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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
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.... 17 LaSalle County Nuclear Station -
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v' g . Rural Route #1,61341 Box 220 -
$ Marseilles,I!!inois p;< - Telephone 815/357 6761 i
June 25, 1990 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory <ccamiission Mail Station Pl-137 Washington, D.C. 20555 .
j
Dear Sir:
1 l Licensee Event Report 990-000-00, Docket 9050-373 is being L submitted to your office in accordance with 10CFR50.73 (a)(2)(i).
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M b ) 7 G. J. Diederic [h Station Manager LaSalle County Station E GJD/DAC/1s 1 Enclosure i
xc: Nuclear. Licensing Administrator NRC Resident Inspector NRC Region III Administrator IMPO - Records Center L
9006290001 900625 g, PDR ADOCK 03000373 V s PDC ,
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. i LIC8 mat EVENT AkPORT (tit) Fem tev 2.0 Facility usme (1) Decket thaber (2) Penn (3) mile e- -tv statlan unit i , el 51 of of of 31 71 3 1 of e 5 litle (4) ysad techalcal lagciflamilan thgriv Fim Match the to MI' -itatlans
, inset hate (1) -
LEl - ^ - (6) ; bate (7) Other Facilities ineolved (8)
Month Day Yeer Veer j/g seguential /g Revislen Month f
Day Year Fati1Itv "-- 7 T- d at " " ( s )
W/ /Y/ l tasalle unit 2 of 51 of ol 01 31 71 4
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of5 21 5 el o el o oIoIe o1e oI6 21 5 el o el51elelel l I )
TMil REPORT 15 $WRITTED PUR$uRNT TO THE IIEqulRE7ENTS OF 10CFR OPEMTING 1 (Chd one er more of the followina) (11) '
OI 30.402(b) _,,,, 20.406(c) ,_ 50.73(a)(2)(lv) 73.71(b) l ptRet ,_,. 20.405(a)(1)(l) ,,,,, 50.36(c)(1) _,,,, 50.73(a)(2)(v) _ 73.71(c)
LEVEL 30.406(a)(1)(ll) W.36(c)(2) ,, 50.73(a)(2)(vil) ,,,,,
other (specify 1 !0 (10) o ,_ 20.406(a)(1)(lll) _L, 50.73(a)(2)(1) ,, W.73(a)(2)(vill)(A) in Abstract
// // / / ,,,_, 20.405(a)(1)(lv) ,_,,, 50.73(a)(2)(ll) 50.73(a)(2)(vill)(c) below and in f/f f/ f f/ /f/f/ ff
/ 20.405(a)(1)(v) _,,_ 50.73(a)(2)(lit) ,,,,_ 50.73(a)(2)(a) Teat) ]
LICEN5EE CGriACT FOR THIS LER (12) l l lease iLLEPHONE IM GER AREA CODE Den A. Crevl. HPES Coordinator. estension 2460 8 1 1 15 31 51 71 -l 61 71 61 1 l CWFLLTE ONE LINE FOR EACH C090 MENT FAILURE DESCRIRED IN THIS REPORT (13)
$YSTEM COWOMENT MNUFAC-l
! CAUSE REPORTABLE CAUSE SYSTEM COWOMENT MANUFAC- REPORTABLE /jfe//
TUICR TO IIPWS TUI0R TO IrWE T l
i A 1 N 11 '
I l 1 l 'f '
$UPPLEMENTAL REPORT EXPECTED (14) Espected Month l Bay l tear submission
~~
lves (if ves. cam >lete EXPECTED $WMI5510N DATE) Il ND l l i ABSTRACT (Limit to 1400 spaces, i.e, approaleAt 9 fifteen single-space typewritten lines) (16) l On May 25, 1990 with unit 1 in the Run en es 100E power and Unit 2 in Md Shutdown with the Reactor vessel
( reassembly in progress, the Reactor building Refuel f;oor hourly fire rgM was not perfonned at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> I cs required by Technical Specifications (due to fire detection being inoperable). The missed fire watch
( occurred due to several causes which were as follow; (1) a miscommunication between the Security personnel who needed to perfom the fire watch and the Radiation Protection Personnel who needed to authorize Security to perform the fire wtch in a high radiation area, (2) due to shift turnover taking place at the time of this event, no personnel were located on the Refuel Floor to allow Security to phone them for verification that no sites were present and (3) inadequate radiation control practices lead to Security not belne able to perform the ?lre watch due to the spread of contamination. The fire watch was re established at 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on May it, .990, I hour and 27 minutes following the previous fire watch and all responsible department personnel will be tallgated on this event. The safety significance of this event is alnleal because no work was lh progress prior to this event or during this event which would have Increased the potential for a fire to occur on the Refuel Floor, enty 27 minutes had elapsed since the fire watch was required to be perfonned.
This event is being sutanitted pursuant to the requirements of 10CRFR50.73(a)(2)(l) due to a deviation from l plant Technical Specifications.
l
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I E l a PMILITY WE (l) MTWWA(2) Las _ - 141 _ m as 0 11 Tear O/ Sequential yf Asvisten TY M7 that i tasalle emustr statlan unitL o i s i o 1 e i o I al 71 3 gio - oIeie - o Io el 2 er al l l Text tory insustry lesetithetten system (tils) codes are identified in the test as (xx] j
, pu wT Am $YsteM !OtNTiflCATim eeneral Electric - telling %ter Reactor Energ ladustry identification System ($115) codes are identified in the test as [xx].
A. COWITION PRIOR TO EVENT unit (s): jfL twent Date $/25/g0 twent flam: 2300 Hours I heactorMode(s): jf,L Powr tevel(s): Jgg Mode (s) names hun / Cold theidsun
- 8. DESCRIPTION OF AVENT on May 25,1990 with unit i in the Run made at 1005 power and unit 2 in Cold Sheldown, security uns assigned the task of perfonning hourly fire watches on the refuel floor. The fire watches teve required by LaSalle Techalcal Specification 3.3.7.g, because the nonna) fire detection (FP) [lC) system toes disabled to prevent nuisance or falso fire alems due to high radiation conditions which result fram moving the reactor vessel camponents (W) [AD] for reassembly. At 2246 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.54603e-4 months <br /> the last fire watch was perfomed for May 25, 1990, the subsequent fire watch was not perfomed untl10013 hours on May 26, 1990, therefore I hour and 27 minutes had elapsed since a fire watch us perforund.
Security was perfoming the required fire watcles by calling the refuel floor and questioning personnel in the area about whether or not they had seen any fires. This method was utilized to perfom the fire watch because the refuel floor area and the access to the refuel floor had became contelnated. The spread of centmination us caused by ventilation air flow through the refuel floor plugs. e During the reactor vessel reassembly, 2 Radiation Protection Technicians (RPT's) were assigned to the c refuel floor to control and monitor activities and one was assigned to the desk (located at the refuel >
floor access point on the Reactor buildint 832' elevation) to control the Radiation Work Pomit and '
assign digital ensleetry. No one was present on the refuel floor during this event due to shift crew turnovers which were taking place.
I At 2246 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.54603e-4 months <br />, the last person to leave the refuel floor was logged out and the security guard (Rever N) posted at the refuel floor access point questioned this person as to whether or not any fires were noted. This was the last 41se a fire watch was perfomed and documented for May 25, 1990.
At 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br /> the security guard (Rover N) was contacted by the fire watch security guard. Rever N notified the fire watch security guard that the match tours were satisfactorily completed.
At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, both Operating and Maintenance department turnovers took place.
.._____-_-_-.----.-.--.-.-.,-a..._-
te evert aspent (tnan Tant certa-flou tr- nov 2.0 i e
5 pMILITY WE (1) 001E11 apWER (2) LEA ^^ - = (6)
_ Paan (3) l
- Voer seguential '
nevision l f,y/,
yft
+ 11. * ^ tsatlan udt i e i s i e i e i e 1 al 11 3 eIe - oIoIe - o Io el 3 or el5 i TEXT Energ lutustry lesotification Systa (Ells) codes are identified in the tent as [KX]
O. OtlCRIPfleu 0F IVONT (Continued)
At apprealantely 2360 hours0.0273 days <br />0.656 hours <br />0.0039 weeks <br />8.9798e-4 months <br />, the security guard posted at the refuel floor access point had nottfled his supervisor that everyone had left the refuel floor. The security guard was then Instructed by his supervisor to perfom his teactoi tullding tour and call the refuel floor when it can tlan to deement the fire watch. ,
I At the end of the security guard's tour, he called the refuel floor to verify no fires wre taking I place. No answr was received because no one was present on the refuel floor due to shift turnovers. !
i At 2333 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.877065e-4 months <br /> the security guard (Rover H ) was apeln contacted by the fire watch security guard. Rever l N again notified the fire watch security guard that the watch tours wre cogleted.
i At approalsetely 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br /> on May 25, 1990 the security guard called the security supervisor to notify i I
him that no one was on the refuel floor to facilitate completing the fire watch. At this ties the
- security supervisor called the Radiation Protection (RP) supervisor. l
- I in an investigation laterview with the RP supervisor, he had Indicated that Security had questioned him ;
as to where t:ee RP1's were and that no mention was made to the RP supervisor as to the concern for
]
perfoming the hourly fire watch. The MP supervisor did not ask security why they wre asking for the ,
IFT's locations. Mditional interviews wre held with security. The security supervisor who contacted ;
the AP supervlur sentioned he had Indicated to the RP supervisor that no one was positioned at the desk on the Reactor tullding 832 elevation for access to the refuel floor. During the laterview the Security i i
supervisor had sentioned that the AP supervisor responded by saying that he had people on their way up there (Reactor tullding 832 elevation, at access point to the refuel floor). The Security supervisor said he had told the RP supervisor that he needed to perfom the fire watch. The conclusion of the ,
Intervlows indicated a misconnunication between the RP supervisor and the Security supervisor.
i At 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on May 26, 1990, an entry was made onto the refuel floor and the fire watch re estabilshed '
using personnel working in the area on the Unit 2 Reactor vessel reassembly.
C. - APPARENT CAUSE Of EVENT f I ,
Poor ceumunication practices lead to the failure rf the radiation protection supervisor to reallae the need tc insure security had access to the refuel floor, it was not until ofter the event that security was infomed that they could do a visual floor inspection from the doorway of the refuel floor when no ons was present on the floor.
Poor canuunication practices also lead the fire watch security guard into believing the fire watch was completed at 2333 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.877065e-4 months <br /> and the fire watch security guar 11 logged the fire watch complete at this time.
On May 22,1990, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, inadequate radiation work practices lead to the loss of contamination control by the refuel floor doorway which prevented security from being able to perfom a doorway inspection of the refuel floor for fires, i
__ m ___.. .- -
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[
t sumart amant itsai tant conti==ttan Fem ano 2.s !
c* PMILITY INE (l) MCEEi lap M A (f) lea _ _ 16) Puma 0 l} [
Year 5eguential Apelslon :
fJ/
/
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%Ile e- tv statlan =lt 1 e 1 5 1 e i e i e 1 al 11 3 eio - o1eie - o Io el4 nF cl i !
TEXT Energ Industry idestification System (Elll) codes are identified in the test as [KR) j C. APPARENT CAUSE OF EvtNT (Continued)
Shift turnover for all personnel on the refuel floor occurred at the same time resultlne in no one belne I pewsont on the refuel floor to 411ew security to perfom the fire watch by ca111ag the refus) floor for verification that no fires wre occurring.
- 0. SAFETY An4LY515 0F EVtWT t
The design of the hefuel floor fire detection system does not allow for t%e system to remain operable during high background radiation conditions which result during reactor m sel assembly and l disassembly. This requires a fire watch to be estab11shed during these conditions as required by ,
LaSalle Technical Specifications. ;
t The fire detection system is nomally bypassed for areas in which wlding, grinding or other activity in y progress that actuates the system, in these situations a fire watch is estabilshed to provide for '
adequate detection and waming of fires which may result. The probability of a fire occurring durint
- this event was alnloal because no work was in progress at the time due to turnovers taking place and no work was in progress prior to this event Ithat would have required an increase in the capability to '
d detect fires.
E. C0ARECilVE ACTIONS A fire watch was re-established as soon as personnel entered the refuel floor to continue vessel reassembly work activities. Security personnel wre Instructed to continue perfoming the fire watch by calling the refuel floor and questioning personnel on the floor as to whether or not there were any fires, if no personnel were available on the floor, security was infomed that they could perfom the fire watch by opening the refuel floor door and perfo m a visual check of the floor from the doorway.
This was done to minimize dose and any potential for cont mination. The hourly fire watch was re-established at 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on May 26, 1990. This was I hour and 27 minutes after the previous fire watch.
The Security Administrator issued a security memorandum to Instruct security personnel to notify the Shift Engineer laundlately when a fire watch is unable to be perfomed. ,
A tellgate for both Security and Radiation Protection personnel on this event with emphasis placed on the Igoriance of good communication practices will be conducted. The tallgates will also include a discussion for Security to take compensatory measures during turnover periods. The coupletion of this i
! corrective action will be tracked by Action item Record (AIR) neber 313-200-90-04401.
1 A review of the feasibl11ty to set up a Refuel Floor camera, with a monitor located at the Refuel Floor i access point on the heector Building 832' elevation to allow security to monitor for fires and minimize dose and the potential for contamination will be performed. The coupletion of this corrective action <
will be tracked by AIR neber 373-200-90-04402.
)
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. .. _ ., _ _ _ ~_.. . __ _ _ - . _ _ _ -
-. - _ , - . .- - . . - - _ - . - . . - . - - - . . - . - . . - - ~ . _ - . - - -
s LT ~7 EURIK M (tsal TERT tmK'"" TIM Fare hv 2.0 '
?
4 FAtiLITY WE (1) SetRET 18508R (2) LER r _- - (6) pine Cl) !
Year Sequential / Revision
% 11e - ^_, statlan r 1 e i n i o 1 o I o I al 113 e1o - 0IoIe - oIo el 5 or el 5 i TEXT Energ ladustry identification Systa (Ell 5) codes are identified in the text as [XX) .
E. CORRECTIVE ACTieu5 (Continued)
A LaSalle A hinistrative Procedure will be developed, or a revision to the entsting procedures, to -
provies guidance as to who can perform a fire watch and what constitutes a fire watch. This procedure or revision will include guleance on transferring the fire watch responsibility between one work group to another. The cespletion of this corrective action will be tracked by AIR nueer 373-200 00-44403.
A revision to security post orders to provide guidance to lanediately notify the Shift Engineer when a i fire watch cannot be performed will be issued. The coupletion of this corrective action will be tracked ;
by AIR nueer 373-200-00-04404.
A review of procedures for the reactor vessel disasseely and reassaely to provide Instruction to insert that the refuel floor plugs are properly sealed will be conducted. This will force ventilation .
flow te erd the reactor well to prevent the potential for spreading containation during the movement of f reactor vessel components. The completion of this corrective action will be tracked by AIR numer 373-200-00-04405.
F. PIIEVIOUS EVENTS
( Ilone l, G. C090utNT FAILURE DATA Ilone I
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_ . , . _ . - . , - - - _ ,- - % '