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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D0261994-04-22022 April 1994 LER 94-002-00:on 940329,inadvertent Automatic Closure of Primary Containment Isolation Valves & ESF Actuations Occurred Due to Malfunctioning Handswitch.Caused by Weak Electrical Contact Spring.Handswitch replaced.W/940422 Ltr ML20046B4961993-07-30030 July 1993 LER 93-008-00:on 930627,MCR Annunciator Alarmed Indicating That Outside Atmosphere Reactor Encl (Re) Negative Differential Pressure Decayed Due to Failure of Normal Re Ventilation Fan Motor.Subj Fan replaced.W/930730 Ltr ML20046C3961993-07-30030 July 1993 LER 92-011-01:on 920605,discovered Potential Physical Electrical Separation Deficiency in Panel 10C790.Plant Electrical Maint I&C Technicians Received Training on Electrical Separation Requirements ML20046B5051993-07-30030 July 1993 LER 91-015-01:on 910912,HPCI Sys Discovered to Be in Degraded Condition When HPCI Turbine Steam Supply Valve Failed to Fully Open.Recommendations of EPRI Improved MOV Lubricant Program implemented.W/930730 Ltr ML20046B5001993-07-30030 July 1993 LER 93-008-00:on 930630,determined That TS SR on Fire Rated Assemblies Not Satisfied Due to Personnel Error During Procedure Preparation.Surveillance Test Procedure ST-7-022-922-0 Will Be revised.W/930730 Ltr ML20046A4431993-07-19019 July 1993 LER 93-007-00:on 930617,alarm Indicated TIP Sys Shear Valve Was Inoperable.Cause Interminate.Isolated Occurrence. W/930719 Ltr ML20045D3931993-06-21021 June 1993 LER 93-007-00:on 930521,primary Containment Isolation Valve Inoperable & TS Action Statement & SR Not Implemented in Required Time.Caused by Personnel Error.Ltr Issued to Personnel Emphasizing Requirement ML20044E7431993-05-20020 May 1993 LER 93-002-01:on 930124,discovered That EDG Inoperable Since 930119 Due to Improperly Connected Wires in Circuit Breaker. Wires Restored to Proper Position & Tested Satisfactorily. Procedural & Training Changes Also Implemented ML20044D1761993-05-0707 May 1993 LER 87-028-01:on 870610,hourly Fire Watch Required by TS 3.7.7 Not Performed Due to Personnel Error.Plant Security Organization Accepted Responsibility for Hourly Firewatch Patrol Required by Ts,Effective 930104 ML20044C9231993-05-0505 May 1993 LER 93-004-00:on 930405,primary Containment & Reactor Vessel Isolation Control Sys Actuation Occurred During Test of NSSSS-refueling Area Ventilation Exhaust Duct.Caused by Personnel Error.Technician counseled.W/930505 Ltr ML20024H0901991-05-10010 May 1991 LER 91-007-00:on 910410,handling of Control Rod Prohibited by Tech Spec Surveillance Requirements 4.9.6.3b.Caused by Inadequate Procedure.Maint Procedure Changed Deleting Provisions to Reposition Mechanical stop.W/910510 Ltr ML20024G6981991-04-22022 April 1991 LER 91-003-00:on 910324,inadvertent Actuation of Reactor Protection Sys Occurred.Caused by Personnel Error.Procedural Guidance Developed,Shift Training Bulletin Issued & Operator Requalification Training Module revised.W/910422 Ltr ML20029A8251991-02-27027 February 1991 LER 91-005-00:on 910130,pressure Differential Switch Restored Incorrectly,Causing Spurious Drywell Pressure Signal & ESF Actuation.Caused by Personnel Error.Personnel Counseled & Warning Labels added.W/910227 Ltr ML20029A7101991-02-22022 February 1991 LER 91-004-00:on 910123,determined That TS Section 3.3.7.5 Surveillance Requirements Not Satisfied for Fuel Zone Level & Neutron Flux Instrumentation.Caused by Misinterpretation of Ts.Calibr Procedures revised.W/910222 Ltr ML20028H7121991-01-22022 January 1991 LER 90-035-00:on 901224,14 Valves Associated W/Various Sys & Required to Perform Function of Isolating Primary Containment Determined Inoperable.Caused by Installation Error During Initial const.W/910122 Ltr ML20028H6791991-01-18018 January 1991 LER 91-002-00:on 910109,replacement Cassette Drive Unit to Replace Inoperable Seismic Monitoring Sys Not Received by 910109,rendering Sys Inoperable for More than 30 Days.Caused by Grit on Gear.Sys repaired.W/910118 Ltr ML20024F7361990-12-0707 December 1990 LER 90-025-00:on 901110,spurious LOCA Signal Resulted in ESF actuations.W/901207 Ltr ML20028G9221990-09-26026 September 1990 LER 90-017-00:on 900828,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Technician Inadvertently Shorting Power Supply During Installation of Test Jack.Blown Fuse replaced.W/900926 Ltr ML20044A9761990-07-12012 July 1990 LER 90-013-00:on 900611,dc Distribution Sys Identified to Have Inadequate Isolation Capability Between Class IE & non-Class IE Components.Cause of Event Under Investigation. Hourly Fire Watches Established Until 900626.W/900712 Ltr ML20043C5231990-06-0101 June 1990 LER 90-003-01:on 900208,HPCI Sys Isolation Valve Inadvertently Isolated During Surveillance Test.Caused by Both Channels of Isolation Logic Being in Tripped Condition at Same Time.Isolation of HPCI Sys reset.W/900601 Ltr ML20043C3211990-05-30030 May 1990 LER 90-012-00:on 900426,inoperability of RHR Sys Modes Occurred Due to Physical Separation Deficiencies.Caused by Drawing Deficiency Resulting in Installation Error During Original Const.Nonclass 1E Cable sleeved.W/900530 Ltr ML20043B1331990-05-21021 May 1990 LER 90-011-00:on 900420,discovered That Emergency Svc Water Pump B Discharge Check Valve Not Preventing Reverse Flow. Caused by Personnel Error in That Actuating Arm Incorrectly Assembled.Actuating Arm repositioned.W/900521 Ltr ML20043B1311990-05-18018 May 1990 LER 90-006-01:on 900223,determined That Capability to Activate Emergency Public Notification Sys Sirens from Counties Lost from 900112-0205.Caused by Disconnection of Phone Lines.Lines Reconnected for All counties.W/900518 Ltr ML20043A7651990-05-17017 May 1990 LER 90-008-00:on 900417,HPCI Sys Isolation & Inoperability Occurred Due to Failure of Differential Pressure Transmitter.Cause of Transmittal Failure Under Investigation.Transmitter Returned to mfg.W/900517 Ltr ML20043A6321990-05-15015 May 1990 LER 89-060-01:on 891212,standby Gas Treatment Sys Charcoal Filter Discovered in Degraded Condition W/Possible Bypass Leakage Paths.Similar Condition Discovered on 891218.Caused by Holes in Charcoal Filter assemblies.W/900515 Ltr ML20043A4261990-05-15015 May 1990 LER 90-010-00:on 900415,ESF Actuation Occurred Closing Three Containment Isolation Valves for Analyzers.Cause Unknown. Isolation Reset,Analyzers Returned to Svc & Voltmeter Not Being Used Pending Determination of cause.W/900515 Ltr ML20042G0521990-05-0404 May 1990 LER 90-009-00:on 900405,control Room Chlorine Isolation of Habitability Control Room Isolation Sys & ESF Initiated. Caused by Failure of B Toxic Gas Detector & False Signal from Untested Analyzer.Detector replaced.W/900504 Ltr ML20012C9361990-03-12012 March 1990 LER 90-005-00:on 900211,no Fire Watch Insps for Rooms 103, 114 & 117 on Elevation 177 Ft in Reactor Encl Performed by Personnel.Caused by Personnel Error.Person Involved Disciplined.Training Program improved.W/900312 Ltr ML20012C5541990-03-12012 March 1990 LER 90-004-00:on 900209,station Personnel Discovered That on 890708,22-s Reactor Power Transient Occurred in Which Reactor Thermal Power Changed by More than 15% of Rated Thermal Power in 1 H.Procedure revised.W/900312 Ltr ML20012C7071990-03-12012 March 1990 LER 90-003-00:on 900208,HPCI Sys Inboard Isolation Valve Inadvertently Isolated & Closed When One Channel of Isolation Logic Tripped.Caused by Degradation of Darlington Output Transistor.Isolation reset.W/900312 Ltr ML20011F7911990-02-26026 February 1990 LER 90-002-00:on 900125,identified That Main Control Room Ventilation Sys Outside Design Basis.Caused by Misapplication of Design Basis Assumptions.No Immediate Actions Taken as Existing Procedures adequate.W/900226 Ltr ML20006E4271990-02-0909 February 1990 LER 90-001-00:on 900122,discovered That Monthly Instrument Channel Functional Test for RCIC Steam Supply Pressure Low Missed.Caused by Deficiency in Computer Program Used to Schedule Tests.Computer Program revised.W/900209 Ltr ML20006E3451990-02-0808 February 1990 LER 90-003-00:on 900112,primary Containment & Reactor Vessel Isolation Control Sys Isolation Signals Initiated, Closing Inboard & Outboard Isolation Valves for Rwcu.Caused by Lifting Relief Valve.Opening Time reset.W/900208 Ltr ML20006E2851990-02-0707 February 1990 LER 90-002-00:on 900105,containment H2/O2 Analyzer Declared Inoperable During Containment Inerting.Caused by Reversed Tubing Connections in Installation of Analyzer Due to Mislabeling.Analyzer restored.W/900207 Ltr ML20006D5171990-02-0707 February 1990 LER 90-001-00:on 900108,Tech Spec Violation & Reactor Encl Ventilation Isolation Occurred.Caused by Personnel Error. Chief Operator Counseled on Importance of Communicating All Pertinent info.W/900207 Ltr ML20006A8801990-01-19019 January 1990 LER 89-015-00:on 891223 & 24,problem W/Reactor Protection Sys (Rps)/Uninterruptable Power Supply Static Inverter Caused Loss of Power to RPS Panel.Caused by Failure of Gate Drive Boost Card.Isolations reset.W/900119 Ltr ML20005F9441990-01-10010 January 1990 LER 89-060-00:on 891212,standby Gas Treatment Sys Charcoal Filter a Discovered to Be Degraded W/Possible Bypass Leakage Paths.On 891218,filter B Found W/Similar Condition.Caused by Failure of Spot Welds.Filters repaired.W/900110 Ltr ML20005E6841990-01-0303 January 1990 LER 89-059-00:on 891206,instrumentation & Controls Technician Inadvertently Grounded Test Jack,Resulting in Blown Fuse.Caused by Personnel Error.Fuse Replaced. Technicians counseled.W/900103 Ltr ML20042D1961989-12-29029 December 1989 LER 89-009-02:on 890820 & 0925,RCIC Sys Injections Into RCS Occurred During Startup Test.From 891023-26,three HPCI Sys Injections Into RCS Occurred During Test.Injections Anticipated.Startup Tests performed.W/891229 Ltr ML20005E3301989-12-29029 December 1989 LER 89-014-00:on 891202,unexpected Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred. Caused by Insufficient Guidance in General Plant Procedure. Appropriate Procedures Reviewed & revised.W/891229 Ltr ML20005E0961989-12-26026 December 1989 LER 89-058-00:on 891123,actuation of Group III Primary Containment & Reactor Vessel Isolation Control Sys Resulted in Automatic Isolation of Rwcu.Caused by Failure of Flow Summer Card.Card replaced.W/891226 Ltr ML20011D2291989-12-19019 December 1989 LER 89-057-00:on 891120,refuel Floor Secondary Containment Isolated on Low Flow Differential Pressure,Causing Initiation of Standby Gas Treatment Sys.Caused by Severe Storm.Normal Ventilation Restored to floor.W/891219 Ltr ML19332F8631989-12-13013 December 1989 LER 89-056-00:on 891119,unexpected Nuclear Steam Supply Shutoff Sys Group Iii,Div 4 Isolation Initiated ESF Actuation.Caused by Defective read-set Selector Switch. Switch repositioned.W/891213 Ltr ML19332F7761989-12-11011 December 1989 LER 89-013-00:on 891110,reactor Scram Occurred Following Main Turbine Trip,Causing Initiation Signals on HPCI & RCIC Sys Due to Spiking of Level Transformers.Caused by Design Error.Hpci Turbine secured.W/891211 Ltr ML19332F7751989-12-11011 December 1989 LER 89-012-00:on 891110,RWCU Sys Differential Flow Oscillations Observed While Placing RWCU 2A Filter/ Demineralizer Into Svc.Caused by Leakage in Reactor HX Tube Side Safety Relief Valve.Valve removed.W/891211 Ltr ML19332F2961989-11-29029 November 1989 LER 89-009-01:on 890820,eight RCIC Sys Injections Into RCS Occurred Under Purview of Facility start-up Test Program. Caused by Abnormal Plant Conditions Requiring Safety Sys Actuations.Rcic & HPCI Sys Tests completed.W/891129 Ltr ML19332D6331989-11-27027 November 1989 LER 89-011-00:on 891027,outboard Nuclear Steam Supply Shutoff Sys Isolation Valves Isolated.Caused by Personnel Error Due to Lack of Attention to Detail by Technicians. Event Discussed at All Hands meeting.W/891127 Ltr ML19332D6251989-11-27027 November 1989 LER 89-055-00:on 891025,reactor Protection Sys 1A Shunt Trip Breaker Tripped on Undervoltage,Causing Loss of Power to Distribution Panel 1AY160 & ESF Isolation.Caused by Relief Valve Failures.Isolations reset.W/891127 Ltr ML19332C1781989-11-17017 November 1989 LER 89-053-00:on 891022,control Room Personnel Manually Initiated Ventilation Sys Chlorine Isolation,Esf.Caused by High Vinyl Chloride Concentration in Outside Air Intake Plenum.Special Event Procedure implemented.W/891117 Ltr ML19332B9841989-11-15015 November 1989 LER 89-054-01:on 891025,discovered That Daily Channel Check Surveillance Requirement for Channel D High Level Trip Not Met.Caused by Procedural Deficiency Since Initial Plant Operation.Associated Log Procedures revised.W/891115 Ltr 1994-04-22
[Table view] Category:RO)
MONTHYEARML20029D0261994-04-22022 April 1994 LER 94-002-00:on 940329,inadvertent Automatic Closure of Primary Containment Isolation Valves & ESF Actuations Occurred Due to Malfunctioning Handswitch.Caused by Weak Electrical Contact Spring.Handswitch replaced.W/940422 Ltr ML20046B4961993-07-30030 July 1993 LER 93-008-00:on 930627,MCR Annunciator Alarmed Indicating That Outside Atmosphere Reactor Encl (Re) Negative Differential Pressure Decayed Due to Failure of Normal Re Ventilation Fan Motor.Subj Fan replaced.W/930730 Ltr ML20046C3961993-07-30030 July 1993 LER 92-011-01:on 920605,discovered Potential Physical Electrical Separation Deficiency in Panel 10C790.Plant Electrical Maint I&C Technicians Received Training on Electrical Separation Requirements ML20046B5051993-07-30030 July 1993 LER 91-015-01:on 910912,HPCI Sys Discovered to Be in Degraded Condition When HPCI Turbine Steam Supply Valve Failed to Fully Open.Recommendations of EPRI Improved MOV Lubricant Program implemented.W/930730 Ltr ML20046B5001993-07-30030 July 1993 LER 93-008-00:on 930630,determined That TS SR on Fire Rated Assemblies Not Satisfied Due to Personnel Error During Procedure Preparation.Surveillance Test Procedure ST-7-022-922-0 Will Be revised.W/930730 Ltr ML20046A4431993-07-19019 July 1993 LER 93-007-00:on 930617,alarm Indicated TIP Sys Shear Valve Was Inoperable.Cause Interminate.Isolated Occurrence. W/930719 Ltr ML20045D3931993-06-21021 June 1993 LER 93-007-00:on 930521,primary Containment Isolation Valve Inoperable & TS Action Statement & SR Not Implemented in Required Time.Caused by Personnel Error.Ltr Issued to Personnel Emphasizing Requirement ML20044E7431993-05-20020 May 1993 LER 93-002-01:on 930124,discovered That EDG Inoperable Since 930119 Due to Improperly Connected Wires in Circuit Breaker. Wires Restored to Proper Position & Tested Satisfactorily. Procedural & Training Changes Also Implemented ML20044D1761993-05-0707 May 1993 LER 87-028-01:on 870610,hourly Fire Watch Required by TS 3.7.7 Not Performed Due to Personnel Error.Plant Security Organization Accepted Responsibility for Hourly Firewatch Patrol Required by Ts,Effective 930104 ML20044C9231993-05-0505 May 1993 LER 93-004-00:on 930405,primary Containment & Reactor Vessel Isolation Control Sys Actuation Occurred During Test of NSSSS-refueling Area Ventilation Exhaust Duct.Caused by Personnel Error.Technician counseled.W/930505 Ltr ML20024H0901991-05-10010 May 1991 LER 91-007-00:on 910410,handling of Control Rod Prohibited by Tech Spec Surveillance Requirements 4.9.6.3b.Caused by Inadequate Procedure.Maint Procedure Changed Deleting Provisions to Reposition Mechanical stop.W/910510 Ltr ML20024G6981991-04-22022 April 1991 LER 91-003-00:on 910324,inadvertent Actuation of Reactor Protection Sys Occurred.Caused by Personnel Error.Procedural Guidance Developed,Shift Training Bulletin Issued & Operator Requalification Training Module revised.W/910422 Ltr ML20029A8251991-02-27027 February 1991 LER 91-005-00:on 910130,pressure Differential Switch Restored Incorrectly,Causing Spurious Drywell Pressure Signal & ESF Actuation.Caused by Personnel Error.Personnel Counseled & Warning Labels added.W/910227 Ltr ML20029A7101991-02-22022 February 1991 LER 91-004-00:on 910123,determined That TS Section 3.3.7.5 Surveillance Requirements Not Satisfied for Fuel Zone Level & Neutron Flux Instrumentation.Caused by Misinterpretation of Ts.Calibr Procedures revised.W/910222 Ltr ML20028H7121991-01-22022 January 1991 LER 90-035-00:on 901224,14 Valves Associated W/Various Sys & Required to Perform Function of Isolating Primary Containment Determined Inoperable.Caused by Installation Error During Initial const.W/910122 Ltr ML20028H6791991-01-18018 January 1991 LER 91-002-00:on 910109,replacement Cassette Drive Unit to Replace Inoperable Seismic Monitoring Sys Not Received by 910109,rendering Sys Inoperable for More than 30 Days.Caused by Grit on Gear.Sys repaired.W/910118 Ltr ML20024F7361990-12-0707 December 1990 LER 90-025-00:on 901110,spurious LOCA Signal Resulted in ESF actuations.W/901207 Ltr ML20028G9221990-09-26026 September 1990 LER 90-017-00:on 900828,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Technician Inadvertently Shorting Power Supply During Installation of Test Jack.Blown Fuse replaced.W/900926 Ltr ML20044A9761990-07-12012 July 1990 LER 90-013-00:on 900611,dc Distribution Sys Identified to Have Inadequate Isolation Capability Between Class IE & non-Class IE Components.Cause of Event Under Investigation. Hourly Fire Watches Established Until 900626.W/900712 Ltr ML20043C5231990-06-0101 June 1990 LER 90-003-01:on 900208,HPCI Sys Isolation Valve Inadvertently Isolated During Surveillance Test.Caused by Both Channels of Isolation Logic Being in Tripped Condition at Same Time.Isolation of HPCI Sys reset.W/900601 Ltr ML20043C3211990-05-30030 May 1990 LER 90-012-00:on 900426,inoperability of RHR Sys Modes Occurred Due to Physical Separation Deficiencies.Caused by Drawing Deficiency Resulting in Installation Error During Original Const.Nonclass 1E Cable sleeved.W/900530 Ltr ML20043B1331990-05-21021 May 1990 LER 90-011-00:on 900420,discovered That Emergency Svc Water Pump B Discharge Check Valve Not Preventing Reverse Flow. Caused by Personnel Error in That Actuating Arm Incorrectly Assembled.Actuating Arm repositioned.W/900521 Ltr ML20043B1311990-05-18018 May 1990 LER 90-006-01:on 900223,determined That Capability to Activate Emergency Public Notification Sys Sirens from Counties Lost from 900112-0205.Caused by Disconnection of Phone Lines.Lines Reconnected for All counties.W/900518 Ltr ML20043A7651990-05-17017 May 1990 LER 90-008-00:on 900417,HPCI Sys Isolation & Inoperability Occurred Due to Failure of Differential Pressure Transmitter.Cause of Transmittal Failure Under Investigation.Transmitter Returned to mfg.W/900517 Ltr ML20043A6321990-05-15015 May 1990 LER 89-060-01:on 891212,standby Gas Treatment Sys Charcoal Filter Discovered in Degraded Condition W/Possible Bypass Leakage Paths.Similar Condition Discovered on 891218.Caused by Holes in Charcoal Filter assemblies.W/900515 Ltr ML20043A4261990-05-15015 May 1990 LER 90-010-00:on 900415,ESF Actuation Occurred Closing Three Containment Isolation Valves for Analyzers.Cause Unknown. Isolation Reset,Analyzers Returned to Svc & Voltmeter Not Being Used Pending Determination of cause.W/900515 Ltr ML20042G0521990-05-0404 May 1990 LER 90-009-00:on 900405,control Room Chlorine Isolation of Habitability Control Room Isolation Sys & ESF Initiated. Caused by Failure of B Toxic Gas Detector & False Signal from Untested Analyzer.Detector replaced.W/900504 Ltr ML20012C9361990-03-12012 March 1990 LER 90-005-00:on 900211,no Fire Watch Insps for Rooms 103, 114 & 117 on Elevation 177 Ft in Reactor Encl Performed by Personnel.Caused by Personnel Error.Person Involved Disciplined.Training Program improved.W/900312 Ltr ML20012C5541990-03-12012 March 1990 LER 90-004-00:on 900209,station Personnel Discovered That on 890708,22-s Reactor Power Transient Occurred in Which Reactor Thermal Power Changed by More than 15% of Rated Thermal Power in 1 H.Procedure revised.W/900312 Ltr ML20012C7071990-03-12012 March 1990 LER 90-003-00:on 900208,HPCI Sys Inboard Isolation Valve Inadvertently Isolated & Closed When One Channel of Isolation Logic Tripped.Caused by Degradation of Darlington Output Transistor.Isolation reset.W/900312 Ltr ML20011F7911990-02-26026 February 1990 LER 90-002-00:on 900125,identified That Main Control Room Ventilation Sys Outside Design Basis.Caused by Misapplication of Design Basis Assumptions.No Immediate Actions Taken as Existing Procedures adequate.W/900226 Ltr ML20006E4271990-02-0909 February 1990 LER 90-001-00:on 900122,discovered That Monthly Instrument Channel Functional Test for RCIC Steam Supply Pressure Low Missed.Caused by Deficiency in Computer Program Used to Schedule Tests.Computer Program revised.W/900209 Ltr ML20006E3451990-02-0808 February 1990 LER 90-003-00:on 900112,primary Containment & Reactor Vessel Isolation Control Sys Isolation Signals Initiated, Closing Inboard & Outboard Isolation Valves for Rwcu.Caused by Lifting Relief Valve.Opening Time reset.W/900208 Ltr ML20006E2851990-02-0707 February 1990 LER 90-002-00:on 900105,containment H2/O2 Analyzer Declared Inoperable During Containment Inerting.Caused by Reversed Tubing Connections in Installation of Analyzer Due to Mislabeling.Analyzer restored.W/900207 Ltr ML20006D5171990-02-0707 February 1990 LER 90-001-00:on 900108,Tech Spec Violation & Reactor Encl Ventilation Isolation Occurred.Caused by Personnel Error. Chief Operator Counseled on Importance of Communicating All Pertinent info.W/900207 Ltr ML20006A8801990-01-19019 January 1990 LER 89-015-00:on 891223 & 24,problem W/Reactor Protection Sys (Rps)/Uninterruptable Power Supply Static Inverter Caused Loss of Power to RPS Panel.Caused by Failure of Gate Drive Boost Card.Isolations reset.W/900119 Ltr ML20005F9441990-01-10010 January 1990 LER 89-060-00:on 891212,standby Gas Treatment Sys Charcoal Filter a Discovered to Be Degraded W/Possible Bypass Leakage Paths.On 891218,filter B Found W/Similar Condition.Caused by Failure of Spot Welds.Filters repaired.W/900110 Ltr ML20005E6841990-01-0303 January 1990 LER 89-059-00:on 891206,instrumentation & Controls Technician Inadvertently Grounded Test Jack,Resulting in Blown Fuse.Caused by Personnel Error.Fuse Replaced. Technicians counseled.W/900103 Ltr ML20042D1961989-12-29029 December 1989 LER 89-009-02:on 890820 & 0925,RCIC Sys Injections Into RCS Occurred During Startup Test.From 891023-26,three HPCI Sys Injections Into RCS Occurred During Test.Injections Anticipated.Startup Tests performed.W/891229 Ltr ML20005E3301989-12-29029 December 1989 LER 89-014-00:on 891202,unexpected Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred. Caused by Insufficient Guidance in General Plant Procedure. Appropriate Procedures Reviewed & revised.W/891229 Ltr ML20005E0961989-12-26026 December 1989 LER 89-058-00:on 891123,actuation of Group III Primary Containment & Reactor Vessel Isolation Control Sys Resulted in Automatic Isolation of Rwcu.Caused by Failure of Flow Summer Card.Card replaced.W/891226 Ltr ML20011D2291989-12-19019 December 1989 LER 89-057-00:on 891120,refuel Floor Secondary Containment Isolated on Low Flow Differential Pressure,Causing Initiation of Standby Gas Treatment Sys.Caused by Severe Storm.Normal Ventilation Restored to floor.W/891219 Ltr ML19332F8631989-12-13013 December 1989 LER 89-056-00:on 891119,unexpected Nuclear Steam Supply Shutoff Sys Group Iii,Div 4 Isolation Initiated ESF Actuation.Caused by Defective read-set Selector Switch. Switch repositioned.W/891213 Ltr ML19332F7761989-12-11011 December 1989 LER 89-013-00:on 891110,reactor Scram Occurred Following Main Turbine Trip,Causing Initiation Signals on HPCI & RCIC Sys Due to Spiking of Level Transformers.Caused by Design Error.Hpci Turbine secured.W/891211 Ltr ML19332F7751989-12-11011 December 1989 LER 89-012-00:on 891110,RWCU Sys Differential Flow Oscillations Observed While Placing RWCU 2A Filter/ Demineralizer Into Svc.Caused by Leakage in Reactor HX Tube Side Safety Relief Valve.Valve removed.W/891211 Ltr ML19332F2961989-11-29029 November 1989 LER 89-009-01:on 890820,eight RCIC Sys Injections Into RCS Occurred Under Purview of Facility start-up Test Program. Caused by Abnormal Plant Conditions Requiring Safety Sys Actuations.Rcic & HPCI Sys Tests completed.W/891129 Ltr ML19332D6331989-11-27027 November 1989 LER 89-011-00:on 891027,outboard Nuclear Steam Supply Shutoff Sys Isolation Valves Isolated.Caused by Personnel Error Due to Lack of Attention to Detail by Technicians. Event Discussed at All Hands meeting.W/891127 Ltr ML19332D6251989-11-27027 November 1989 LER 89-055-00:on 891025,reactor Protection Sys 1A Shunt Trip Breaker Tripped on Undervoltage,Causing Loss of Power to Distribution Panel 1AY160 & ESF Isolation.Caused by Relief Valve Failures.Isolations reset.W/891127 Ltr ML19332C1781989-11-17017 November 1989 LER 89-053-00:on 891022,control Room Personnel Manually Initiated Ventilation Sys Chlorine Isolation,Esf.Caused by High Vinyl Chloride Concentration in Outside Air Intake Plenum.Special Event Procedure implemented.W/891117 Ltr ML19332B9841989-11-15015 November 1989 LER 89-054-01:on 891025,discovered That Daily Channel Check Surveillance Requirement for Channel D High Level Trip Not Met.Caused by Procedural Deficiency Since Initial Plant Operation.Associated Log Procedures revised.W/891115 Ltr 1994-04-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,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 ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154H5691998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With ML20151X3511998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With ML20237F0291998-08-27027 August 1998 Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present ML20237D1041998-08-17017 August 1998 Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20237B4711998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2 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 ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20236P9781998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2 ML20196K1801998-06-30030 June 1998 Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with ML20249B3501998-06-11011 June 1998 Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5 ML20249A5331998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Limerick Units 1 & 2 ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20247H5071998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Limerick Generating Station ML20216F3601998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216F9471998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2 ML20216F3471998-02-28028 February 1998 Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1 1999-09-30
[Table view] |
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! 10 CFR 50.73 i i
t PHILADELPHIA ELECTRIC COMPANY :
LINCRICK GENER ATING ST ATION P. O. BOX A SAN ATOG A, PElih tY LV ANI A 19464 ,
I (116) 3271400 amt. 2000
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g 50-353 License Nos. NPF-39 NPF-85 ;
U.S. Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555
SUBJECT:
Licensee Event Report Limeri Q Generating Station - Units 1 and 2 ,
This LER concerns the n.anual isolation of Main Control Room
- Ventilation System and the acteation of the Control Room Emerger.cy Presh Air Supply (CREFAS) system, Engineered Safety Features, due to ,
a high toxic chemical concentration signal.
Reference:
Docket Nos. 50-357; 50-353 ;
Report Number: 1-89-053 i
. Revision Number: 00 t Event Date: October 22, 1989 Report'Date: !bvmber 17, 1989 Facility: Limerick Generating Station P.O. Box A, Sanatoga, PA 19464 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv).
8 Very truly yours, JKPich
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cc: W. T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS I
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On October 22, 1989, Main Control Room (MCR) personnel manually initiated a MCR ventilation system chlorine isolation, an Engineered Safety Feature (ESP), as a result of a high vinyl chloride concentration in the MCR outside air intake plenum as detected by the 'A' and 'B' Toxic Gas Analyzers. In conjunction with the MCR ventilation system isolation, the Control Room Emergency Fresh Air Supply System (CREFAS), also an ESF, initiated as designed and provided total recirculation of the MCR air without any intake from the outside atmosphert,. The toxic gas analyzers detected a vinyl chloride concentration of approximately 15 ppm, initiating a high toxic chemical concentration annunciator alarm. MCR personnel immediately implemented Special Event Procedure, SE-2, by donning self-contained breathing apparatus and initiating a manual MCR ventilation system chlorine isolation. The 'A' train of CREFAS I started and the redundant 'B' train of CREFAS remained in standby.
[ All systems operated as designed. The indicated vinyl chloride j concentration was well below the hazardous concentration limit. Air h samples were obtained from the MCR and no vinyl chloride was L detected. This event was caused by the presence of vinyl chloride in the MCR outside air intake plenum from an atmospheric release of the toxic chemical from the Occidental Chemical Corporation (OCC)
I which is' located in the vicinity of Limerick Generating Station.
OCC is taking the necessary measures to prevent recurrence.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION 6e+=evas cvs =o usa-a p n n ,..is e v ei !
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Limerick cenerating Stat. ion, Unit 1 e is to lo lo l3 l5 12 8 l9 0 l Sj 3 0 l0 012 or 0 15 l
. Unit Conditions P'rior to the Event: '
Unit 1 Operating Condition: 1(Power Operation) '
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Unit 2 Operating Condition: 1(Power Operation)
Unit 1 Reactor Power: 99%
Unit 2 Reactor Power: 71%
Description of the Event:
On' October 22, 1989, at 2039 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.758395e-4 months <br />, Main Control Room (MCR) personnel manually initiated a MCR ventilation system chlorine isolation, an Engineered Safety Feature (ESP), as a result of a high ,
vinyl chloride concentration in the MCR outsido air intake plenum as ;
detected by the 'A' and 'B' Toxic Gas Analyzers (EIIE VI). In
' conjunction with the mar.ual MCR ventilation system isolation the
& Control Room Emergency fresh Air Supply System (CREFAS), also an '
ESP, initiated as designed and provided total recirculation of the MCR air without any intake from the outside atmosphere.
The toxic gas analyzers function to provide indication of high toxic gas concentrations in the MCR outside air intake plenum. A manual isolation of the MCR ventilation system is required in the event toxic chemicals are detected by these toxic gas analyzers.
- The manual MCR isolation occurred following receipt of a MCR high toxic chemical concentration annunciator alarm at 2039 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.758395e-4 months <br /> on '
October 22, 1989. The 'A' and 'B' MCR Toxic Gas Analyzers indicated the presence of vinyl chloride in concentrations of approximately 15 l
ppm (5 ppm above the alarm setpoint of 10 ppm) in the MCR outside l air intake plenum. Immediately following the receipt of the alarm,
- MCR' personnel implemented Special Event Procedure SE-2, " Toxic Gas," !
and donned self-contained breathing apparatus (SCBA). The operators then manually initiated a MCR ventilatian system chlorine isolation, in accordance with system procedures, as directed by SE-2. The 'A' train of CREFAS started as designed, and the 'B' train of CREFAS remained in the automatic standby mode. Chemistry personnel then g donned SCBA, entered the MCR, and obtained air samples in the MCR.
L The results indicated that there was no vinyl chloride present in L the MCR. MCR pers>nnel then "A" and "B" Toxic Gas Analyzers indicated normal le,vels, verified and that the their SCBA at 2100 removed '
hours. ;
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Li.merick Generating Station, Unit 1 o p;olotol3l5l2 9l9 0l5l3 -- 00 n13 er oI5 m w - . ... - c ~ ,,nn At 0218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br /> on' October 23, 1989, an MCR operator contacted
- Occidental Chemical Corporation (OCC), a chemical plant located approximately two miles from Limerick Generating Station (LGS),;by telephone in reference to any atmospheric releases of toxic chemicals that may have occurred at their plant. The individual on the phone from OCC did state that they were currently experiencing difficulties with their incinerators, and to call again later. Upon
' contacting the company again at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, an OCC official verified there was an earlier release of vinyl chloride and that the incident was over. 'He also stated that the duration of the vinyl chloride release lasted for approximately fifteen (15) minutes and thereafter the plant had returned to a stabilized condition. The MCR isolation was reset at.1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> on October 23, 1989, and normal MCR ventilation was restored. A four (4) hour notification to the NRC .
was made in accordance with 10CFRSO.72(a)(2)(ii) at 2326 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.85043e-4 months <br /> on October 22, 1989, since this event resulted in a manu'al actuation of
Consequences of the Event:
The consequences of this event were minimal. There was no release of radioactive material to the environment as a result of this event.
Both the 'A' and 'B' Toxic Gas Analyzers functioned as designed and alarmed on the presence of vinyl chloride. The MCR ventilation system isolated, and the 'A' train of CREFAS started and operated as designed. The redundant 'B' train of CREFAS was in the automatic standby mode and was available for operation in the event the 'A'
' train failed to properly function.
In the event these systems had failed to properly function, the consequences would have been minimal in 4 hat the vinyl chloride concentrations detected by the toxic gas analyzers were well below specified hazardous limits. NRC Regulatory Guide'l.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," as referenced L in the LGS Final' Safety Analysis Report (Section 6.4.1), defines the l toxic limit of vinyl chloride,at 1000 ppm. The maximum limit t
observed during this event was 15 ppm which is well below this toxic limit. In addition, MCR personnel donned SCBA which provided .
protection against the inhalation of any toxic chemicals. ,'
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T" UCENSEE EVENT REPORT (LER) TEXT CONTINUATION *.m so eve =o sin re.
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0 l0 014 07 0 15 rart v . w. ..e , = ., on Cause of the Event:
The cause of this event was the presence of vinyl chloride in the MCR outside air intake plenum as detected by the 'A' and 'B' Toxic Gas Analyzers. The source of the vinyl chloride originated from an atmospheric release of the toxic chemical from the OCC which is ,
located in the. vicinity of the station. The operators manually initiated a MCR isolation and CREFAS initiated as designed providing the release.designed protection for the operators from the toxic gas Corrective Actions:
MCR personnel immediately implemented Special Event Procedure SE-2, !
\
" Toxic the Gas," and donned SCBA within two (2) minutes as required by procedure. Operations personnel then manually initiated a MCR ventilation system chlorine isolation, on all four chlorine isolation channels ("A", "B", "C", and "D"), in accordance with system procedures, as directed by SE-2. Chemistry personnel don'ned SCBA and obtained air samples from the MCR. The results indicated i
that there was no vinyl chloride present in the MCR. All systems
( and equipment responded as designed and performed their intended functions. Following confirmation of the source of the vinyl chloride and that the release was terminated, MCR personnel restored #
MCR ventilation to normal operation and shutdown the CREFAS. The duration of MCR ventilation system isolation and CREFAS operation was approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
Actions Taken to Prevent Recurrence:
This chloride.event re's'ulted from an actual release and detection of vinyl At LGS, all systems responded as designed and therefore no further corrective actions to prevent recurrence are planned.
OCC is taking the necessary action to prevent recurrence of the release of vinyl chloride.
These actions are documented in a.
National Emission Standard for flazardous Air Pollutants (NESHAP) report submitted by OCC to the US Environmental Protection Agency and Pennsylvania Department of Environmental Resources. A follow up meeting between OCC and LGS management will be arranged to review .
the twoOCC plants actions in theand event to establish of futuredirect events. communications between the N hh5 .
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Previous similar' Occurrences:
- I LER's 85-90, 06-22, 86-28, 88-43 and 89-029 reported manual -
isolations of MCR ventilation due to high toxic chemical l concentration signals.
- Tracking C6de C99 (Other External Cause) s P
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