-90D Tripped High.Caused by Instrument Setpoint Drift.Switch Recalibr ML20002C0861980-12-19019 December 1980 Fourth of Six Updated LERs 80-021/03L-0:on 800901,during Main Steam Line Drain Local Leak Rate Test,Valve MO-1-220-1 Found to Have Leakage in Excess of Tech Specs.Caused by Worn Seal Ring.Seal Replaced,Valve Repacked & Stroked ML20002C0921980-12-19019 December 1980 Sixth of Six Updated LERs 80-021/03L-1:on 800919,during Feedwater Check Valve Local Leak Rate Test,Leakage Through Feedwater Check Valve 1-220-62A Found Excessive.Caused by Dirty Valve Internals.Valve Retested ML19339B9031980-10-29029 October 1980 LER 80-027/01T-0:on 801015,during IE Bulletin 79-14 Reanalysis of safety-related Piping,Ten Pipes Failed to Meet Operability Criteria.Caused by Improper Const.Pipes Will Be Modified to Meet Requirements Prior to Startup ML19339B9191980-10-23023 October 1980 LER 80-024/03L-0:on 801010,valve MO-2-1-1001-34A Would Only Open Far Enough to Give Dual Position Indication.Caused by Limit Switches on Valve Operator Being Out of Adjustment. Limit Switches Adjusted & Control Switch Cleaned ML19347B3661980-09-29029 September 1980 LER 80-023/03L-0:on 800910,fire Barrier Penetrations Found W/O Sealing in Floor Between Cable Spreading Room & Auxiliary Electric Room.Caused by Const Personnel Failure to Follow Core Bore Procedure.Penetrations Sealed ML19338F0091980-09-24024 September 1980 LER 80-020/03L-0:on 800831,during Electromatic Relief Valve Operability Surveillance Qos 201-1,electromatic Relief Valve 1-203-3B Failed to Close.Caused by Steam Cutting of Pilot Valve Allowing Steam to Leak Out Exhaust Port ML19347B9901980-09-19019 September 1980 First of Five LERs 80-021/03L-0:on 800901,during Main Steam Line Local Rate Test,Valves AO 1-0203-2A,AO 1-0203-1B, AO 1-0203-2B,AO 1-0203-1D & AO 1-0203-2D Found to Have Leakage Rates in Excess of Tech Specs.Cause Not Stated ML19338C9481980-08-12012 August 1980 LER 80-017/03L-0:on 800724,during Testing,Pressure Switch PS-2-1622B Was Found to Actuate at 20.3 Rather than 13.8 Inches of Water.Caused by Setpoint Drift.Switch Replaced ML19321A7221980-07-22022 July 1980 LER 80-014/03L-0:on 800623,during Surveillance Check on HPCI Emergency Oil Pump,Found Oil Leak on Discharge Line.Caused by Cracked Threads on Pipe Nipple.Pipe Nipple Cut & Rethreaded ML19321A4571980-07-22022 July 1980 LER 79-021 Has Been Cancelled ML19321A7181980-07-21021 July 1980 LER 80-016/03L-0:on 800621,during Startup & Shutdown,Valve 1-203-2C Failed to Close While Testing.Caused by Improper Adjustment of Exhaust Restrictor on Pilot Valve.Pilot Valve Dismantled & Adjusted ML19320A8861980-06-26026 June 1980 LER 80-015/03L-0:on 800604,leak Found in HPCI Steam Supply Line.Caused by Thermal Cycling During Normal Operation, Weakening Small Section of Fillet Weld.Hpci Sys Taken Out of Svc,Weld Ground Out & Welded.Sys Returned to Svc ML19318B6611980-06-10010 June 1980 LER 80-010/03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted ML19318A5811980-06-0909 June 1980 LER 80-015/03L-0:on 800511,during Manual Operation of Relief Valves,Valve 1-203-3B Failed to Open.Hpci & Other Valves Operable.Caused by Dirty Contact on Valve Operator hold-in Coil Switch.Switch Replaced & Valve Returned to Svc 800512 ML19316B1401980-05-27027 May 1980 LER 80-013/03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts ML19316B1021980-05-27027 May 1980 LER 80-011/03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced ML19316B1151980-05-27027 May 1980 LER 80-012/03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor 1993-10-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000254/LER-1999-004-03, :on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-021999-10-12012 October 1999
- on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-02
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure1999-10-0707 October 1999
- on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
ML20217A9931999-09-30030 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 ML20216H8481999-09-23023 September 1999 Safety Evaluation Supporting Amends 190 & 187 to Licenses DPR-29 & DPR-30,respectively 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 ML20210U7831999-08-0404 August 1999 Safety Evaluation Supporting Amends 189 & 186 to Licenses DPR-29 & DPR-30,respectively 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 ML20196F4261999-06-25025 June 1999 Safety Evaluation Supporting Amends 188 & 185 to Licenses DPR-29 & DPR-30,respectively 05000265/LER-1999-002-04, :on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 9907151999-06-25025 June 1999
- on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 990715
05000254/LER-1999-004-02, :on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised1999-06-18018 June 1999
- on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised
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 ML20210H3501999-05-25025 May 1999 Rev 1 to Quad Cities Station IPEEE Submittal Rept ML20207E1621999-05-25025 May 1999 Rev 1 to Quad Cities IPEEE, Consisting of Revised Chapter 4.0 Re Internal Fire Analysis 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 05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance1999-05-12012 May 1999
- on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
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 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 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 ML20205F4791999-03-31031 March 1999 Safety Evaluation Supporting Amends 187 & 184 to Licenses DPR-29 & DPR-30,respectively 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 ML20205D4171999-03-26026 March 1999 Safety Evaluation Supporting Amends 186 & 183 to Licenses DPR-29 & DPR-30,respectively ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20204D9751999-03-17017 March 1999 Safety Evaluation Supporting Amends 185 & 182 to Licenses DPR-29 & DPR-30,respectively 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 ML20198S6841998-12-22022 December 1998 Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition ML20196F8931998-12-0303 December 1998 Safety Evaluation Supporting Amend 182 to License DPR-29 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 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 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 ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 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 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-98-358, 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-98-346, 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 05000254/LER-1998-001-01, :on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation1998-10-27027 October 1998
- on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation
05000265/LER-1998-006-04, :on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-061998-10-15015 October 1998
- on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-06
1999-09-30
[Table view] |