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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046B1481993-07-30030 July 1993 LER 93-012-00:on 930702,reactor Core Isolation Cooling Sys Declared Inoperable Due to Associated Bus Voltage Dropping Below TS Limits.Sent Operator to Cycle Timer Which Caused Affected Contact to reclose.W/930730 Ltr ML20045D9331993-07-0202 July 1993 LER 93-004-00:on 930604,unexpected CRD Low Charging Water Header Scram Received Followed by Charging Water Header A2/B2 Alarm.Caused by Crud or Foreign Matl Passing Through Suction Filter.Filters Cleaned & reused.W/930702 ML20045D7501993-06-23023 June 1993 LER 93-003-00:on 930524,Div 1 ECCS Initiation Signal Received & LPCS Pump,Lpci Pump 2A & EDG Unit 0 Automatically Started.Caused by Personnel Error.Pumps Secured & Event Documented in Personnel file.W/930623 Ltr ML20044E4161993-05-28028 May 1993 LER 92-009-01:on 920923,spurious Auto Start of CR Ventilation Emergency make-up Train Occurred Due to High Radiation Spike.Radiation Monitor Circuit modified.W/930528 Ltr ML20044E4191993-05-21021 May 1993 LER 93-011-00:on 930423,manual Scram Initiated.Caused by Disconnected Linkage on Valve Positioner on Heater Drain Valve Due to Loose Jam Nut.Tailgate Session Will Be Held W/ Instrument Maint Dept Re Jam nuts.W/930521 Ltr ML20044D5161993-05-15015 May 1993 LER 92-007-01:on 920613,high Radiation Spike Received from CR Ventilation Process Radiation Monitor,Initiating Emergency Makeup Train B.Caused by Normal Variations in Radiation Readings.Spike modified.W/930515 Ltr ML20044D5571993-05-14014 May 1993 LER 93-010-00:on 930414,DG Cooling Water Pump Automatically Tripped on Magnetic Overload.Caused by Inexperienced Trainee in Operation of Control Lever.Lesson Plans & Training Programs for Operators to Be reviewed.W/930514 Ltr ML20044C9801993-05-0707 May 1993 LER 91-010-01:on 910719 & 0805,CR a Ventilation Emergency Makeup Fan auto-started on Spurious Trip of CR Air Intake Process Radiation Monitor.Caused by Normal Variations in Background Radiation.Supply Board replaced.W/930507 Ltr ML20044B6161993-02-25025 February 1993 LER 93-002-00:on 930126,Unit 1 Manual Scram Due to a SRV Being Stuck Open Due to Duct Tape Being Over Actuators Air Valve Manifold Exhaust Port.Maint Procedures That Involve Cleanliness reviewed.W/930225 Ltr ML20024G9771991-05-10010 May 1991 LER 91-005-00:on 910410,determined That Tech Spec Required Surveillance of Suppression Chamber Oxygen Sampling Missed. Caused by Inadequate Review of Tech Spec Change.Drywell & Suppression Chamber Checked for oxygen.W/910510 Ltr ML20044A3851990-06-25025 June 1990 LER 90-008-00:on 900525,Tech Spec Hourly Fire Watch Missed Due to Miscommunications Between Security Personnel & Radiation Protection Personnel.Fire Watch re-established & Memo issued.W/900625 Ltr ML20043F1721990-06-0505 June 1990 LER 90-009-00:on 900510,RWCU Outboard Suction Isolation Valve 2G33-F004 Auto Closed Which Tripped RWCU Pump B. Caused by Procedure Deficiency.Procedure LTS-500-209 Will Be revised.W/900605 Ltr ML20043F1281990-06-0101 June 1990 LER 90-009-00:on 900511,apparent Ruptured Diaphragm Found on Pressure Differential Switch in RCIC Steam Line.Caused by Torn Diaphragm Inside Switch.Replacement Switch Installed, Calibr & Functionally Tested satisfactorily.W/900608 Ltr ML20043B5681990-05-23023 May 1990 LER 89-027-01:on 891113,primary Containment Isolation Sys Group 1 Isolation Occurred During Surveillance Testing. Caused by Burnt Out Window Light Bulbs on Alarm Window. Light Bulbs Replaced & Jumpers installed.W/900523 Ltr ML20043A7721990-05-18018 May 1990 LER 90-007-00:on 900421,reactor Protection Sys Bus a Transfer & Reactor Recirculation Hydraulic Power Unit a Inboard Isolation Valves Closed,Causing Partial Group II isolation.Out-of-svc Procedure revised.W/900518 Ltr ML20043D0591990-05-18018 May 1990 LER 90-008-00:on 900502,ESF Actuation of Control Room B Emergency Ctk Ventilation Makeup Fan Occurred.Caused by Procedure deficiency.LTS-800-205 & Similar Procedures Will Be revised.W/900601 Ltr ML20042H0211990-05-10010 May 1990 LER 90-006-00:on 900412,loop a Primary Containment Chilled Water Sys Inboard Isolation Valves & Reactor Bldg Closed Cooling Water Sys Inboard Isolation Valve Went Closed.Caused by Inadequate Procedure.Procedures revised.W/900510 Ltr ML20042F9001990-05-0404 May 1990 LER 90-005-00:on 900411,experienced Loss of Dc Power to Portion of Div I Primary Containment Isolation Sys Logic Which Resulted in Isolation Signal & Actuation.Caused by Failure to Update Drawings & procedures.W/900504 Ltr ML20042F1941990-04-30030 April 1990 LER 89-025-01:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Door Containing Undervoltage Relays Closed.Caused by Misalignment of Door.Door Repaired. W/900430 Ltr ML20012D5341990-03-16016 March 1990 LER 90-003-01:on 900201,RCIC Isolation Signal Occurred During Warmup.Caused by Spurious High Steam Flow Signal.Rcic Sys Piping Integrity Verified & Isolation Logic Reset.W/ 900316 Ltr ML20012D5371990-03-16016 March 1990 LER 90-002-01:on 900129,oil in Diesel Generator Governor 1A Found to Be Low & Could Not Be Seen in Sight Glass.Caused by Slow Leak from Compensation Needle Valve Plug.Proper Amount of Oil Added & Operability Test performed.W/900316 Ltr ML20012C4931990-03-15015 March 1990 LER 90-004-00:on 900213,control Room B HVAC Intake Radiation Monitor Lost Power Causing auto-start of Emergency make-up Train B.Caused by Blown Fuses.Fuses Replaced.Logic Revs for Radiation Monitors Will Be installed.W/900315 Ltr ML20012B6501990-03-0909 March 1990 LER 90-002-00:on 900209,Operating Surveillance LOS-TG-W1 Determined to Have Exceeded Required Testing Interval,Per Tech Spec 3/4.7.10.Caused by Personnel Error.Personnel Counseled & Ref Procedures Will Be revised.W/900309 Ltr ML20012B5521990-03-0808 March 1990 LER 90-001-00:on 900206,full Reactor Scram Occurred During Instrument Surveillance Testing.Caused by Actuation of APRM E Trip Circuitry.Shutdown Margin Revised & Caution Card Placed on Control Room Bench board.W/900308 Ltr ML20011F8251990-03-0202 March 1990 LER 90-003-00:on 900201,RCIC Received Div 2 Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal Generated When Steam/Water Mixture Admitted to RCIC Steam Line.Isolation Logic reset.W/900302 Ltr ML20011F5551990-02-28028 February 1990 LER 90-002-00:on 900129,after Filling Diesel Generator 1A Governor W/Oil,Generator Started & Declared Inoperable. Caused by Slow Leak Coming from Compensation Needle Valve Plug.Oil Added & Plug Washer replaced.W/900228 Ltr ML20006F5951990-02-21021 February 1990 LER 90-001-00:on 900122,RWCU Sys Received Div 1 Leakage Detection Ambient Temp High Isolation Signal,Causing Trips of RWCU Pumps a & C.Caused by Broken Thermocouple Input Lead.Lead Wire Reconnected & Isolation reset.W/900221 Ltr ML20011F4921990-02-16016 February 1990 LER 89-013-01:on 890907,Group I Isolation Received During Performance of Instrument Surveillance LIS-MS-401.Caused by Depressurization of Main Steam Line Low Pressure Switch. Surveillance Revised to Split Into Two parts.W/900216 Ltr ML20006E4501990-02-15015 February 1990 LER 89-010-01:on 890715 & 17,voltage Oscillations Noted on Div II Battery Charger,Resulting in Inoperability of HPCS Sys.Caused by Failure of Charger in High Voltage Shutdown Relay.Charger Energized & Relay replaced.W/900215 Ltr ML20006E4451990-02-14014 February 1990 LER 89-009-01:on 890619,diaphragm Leak Discovered in RCIC Steam Line High Flow Isolation Switch.Caused by 1 & 1/2-inch Tear in Diaphragm.Pressure Differential Switch Replaced & Calibr.Reported Per NRC Bulletin 86-002.W/900214 Ltr ML20006E3981990-02-14014 February 1990 LER 89-008-01:on 890228,reactor Vessel Low Water Level 2 Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.Channel Placed in Tripped Condition & All Static-O-Ring Pressure Switches to Be replaced.W/900214 Ltr ML20006E3951990-02-14014 February 1990 LER 89-010-01:on 890303,automatic Depressurization Sys Permissive Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.All Static-O-Ring Reactor Vessel Level Switches Will Be replaced.W/900214 Ltr ML19354D8361990-01-15015 January 1990 LER 89-018-00:on 891216,plant 250-volt Battery & RCIC Sys Declared Inoperable Due to Low Battery Electrolyte Temps. Caused by Failure of Div I Switchgear Heat Removal Sys Damper Actuators.Air Intake Dampers closed.W/900115 Ltr ML20042D3921990-01-0404 January 1990 LER 89-011-01:on 890826,spurious Reactor Protection Sys Actuation Occurred.Definite Cause of Trip Not Determined. Brief Disturbance in Reactor Protection Sys Allowed Some Contactors to Trip.Procedure revised.W/900104 Ltr ML20005E2741989-12-22022 December 1989 LER 89-028-00:on 891204,RHR Shutdown Cooling Suction Header Outboard Isolation Valve Automatically Isolated.Caused by Miscommunication Between Technician & Station Operator.Task Force Developed to Review event.W/891222 Ltr ML19351A6301989-12-15015 December 1989 LER 89-006-01:on 890214,reactor Vessel Low Water Level 3 Switch Setpoint Found Out of Tolerance.Caused by Setpoint Drift.Level Switch to Be Replaced by Analog Trip Sys During First Quarter 1990.W/891215 Ltr ML20011D1341989-12-14014 December 1989 LER 89-017-00:on 891117,flow Switch FS-2E22-N006 Found W/ Setpoint Out of Tolerance Above Reject Limit.Caused by Setpoint Drift.Work Request Written to Replace Flow Switch. W/891214 Ltr ML19351A6751989-12-12012 December 1989 LER 89-027-00:on 891113,primary Containment Isolation Sys Group I Isolation Occurred While Performing Instrument Surveillance.Caused by Loss of Power to Leak Detection Sys Logic.Isolation reset.W/891213 Ltr ML19332F0081989-12-0808 December 1989 LER 89-016-00:on 891109,RWCU Isolation Occurred While Instrument Surveillance on Ventilation Differential Temp Isolation Functional Test in Progress.Caused by Faulty Thermocouple.Thermocouple repaired.W/891208 Ltr ML20005D6621989-12-0606 December 1989 LER 89-026-00:on 891106,inadvertent Primary Containment Isolation Actuation Occurred While Clearing out-of-svc. Caused by Inadequate Logic Setup During Mod Installation. Trip Status & Output Switches repositioned.W/891206 Ltr ML19332F2431989-12-0101 December 1989 LER 89-025-00:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Equipment Operator Closed Door Containing Relays.Caused by Misalignment of Door.Isolations Reset,Bus Energized & Circuit Logic tested.W/891201 Ltr ML19332E6581989-11-29029 November 1989 LER 89-015-00:on 891030,shift Control Room Engineer Noted That Quarterly Standby Liquid Control Operating Surveillance LOS-SC-Q1 Was Past Critical Date.Caused by Clerical Data Entry Error.Missed Surveillance performed.W/891129 Ltr ML19332D5181989-11-22022 November 1989 LER 89-018-01:on 890515,RCIC Received Div I & Div II Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal When Steam Added to RCIC Steam Line. Special Test Initiated.Isolation Logic reset.W/891122 Ltr ML19327C2601989-11-17017 November 1989 LER 89-014-00:on 891020,primary Containment Isolation Sys Group 4 Isolation Occurred Causing Isolation Dampers to Close.Caused by Opening of Div 2 125-volt Dc Breaker.Power Supply replaced.W/891117 Ltr ML19325F3411989-11-13013 November 1989 LER 89-024-00:on 891013 & 30,unsealed Openings in Main Control Room Floor & Main Control Room West Wall Discovered. Caused by Wide Gap Between Structural Beam & Cable Tray. Openings Sealed & Fire Watch established.W/891113 Ltr ML19324C1751989-11-0808 November 1989 LER 89-012-01:on 890309,diaphragm Leak Found in Pressure Differential Switch 1E31-N013BB.Caused by Tear Found in Diaphragm.Replacement Switch Installed,Calibr & Functionally Tested satisfactorily.W/891108 Ltr ML20024E9121983-08-26026 August 1983 LER 83-093/03L-0:on 830801,discovered full-in Indication on Core Display for Control Rod 34-47 Inoperable.Caused by Failed Switching Transistor on Data Memory Board 19.Data Memory Board replaced.W/830826 Ltr ML20024B8381983-07-0505 July 1983 LER 83-060/03L-0:on 830606,following Turbine Trip & Scram Due to High Vibration on Main Turbine,Reactor Recirculation Breaker 4B Closed.Cause Undetermined.Auxiliary Contacts cleaned.W/830705 Ltr ML20024B0721983-06-16016 June 1983 Updated LER 83-012/03X-1:on 830210,w/reactor in Cold Shutdown,Setpoints for Switches 1E31-N612A/B Found Above Tech Spec Limits.Cause Unknown.Switches calibr.W/830616 Ltr ML20024A6961983-06-14014 June 1983 LER 83-051/03L-0:on 830516,reactor Protection Sys Trip Channel H2 Limit Switch Failed to Operate Properly.Cause Unknown.Limit Switch readjusted.W/830614 Ltr 1993-07-30
[Table view] Category:RO)
MONTHYEARML20046B1481993-07-30030 July 1993 LER 93-012-00:on 930702,reactor Core Isolation Cooling Sys Declared Inoperable Due to Associated Bus Voltage Dropping Below TS Limits.Sent Operator to Cycle Timer Which Caused Affected Contact to reclose.W/930730 Ltr ML20045D9331993-07-0202 July 1993 LER 93-004-00:on 930604,unexpected CRD Low Charging Water Header Scram Received Followed by Charging Water Header A2/B2 Alarm.Caused by Crud or Foreign Matl Passing Through Suction Filter.Filters Cleaned & reused.W/930702 ML20045D7501993-06-23023 June 1993 LER 93-003-00:on 930524,Div 1 ECCS Initiation Signal Received & LPCS Pump,Lpci Pump 2A & EDG Unit 0 Automatically Started.Caused by Personnel Error.Pumps Secured & Event Documented in Personnel file.W/930623 Ltr ML20044E4161993-05-28028 May 1993 LER 92-009-01:on 920923,spurious Auto Start of CR Ventilation Emergency make-up Train Occurred Due to High Radiation Spike.Radiation Monitor Circuit modified.W/930528 Ltr ML20044E4191993-05-21021 May 1993 LER 93-011-00:on 930423,manual Scram Initiated.Caused by Disconnected Linkage on Valve Positioner on Heater Drain Valve Due to Loose Jam Nut.Tailgate Session Will Be Held W/ Instrument Maint Dept Re Jam nuts.W/930521 Ltr ML20044D5161993-05-15015 May 1993 LER 92-007-01:on 920613,high Radiation Spike Received from CR Ventilation Process Radiation Monitor,Initiating Emergency Makeup Train B.Caused by Normal Variations in Radiation Readings.Spike modified.W/930515 Ltr ML20044D5571993-05-14014 May 1993 LER 93-010-00:on 930414,DG Cooling Water Pump Automatically Tripped on Magnetic Overload.Caused by Inexperienced Trainee in Operation of Control Lever.Lesson Plans & Training Programs for Operators to Be reviewed.W/930514 Ltr ML20044C9801993-05-0707 May 1993 LER 91-010-01:on 910719 & 0805,CR a Ventilation Emergency Makeup Fan auto-started on Spurious Trip of CR Air Intake Process Radiation Monitor.Caused by Normal Variations in Background Radiation.Supply Board replaced.W/930507 Ltr ML20044B6161993-02-25025 February 1993 LER 93-002-00:on 930126,Unit 1 Manual Scram Due to a SRV Being Stuck Open Due to Duct Tape Being Over Actuators Air Valve Manifold Exhaust Port.Maint Procedures That Involve Cleanliness reviewed.W/930225 Ltr ML20024G9771991-05-10010 May 1991 LER 91-005-00:on 910410,determined That Tech Spec Required Surveillance of Suppression Chamber Oxygen Sampling Missed. Caused by Inadequate Review of Tech Spec Change.Drywell & Suppression Chamber Checked for oxygen.W/910510 Ltr ML20044A3851990-06-25025 June 1990 LER 90-008-00:on 900525,Tech Spec Hourly Fire Watch Missed Due to Miscommunications Between Security Personnel & Radiation Protection Personnel.Fire Watch re-established & Memo issued.W/900625 Ltr ML20043F1721990-06-0505 June 1990 LER 90-009-00:on 900510,RWCU Outboard Suction Isolation Valve 2G33-F004 Auto Closed Which Tripped RWCU Pump B. Caused by Procedure Deficiency.Procedure LTS-500-209 Will Be revised.W/900605 Ltr ML20043F1281990-06-0101 June 1990 LER 90-009-00:on 900511,apparent Ruptured Diaphragm Found on Pressure Differential Switch in RCIC Steam Line.Caused by Torn Diaphragm Inside Switch.Replacement Switch Installed, Calibr & Functionally Tested satisfactorily.W/900608 Ltr ML20043B5681990-05-23023 May 1990 LER 89-027-01:on 891113,primary Containment Isolation Sys Group 1 Isolation Occurred During Surveillance Testing. Caused by Burnt Out Window Light Bulbs on Alarm Window. Light Bulbs Replaced & Jumpers installed.W/900523 Ltr ML20043A7721990-05-18018 May 1990 LER 90-007-00:on 900421,reactor Protection Sys Bus a Transfer & Reactor Recirculation Hydraulic Power Unit a Inboard Isolation Valves Closed,Causing Partial Group II isolation.Out-of-svc Procedure revised.W/900518 Ltr ML20043D0591990-05-18018 May 1990 LER 90-008-00:on 900502,ESF Actuation of Control Room B Emergency Ctk Ventilation Makeup Fan Occurred.Caused by Procedure deficiency.LTS-800-205 & Similar Procedures Will Be revised.W/900601 Ltr ML20042H0211990-05-10010 May 1990 LER 90-006-00:on 900412,loop a Primary Containment Chilled Water Sys Inboard Isolation Valves & Reactor Bldg Closed Cooling Water Sys Inboard Isolation Valve Went Closed.Caused by Inadequate Procedure.Procedures revised.W/900510 Ltr ML20042F9001990-05-0404 May 1990 LER 90-005-00:on 900411,experienced Loss of Dc Power to Portion of Div I Primary Containment Isolation Sys Logic Which Resulted in Isolation Signal & Actuation.Caused by Failure to Update Drawings & procedures.W/900504 Ltr ML20042F1941990-04-30030 April 1990 LER 89-025-01:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Door Containing Undervoltage Relays Closed.Caused by Misalignment of Door.Door Repaired. W/900430 Ltr ML20012D5341990-03-16016 March 1990 LER 90-003-01:on 900201,RCIC Isolation Signal Occurred During Warmup.Caused by Spurious High Steam Flow Signal.Rcic Sys Piping Integrity Verified & Isolation Logic Reset.W/ 900316 Ltr ML20012D5371990-03-16016 March 1990 LER 90-002-01:on 900129,oil in Diesel Generator Governor 1A Found to Be Low & Could Not Be Seen in Sight Glass.Caused by Slow Leak from Compensation Needle Valve Plug.Proper Amount of Oil Added & Operability Test performed.W/900316 Ltr ML20012C4931990-03-15015 March 1990 LER 90-004-00:on 900213,control Room B HVAC Intake Radiation Monitor Lost Power Causing auto-start of Emergency make-up Train B.Caused by Blown Fuses.Fuses Replaced.Logic Revs for Radiation Monitors Will Be installed.W/900315 Ltr ML20012B6501990-03-0909 March 1990 LER 90-002-00:on 900209,Operating Surveillance LOS-TG-W1 Determined to Have Exceeded Required Testing Interval,Per Tech Spec 3/4.7.10.Caused by Personnel Error.Personnel Counseled & Ref Procedures Will Be revised.W/900309 Ltr ML20012B5521990-03-0808 March 1990 LER 90-001-00:on 900206,full Reactor Scram Occurred During Instrument Surveillance Testing.Caused by Actuation of APRM E Trip Circuitry.Shutdown Margin Revised & Caution Card Placed on Control Room Bench board.W/900308 Ltr ML20011F8251990-03-0202 March 1990 LER 90-003-00:on 900201,RCIC Received Div 2 Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal Generated When Steam/Water Mixture Admitted to RCIC Steam Line.Isolation Logic reset.W/900302 Ltr ML20011F5551990-02-28028 February 1990 LER 90-002-00:on 900129,after Filling Diesel Generator 1A Governor W/Oil,Generator Started & Declared Inoperable. Caused by Slow Leak Coming from Compensation Needle Valve Plug.Oil Added & Plug Washer replaced.W/900228 Ltr ML20006F5951990-02-21021 February 1990 LER 90-001-00:on 900122,RWCU Sys Received Div 1 Leakage Detection Ambient Temp High Isolation Signal,Causing Trips of RWCU Pumps a & C.Caused by Broken Thermocouple Input Lead.Lead Wire Reconnected & Isolation reset.W/900221 Ltr ML20011F4921990-02-16016 February 1990 LER 89-013-01:on 890907,Group I Isolation Received During Performance of Instrument Surveillance LIS-MS-401.Caused by Depressurization of Main Steam Line Low Pressure Switch. Surveillance Revised to Split Into Two parts.W/900216 Ltr ML20006E4501990-02-15015 February 1990 LER 89-010-01:on 890715 & 17,voltage Oscillations Noted on Div II Battery Charger,Resulting in Inoperability of HPCS Sys.Caused by Failure of Charger in High Voltage Shutdown Relay.Charger Energized & Relay replaced.W/900215 Ltr ML20006E4451990-02-14014 February 1990 LER 89-009-01:on 890619,diaphragm Leak Discovered in RCIC Steam Line High Flow Isolation Switch.Caused by 1 & 1/2-inch Tear in Diaphragm.Pressure Differential Switch Replaced & Calibr.Reported Per NRC Bulletin 86-002.W/900214 Ltr ML20006E3981990-02-14014 February 1990 LER 89-008-01:on 890228,reactor Vessel Low Water Level 2 Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.Channel Placed in Tripped Condition & All Static-O-Ring Pressure Switches to Be replaced.W/900214 Ltr ML20006E3951990-02-14014 February 1990 LER 89-010-01:on 890303,automatic Depressurization Sys Permissive Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.All Static-O-Ring Reactor Vessel Level Switches Will Be replaced.W/900214 Ltr ML19354D8361990-01-15015 January 1990 LER 89-018-00:on 891216,plant 250-volt Battery & RCIC Sys Declared Inoperable Due to Low Battery Electrolyte Temps. Caused by Failure of Div I Switchgear Heat Removal Sys Damper Actuators.Air Intake Dampers closed.W/900115 Ltr ML20042D3921990-01-0404 January 1990 LER 89-011-01:on 890826,spurious Reactor Protection Sys Actuation Occurred.Definite Cause of Trip Not Determined. Brief Disturbance in Reactor Protection Sys Allowed Some Contactors to Trip.Procedure revised.W/900104 Ltr ML20005E2741989-12-22022 December 1989 LER 89-028-00:on 891204,RHR Shutdown Cooling Suction Header Outboard Isolation Valve Automatically Isolated.Caused by Miscommunication Between Technician & Station Operator.Task Force Developed to Review event.W/891222 Ltr ML19351A6301989-12-15015 December 1989 LER 89-006-01:on 890214,reactor Vessel Low Water Level 3 Switch Setpoint Found Out of Tolerance.Caused by Setpoint Drift.Level Switch to Be Replaced by Analog Trip Sys During First Quarter 1990.W/891215 Ltr ML20011D1341989-12-14014 December 1989 LER 89-017-00:on 891117,flow Switch FS-2E22-N006 Found W/ Setpoint Out of Tolerance Above Reject Limit.Caused by Setpoint Drift.Work Request Written to Replace Flow Switch. W/891214 Ltr ML19351A6751989-12-12012 December 1989 LER 89-027-00:on 891113,primary Containment Isolation Sys Group I Isolation Occurred While Performing Instrument Surveillance.Caused by Loss of Power to Leak Detection Sys Logic.Isolation reset.W/891213 Ltr ML19332F0081989-12-0808 December 1989 LER 89-016-00:on 891109,RWCU Isolation Occurred While Instrument Surveillance on Ventilation Differential Temp Isolation Functional Test in Progress.Caused by Faulty Thermocouple.Thermocouple repaired.W/891208 Ltr ML20005D6621989-12-0606 December 1989 LER 89-026-00:on 891106,inadvertent Primary Containment Isolation Actuation Occurred While Clearing out-of-svc. Caused by Inadequate Logic Setup During Mod Installation. Trip Status & Output Switches repositioned.W/891206 Ltr ML19332F2431989-12-0101 December 1989 LER 89-025-00:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Equipment Operator Closed Door Containing Relays.Caused by Misalignment of Door.Isolations Reset,Bus Energized & Circuit Logic tested.W/891201 Ltr ML19332E6581989-11-29029 November 1989 LER 89-015-00:on 891030,shift Control Room Engineer Noted That Quarterly Standby Liquid Control Operating Surveillance LOS-SC-Q1 Was Past Critical Date.Caused by Clerical Data Entry Error.Missed Surveillance performed.W/891129 Ltr ML19332D5181989-11-22022 November 1989 LER 89-018-01:on 890515,RCIC Received Div I & Div II Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal When Steam Added to RCIC Steam Line. Special Test Initiated.Isolation Logic reset.W/891122 Ltr ML19327C2601989-11-17017 November 1989 LER 89-014-00:on 891020,primary Containment Isolation Sys Group 4 Isolation Occurred Causing Isolation Dampers to Close.Caused by Opening of Div 2 125-volt Dc Breaker.Power Supply replaced.W/891117 Ltr ML19325F3411989-11-13013 November 1989 LER 89-024-00:on 891013 & 30,unsealed Openings in Main Control Room Floor & Main Control Room West Wall Discovered. Caused by Wide Gap Between Structural Beam & Cable Tray. Openings Sealed & Fire Watch established.W/891113 Ltr ML19324C1751989-11-0808 November 1989 LER 89-012-01:on 890309,diaphragm Leak Found in Pressure Differential Switch 1E31-N013BB.Caused by Tear Found in Diaphragm.Replacement Switch Installed,Calibr & Functionally Tested satisfactorily.W/891108 Ltr ML20024E9121983-08-26026 August 1983 LER 83-093/03L-0:on 830801,discovered full-in Indication on Core Display for Control Rod 34-47 Inoperable.Caused by Failed Switching Transistor on Data Memory Board 19.Data Memory Board replaced.W/830826 Ltr ML20024B8381983-07-0505 July 1983 LER 83-060/03L-0:on 830606,following Turbine Trip & Scram Due to High Vibration on Main Turbine,Reactor Recirculation Breaker 4B Closed.Cause Undetermined.Auxiliary Contacts cleaned.W/830705 Ltr ML20024B0721983-06-16016 June 1983 Updated LER 83-012/03X-1:on 830210,w/reactor in Cold Shutdown,Setpoints for Switches 1E31-N612A/B Found Above Tech Spec Limits.Cause Unknown.Switches calibr.W/830616 Ltr ML20024A6961983-06-14014 June 1983 LER 83-051/03L-0:on 830516,reactor Protection Sys Trip Channel H2 Limit Switch Failed to Operate Properly.Cause Unknown.Limit Switch readjusted.W/830614 Ltr 1993-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,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 ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 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 ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML20199E4601998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for LaSalle County Station,Units 1 & 2.With ML20207C7371998-12-31031 December 1998 Annual Rept for LaSalle County Station for Jan 1998 Through Dec 1998 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20206N2261998-12-0909 December 1998 LER 98-S03-00:on 981116,protected Area Was Entered Without Current Authorization for Unescorted Access Due to Programmatic Deficiency Error.Changed Badge Control Process ML20197K0981998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for LaSalle County Station,Unts 1 & 2.With ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings 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 ML20195D3191998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for LaSalle County Station.With ML20154H6781998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 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 ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode 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 ML20151W0241998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for LaSalle County Station.With ML20237E2921998-08-21021 August 1998 Special Rept:On 980811,channel 5 of Lpms Became Inoperable. Caused by Channel Failed pre-amplifier Located Inside Primary Containment at Inboard Side of Electrical Penetration E-19.Initiated Repairs of Channel ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B4861998-07-31031 July 1998 Monthly Operating Repts for July 1998 for LaSalle County Nuclear Power Station Units 1 & 2 ML20236V7701998-07-31031 July 1998 Revised LaSalle Unit 1 Cycle 8 COLR & Reload Transient Analysis Results ML20236P8231998-07-14014 July 1998 Special Rept:From 980614-17,various Fire Rated Assemblies Were Inoperable for Period Greater than Seven Days.Caused by Test Equipment Being Routed Through Fire Doors.Established Fire Watches & on 980619 Assemblies Were Declared Operable ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20236P3611998-06-30030 June 1998 Monthly Operating Repts for June 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20249C4891998-06-22022 June 1998 Special Rept:On 980522,Fire Detection Zone 1-31 Was Noted out-of-service for More than 14 Days.Detection Sys Was Taken out-of-service on 980508 to Prevent False Alarms During Hot Work Activities.Sys Was Returned to Operable Status 980528 ML20248M3101998-05-31031 May 1998 Monthly Operating Repts for May 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20236V7771998-05-31031 May 1998 Rev 1 to 24A5180, Supplemental Reload Licensing Rept for LaSalle County Station Unit 1 Reload 7 Cycle 8 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20247M4491998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for LaSalle County Station ML20216F4941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for LaSalle County Station,Units 1 & 2 ML20217N6581998-03-30030 March 1998 Special Rept on Fire Detection,Deluge Sys & Fire Rated Assemblies During Period of 980303-25.Established Fire Watches Until Affected Equipment Is Returned to Operable Status ML20216D9511998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for LaSalle County Station,Units 1 & 2 ML20247M4631998-02-28028 February 1998 Rev Monthly Operating Rept for Feb 1998 for LaSalle County Station ML20203D7241998-02-20020 February 1998 Special Rept:On 980118,Fire Detection Zones 1-18 & 2-18 Taken out-of-svc to Prevent False Alarms During Hot Work Activities on Auxiliary Electric Equipment Room Ventilation Sys.Fire Watches Will Remain in Place ML20202G9851998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for LaSalle County Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr 1999-09-30
[Table view] |
Text
. 1 .
l : Commonwestth Edison LaSalle County Nuclear Station
* Rural Roate #1, Box 220 Marseillen, Illinois 61341 Telephons 815/357-6761 ~
May 23, 1990 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory cannission Mall Station PI-137 Washington 0.C. 20555
Dear $1r:
Licensee Event Report 809-027-01 Docket #050-373 is being submitted to your office to superceed previously submitted Licensee Event Report #99-027 40.
This report is being submitted to clarify and update the event and corrective actions.
4O
&k G. J. Olederl h et Station Manager LaSalle County Station GJO/DRR/msh Enclosure ac: Nuclear Licensing Administrator NRC Resident inspector NR6 Region 111 Aeninistrator INP0 - Records Center l
90033o 1 b00hhhy3 nc 162a
= 'l! )
. l
.- LICENSEE EVEW1 REPORT (LER) facility Wme (1) Docket Natier (2) _ Pane (3)
L W ile County Station Unit 1 01 51 01 of 01 31 71 3 I of 0 6 i I
iltle (4) Primary Contalrunent Isolation During Surveillance Testing Due to turned Out Annitncletor Window Lloht Bulbs _
Event Date (5) LER Wustier (6) Reoort Date (7) Other Feel 11 ties involved (0)
Month Day Year Year /// Sequential /j/j
/ Revision Month Day Year Facility Wars Docket Natier(s)
//
01 51 01 01 01 1 1 01 1 11 1 11 3 el 9 el 9 01217 015 al3 91 0 of 51 01 01 01 l l l l TH15 REPOR1 15 $UBMli1ED PURSUANT TO THE REQUIREMENTS OF 10CFR OPEW M (Check one or more of the followino) (11)
MODE (0 20.405(c) 50.73(a)(2)(lv) 73.71(b) 0 20.402(b) ,_, .J._ _,
POWER ,_., 20.405(a)(1)(l) _., 50.36(c)(1) 50.73(a)(2)(v) _,. 73.71(c)
LEVEL 20.405(a)(1)(ll) 50.36(c)(2) _ 50.73(a)(2)(vil) _,
Other (Specify 0! 0! 0 110) ,. 20.405(a)(1)(lin) 50.73(a)(2)(l) ._ 50.73(a)(2)(vill)(A) in Abstract
// / / / /////// / / 20.405(a)(1)(lv) ._,. 50.73(a)(2)(ll) , 50.73(a)(2)(vill)(B) below and in
/ / // // / ,,,20.405(a)(1)(v) ._, 50.73(a)(2)(lli) 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR THis LER (12)
Name ,,,,_
TELEPHONE NUSER ;
AREA CODE Don Crowl. b ulatory Assurance. extension 2860 8 l 1 15 315111-l617161I COMPLETE OWE LINE FOR EACH CO@0NENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COPP0NENT t MiWUFAC- REPORTABLE CAUSEl SYSTEM C0ff0NENT MANUFAC- REPORTABLE TURER 10 WPRDS '
TURER TO WPRDS D I I I I l l l W l I l l l l l l l l l l l l l l l l l l l l SUPPLEMENTAL REPORT EXPECTED (14) Expected Month l Day l Year Submission I
~
US) l lyes (if ves. complete EDJUED SUBMISSION DATF) TlNO l ll ll ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)
On Noventner 13,1989 at 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> with Unit I defueled, a Primary Contalrunent Isolatlan Systun (PCIS) Group i 1 Isolation occurred while perfonning LaSalle Instroent Surveillance LIS-MS-1078, " Unit i Reactor Vessel Low Water Level 1 and Level 2 Isolation Instrunent Channels B and D Refuel Calibration." A full PCl$ Group 1 Isolation occurred because the other half of the isolation logic was tripped due to the loss of leak detection power from the AC electrical bus 135X and 135Y outage. No valve movement occurred because all the Main Steam system isolation valves were previously deenergized due to other scheduled refuel outage work.
The alarm windows were extinguished and the light bulbs for alarm window F504, 'CHAN Al/A2 MSly ISOL TRIP,"
were determined to be burnt out. This prevented the Unit I Wuclear Station Operator (WSO, licensed Reactor Operator) and the Instrenent Malntenance technician from detecting that half of the isolation logic was present due to AC electrical bus 135X being de-energized.
A review of the guidance for what an alarm window test requires will be perfonned.
This event is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(lv) due to the actuation of an l Engineered Safety Feature System.
LLCENSEE EVENT REPORT (LER) TEXT CONTINuAfl0N Fem Rev 2.Q, FACILliT IIRE (1) DOCKET NUSER (2) LER NUMER (6) Pm (3) -i Year /// Sequential //./l Revision !
ff
/N Neber ///#
Ihster -j
% 11e County station unit 1 0 1 5 1 0 1 0 1 0 1 31 11 3 e19 -
0_l 2 1 7 - 01 I of 2 0F 016 l' l TEXT Energy industry identification Syst a (Ells) codes are identified in the text as [XX] l PLANT AND SYSTEM IDENT!flCATION General Electric - tolling E ter Reactor EnergyIndustryidentificationSystem(Ells)codesareidentifiedinthetextas[XX). -l A. COND1110N PRIOR TO EVENT Unit (s): I Event Date: _11/13/09 Event Time: 1823 Hours Reactor Mode (s): Defueled Mode (s) ume: Defueled Power Levet(s): 1 B. DESCRIPTION OF EVENT On November 13, 1999 at 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> with Unit I defueled, a Primary Containment isolation System (PCl$,
PC) [JM) Group 1 Isolation occurred while perfoming LaSalle Instroent Surveillance LIS4-1078, " Unit 1 Reactor vessel Low Water Level 1 and Level 2 1 solation Instr uent channels B end 0 Refuel Calibration." Both Inboard and Outboard Main Stem Line Isolation valves (MSIV, MS) [$8) and Main Stem line drain valves were deenergized prior to the isolation due to planned refuel outage wort. - No valve l motion took place during this event. The PCl$ Group 1 isolation only resulted in relay and alarm actions. .
i-At'0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br /> on November 13, 1999 the 'A' channel callbration was coupleted in accordance with LaSalle
(
Instruent Surveillance LISM-101A, " Unit 1 Reactor Vessel Low Wter Level 1 and Level 21 solation instrument Channels A and C Refuel Calibration."
At 0725 hours0.00839 days <br />0.201 hours <br />0.0012 weeks <br />2.758625e-4 months <br /> "C" channel calibration was started in accordance with LIS-MS-107A.
' At 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> the Olvision 1 AC Electrical Distribution Buses 135X and 135Y (AP) [ED) were doenergized and taken out-of-service in accordance with LaSalle Administrative Procedure LAP-900-4, " Equipment Out-of-Service Procedure," for scheduled refuel outage work. The bus 135X and 135Y outage deenergized the Division I Leak Detection logic (LD/E31) [lJ). (Relays lE31A43A and IE31A43C doenergized.)
Relays IE31A43A and IE31A43C cause relays 1821H47A and 1821H47C to deenergize on loss of power, high area anblent tenperature or high differential tenperature signal. When relays 1821H47A and 1821H47C ,
deenergire, a channel Al and A2 MSIV isolation signal occurs. This occurred during the day shift and caused no consequence to testing the Division I logic per LIS-MS-107A. (Only half of the isolation logic was made up at this time.) Alarm window F504, "CHAN Al/A2 MSIV ISOL TRIP" should have been energized at this time.
At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> the calibration of the "C" channel per LIS-MS-107A was stopped for the shift to allow shlft turnovers (the exchange of day shift personnel with afternoon shift personnel) to take place.
At 1540. hours the calibration of the *C" channel was resumed per LIS-MS-107A.
p
' 1 tlCENSLE EVENT REPORT (LER) TEXT CONilNuAflal ' Fem new 2.0 FACit11Y NAPE (1) 00CKET NupeER (2) tiR 1RpeElt (6) P m (3) !
Year //j/ Sequential /// Revision .
V4 Notwe V4 Numer 1
.3 Lasalle County Station unit 1 0 I $ 101010131713 e19 - 01217 - 0I I 013 0F of 6 TEXT EnergyIndustryidentificationSystem(Ells)codesareidentifiedinthetextas[KK) l i
- t. DESCRIPil0N OF EVENT (Continued)
At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> the instrement mintenance (IM) personnel completed the calibration of the *C" channel per. i ilS-MS-107A. ,
i At 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> the calibration of *t" channel was started in accordance with LIS-MS-1078. The surveillance test was authorized by the Shift Engineer (SE, licensed Senior Reactor Operator), Shift Control Room Engineer (SCRE, licensed Senior Reactor Operator) and Unit 1 Nuclear. Station Operator (WSO,.
licensed Reactor Operator) prior to beginning the surveillance test. l At the beginning of the surveillance test, the conputer points (CX/C91) [LD) wre verlflod to indicate ,
as follows: ,
- 4. 09H 'LO LO RK WIR LYL OlV $1 -#-LO"
- b. C500, 'VERY L0 RK W1R LYL DIV 81 - N-Lo*
- c. C581, "RPS CH B1 INSTR GROSS Fall - AVAIL"
- d. C582, "RPS CH tl INSTR POER LOSS - AVAIL *
- e. C584, *RPS CH B2 INSTR GROSS f All - AVAIL"
- f. C585, 'RPS CH B2 INSTR POER LDSS - AVAIL" At the Control Room panel lH13-P603 the following alarus (AN) [18] wre verlflod reset or clear (slow j flash or extinguished): ;
- a. 8401,~*DIV 1 RK VESSEL WTR LVL 2 LO"
- b. 8412, "DIV 2 RX VESSEL WIR LVL 2 LO"
- c. 8405, *CHAN A1/B1 PRI CNMT PRESS Hl*
- d. 8409, "CHAN A2/B2 PRI CNMT PRESS Hl*
- e. A210, *CHAN A1/81 RX VESSEL WTR LYL 1 LO-LO-LO" I
Il At the Control Room panel 1H13-P601 alam E504, "CHAN B1/82 MSiv ISOL TRIP,* was verlflod reset or clear
! (slow flash or extinguished).
i L15-MS-1078 did not require the IM's to check the Aux 111ery Electric Room panels IH13-P622 anti IHl3423 l Main Ste m isolation Valve (MSIV, MS) solenoid valve status lights if the MSIV's were closed. The solenoid status lights are normally energized when no isolation signal is present.
The alarm windows were extinguished and the light bulbs for alarm windows f504, 'CHAN Al/A2 MSiv ISOL TRIP," and E504,
- CHM B1/82 MSIV ISOL TRIP,* on the Control Room panel IH13-P601 were later determined to be burnt out when testing was done, i
INen the test switch 1821-5208, *MSL ORN ISOL LOGIC,* was turned to test in accordance with Lis-MS-1078, I
a PCIS group 1 outboard Isolation occurred because the other half of the Isolation logic was trlpped due to loss of leak detection power from the AC electrical bus 135X and 135Y outage. No valve movement occurred because all the min Stem Line drain Isolation valves were previously deenergized (out-of-service) due to other scheduled refuel outage work. Both the Unit 1 NSO and the IM did not realize a Main Stem Line drain outboard isolation had occurred at this time because no valve motion took place.
i R j
i (LCENSEE EVENT REPORT (LtR) TEri CONTINu4 TION fom Rev 2.0 FACILITY NAME (1) 00CKE1 NueER (2) LER NHeER (6) Foot (3)
Year // Sequential y/ Revision
/
y//
/ Wunber i// thseer l LaSalle County Station unit 1 015101010131713 e19 - 01211 - 01 1 01 4 0F 01 6 l ;
TEXT Energy Industry identification System (Ells) codes are identified in the text as [KK)
- 8. DESCRIP110N OF EVENT (Continued)
The Instrwnent Melntenance personnel proceeded to the fleid and isolated 1821 4 4028 Division 11 reactor level transmitter and attached the test equipment to sinulate lowering reactor water vessel level. Imen the trip setpoint was reached, the Olvision 11 reactor water level trip unit opened contacts in the -
logic which deenergized the 1821H478 relay. The Olvision 11 reactor vessel water level trip indicator unit trip light and alam window A210, 'A1/81 LVL 2 LO LVL,' 111uminated. The alam window E504 did not illuminate at this point. The IM's stopped testing to investigate why the alam window E504, 'CHAN 81/82 MSly ISOL TRIP,* did not illuminate. The IM's requested the WSO to make an annunciator check and it was discovered that both alam window E504 and f 504 had no indication because the window Ilght bulbs were burnt out. At this point the IM's notified the IM foreman of the problem.
The IM personnel were requested to return reactor level transmitter 1821-W4028 to service and the Olvision 11 isolation was reset. The light bulbs were replaced for alam windows E504 and f 504 and the Operating Department requested the IM's to jisper the IE31A-K3A and IE31A43C relays for Division I to I allow testing of Division 11 logic to continue. This was done in accordance with LaSalle Adminlstrative Procedure LAP-240-6, "Tenporary System Change," and testing was conpleted without any further event, This event is being submitted pursuant to the requirements of 10CfR50.73(a)(2)(lv) due to the actuation of an Engineered Safety feature System.
C. APPARENT CAUSE OF EVENT An alann window F504, 'CHAN A1/A2 MSlY ISOL TRIP" had no indication because the window light bulbs were l
burnt out, which caused both the Unit 1 W50 and the IM to proceed with Lis-MS-1078 believing that no other isolation signal was present at this time. When the test switch 1821-5208, 'MSL DRN ISOL LOGIC
- l was turned to test in accordance with Lis-MS-1078, a Main Steam Line drain valve outboard PC15 group 1 isolation occurred.
When AC electrical bus 13SX was deenergized for planned outage work, a Division i PCl$ Group 1 Isolation
( signal resulted (Only half of the isolation logic was made up at this time.) due to the loss of power to the Leak Detection system logic which inputs to the PCls logic. This was done during the day shift i
(0700-1500 hours). After shift change the afternoon shift (1500-2300 hours) Unit I W50 checked the Main i- Control Room panel alams per LaSalle Operating Surveillance LOS-AA-51, 'Shiftly Surveillance,' and did not notice any extinguished alann window light bulbs. The Unit 1 W50 desunded an alann sisenary to print out on the Sequential Event Recorder typer (alann typer, AN) [1Q). A detailed review of the printout wasn't perfonned due to the work load during the shift and the nisnerous amount of 41anns Ilsted on the typer. Many alanns were caused from the amount of work requiring systems to be in an off-nonnal condition during a refueling outage.
The LaSalle Instrument Surveillance procedure did not require verification of the alanns printed out by the Sequential Event Recorder sisunary. This procedure also did not require the IM to verify the MSiv solenoid status lights energized in the Aux 111ery Electric Room if the MSIV's are closed. The MSIV's were closed due to planned refuel outage work and were deenergized to allow work to continue. Checking the alann sunnary printout may have allowed the W50 or IM to identify that an isolation signal was present. Checking the solenoid status lights for the MSIV's would not have helped in this event because the MStV's wers out of service and the solenoids deenergized to support planned outage work.
L ;
LICENSEE EVLW1 REPORT (lik) TEXT COWilWuA110N Fors nev 2,0 l FACILITY NAME (1) DOCKET WupeER (2) LER Nipt u (6) Paet D) ,
Year /// Sequential /,/,/, Revision !
fff
/// Weber W/ Weber Lasalle County station unit 1 0 1 5 1 0 1 0 1 0 1 31 71 3 sIg - 01211 - 01 1 015 0F 016 IEKI Energy Industry identification System (Ells) codes are identified in the ted as [XX) i C. APPARLW1 CAUSE OF EVENT (Continued)
?
When AC electrical bus 135X was deenergized the Unit 1 W50 on the afternoon shift did not realize that power was also lost to the Olvision 1 Leak Detection system which inputs to the PCl$ system to provide Isolations. Normally the W50 would be aware of the condition of the system by the Indication of Control Room 41ams. There are no specific procedures or lists (outside design drawings) which identify every effect a bus outa;pe has.
The SCRE who prepared and reviewed the AC electrical bus 135X and 135Y outage knew that the valves associated with the PC15 Group 1 Isolation logic were all out of service closed or in their isolated position. The $CRE felt that it would not be a concern during subsequent testing that would cause an isolation because no actual valve movement would take place, only relay actuation. The SCRE used LaSalle Energency Plan impismenting procedure LZP-13101, ' Notifications,' as a reference for making ;
this interpretation. This evaluation was not conewnicated to afternoon shift personnel. ;
D. SAftTY ANALYSl$ OF EVEW1 Bus outages are performed for modification work during planned unit outages. A loss of power to the
The safety significance of this event is minimal since the unit was cefueled and the valves that would have Isolated were already in the closed position due to planned outage work.
E. CORRFCilVE AC110ers At 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> the IM personnel were requested to return reactor level transmitter 1821 4 4028 to service and the Olvision 11 isolation was reset.
The light bulbs were replaced for alarm windows E504, 'CHAN 81/82 MSiv 150L TRIP,' and F504, 'CHAN A1/A2 ,
M$1V 150L TRIP."
1 On Novsaber 14,1989 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> the IM's installed jupers in accordance with LaSalle Administrative Procedure LAP 2404, 'isaporary System Change,' (TSC 1-983 -09) to prevent Malp Steam isolation Valve (MSly) Group 1 PCl$ isolation from occurring while a half isolation signal is present due to AC electrical bus 135K/Y outage. This was done to allow testing of Olvision 11 logic to continue.
At 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on November 14,1999, LIS-MS-1018 was coupleted satisfactorily without any further event.
The operating department has reviewed the LaSalle Operating Surveillance procedure LOS-AA-51, 'Shiftly Surveillance" and revised it to provide more guidance on what an alarm window test requires, such as checking each window to determine if both bulb:, are working properly when tested. Action item Record (AIR) 313-200-89-11201 has been completed.
The LaSalle Adninistative Procedure (AP-1600-2, ' Conduct of Operations" has been revised to require a check of the status of relays (when appilcable) on panels 1(2)H13-P609 and P611, prior to the performance of the surveillances or test that will cause a half scram or half isolations.
' thCENSEt EVENT REPopi (t1R) itti q EilWuAT10W . f ore Rev 2.0 fACILlif WAE (1) 00CKLI NU SER (2) Ltt WHSER (6) Pone (3)
//,/, Seqcentlet Revision
f fff
/T/ #weer /// #weer Wile County Station Unit 1 0 l 5 1 0 1 0 1 0 1 31 71 3 _8 1 9 - 01217 - 0l 1 01 6 0F 016 l .
TEKI Energy industry identification $ystem (Elis) codes are identified in the text as [KK)
E. CORRECTIVE Acil0WS (Continoed) f A review will be cogleted to detemine if dividers will be installed to divide the two annunciator light bulbs (or other potential igrovements) to allow the operating shift personnel to easily detemine when one of the two bulbs are burnt out. Action Itee Record (AIR) 373-200-89-11205 will track this corrective action.
A review of Ll5-4tS-107A(207A) and 1078(2078) has been cagleted to insure procedural steps are provided to verify both 41ers windows (504 and F504 are verlfled deenergized prior to testing. Also a review was vione to determine if in addition to the alars check it would be necessary to verify the M51V solenold .
status lights in the Auxillary Electric Equipment room. Because of the additional guidance provided to I operating shif t personnel in the performnce of alars status checks and the revision to (AP-1600-2, it was determined that this would increase the rellability of the annunciators and this check would not be necessary.
All alarm windows for both Unit I and 2 main Contral Room have been check < $ to verify both Ilght bulbs in each window are working properly.
AC electrical bus outage procedures will be developed ts anist the operating personnel in identifying potential problems which will arise due to de-energizing c1 ult,pment or logic system powsr supplies. AIR 373-200 4 9-11202 will track these procedures.
The training department has reviewed this event and has developed additional tralning to insure proper I turnover information that could effect Engineered Safety featured system actuation reportability is performed. AIR 373-200-89-11203 has been cagleted.
A General Information Notification (GIN) has been developed and a review this event with operating, l mintenance and technical staff personnel saphasizing the importance of verifying or reverifying the required inlilal conditions just prior to performing a test or surveillance to prevent inadvertent Engineered Safety featured System actuation has been conpleted. AIR 373-200-89-11204 has been ccupleted.
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F. PREVIOUS EVENTS LER Wunber iltle l
373/84 4 49-00 Secondary Containment isolation During Testing 373/84-074-00 Reactor Water cleanup Isolation 373/87-009-00 Group tv Isolation During Surveillance Test Due to Instrument Nintenance Procedure inadequacy 373/87-030-00 Reactor Scram While Shutdown During Survelliance Due to Comunication Error 374/88-017 4 0 Reactor Water Cleanup Isolation During Modification lest Due to inadequate Reset 374/89-003-01 Engineered Safety feature Actuation During Performnce of Instrument Nintenance functional Tests Due to Personnel Error l 374/89 4 13-00 Primary Contantenent isolation During Instrwnent Surveillance Testing of Lis-4ts-401 G. COMPONENT fAlLURE DATA Not appilcable.
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