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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
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10 CFR 50.73 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENER ATING ST ATION P, O. BOX A SAN ATOG A. PENNSYLV ANI A 19464 (216) 3271200 sat,2000 M. J. M cCOMMIC K. Ja. P.E.
6.....2^.".'.".'.'".".m..., December 13, 1989 '
Docket No. 50-352' License No. NPF-39 ;
U.S. Nuclear Regulatory Commission
,i Attn: Document Control Desk Washington, DC 20555
'i
SUBJECT:
Licensee Event Report Limerick Generating Station - Unit 1
[ _
l' l- This LER reports an unexpected Reactor Water Cleanup System L isolation, an actuation of a portion of the Nuclear Steam Supply Shutoff system-(an Engineered Safety Feature), due to a defective selector switch on.a Riley Corp. temperature transmitter trip
. unit.-
-References. Docket No. 50-352-Report Number: 1-89-056 Revision Number: 00 i Event Date: Noveraber 19, 1989 '
Report Date: December 13, 1989 Facility: Limerick Generating Station ->
P.O. Box A, Sanatvga, PA 19464 1
This LER is being submitted pursuant to the-requirements of ,
10 CFR 50.73(a)(2)(iv).. :
Very t uly yours, f
DMS:ch cc: W. T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS 8912190222 891213 PDR ADOCK 05000352, h/
S PDC
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!~ ""* ** Uni t 1 Reactor Water Cleanup System isolation due to a detective I selector switch on a temperature transmitter trip unit.
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, , i O'n November 19, 1989, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, a plant operator placed the -
" READ-SET" selector switch located on temperature transmitter
. trip unit, TTS-44-lN600M, to the " READ" position to obtain a temperature reading for the Reactor Water Cleanup (RWCU) 'lB' Non-Regenerative Beat Exchanger (NRHX) room area. Immediately'
- after the selector switch was placed to the " READ" position, an unexpec'ted Nuclear Steam Supply Shutoff System Group III,
, Division 4 isolation was initiated, an Engineered Safety Feature actuation. The isolation signal caused the RWCU Outboard Primary s Containment Isolation Valve to close, and the RWCU pumps then , J. ,
tripped on low flow. Instrumentation and Controls (I&C) ,
technicians repositioned the selector switch in order that the isolation signal could be reset by the Main Control Room operators. The BWCU system was out of service for nin'eteen minutes. The consequences of this event were minimal. The reactor water level and chemistry were not affected by the RWCU l system isolation. The RWCU system isolation was caused by a defective " READ-SET" celector switch on the 'lB' NRHX room area temperature transmitter trip unit. I&C technicians replaced the l temperature transmitter trip unit which had the defective selector switch. No other incidents have occurred as a result of a defective selector-switch on similar trip units. .
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Unit-Conditions Prior to the Event: -
4: ,
Operating Condition: 1.(Power Operations)
Power Levels- 100%. .-
l Description of the Event:
On November 19, 1989, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, the Reactor Water Cleanup .
(RWCU) system (EIIS CE) Outboard Primary Containment Isolation Valve (PCIV), HV-44-lF004, automatically isolated.
This .
isolation was due~to a Nuclear Steam Supply Shutof" System I (NSSSS) (EIIS:JM) isolation actuation, an Engineered Safety Feature (ESP), from a spurious trip of the Steam Leak Detection ,
(SLD) system (EIIS:IJ) isolation signal.
, During performance of the Unit 1. Daily Surveillance Test, a non-licensed. plant operator placed the " READ-SET" selector switch ,
'(EIIS:ES) located on Riley Corp. (Model No. 86APPGF-EG) ,
temperature transmitter trip.. unit (EIIS:TS), TTS-44-lN600M, to the:" READ" position to obtain a SLD system temperature reading-for the RWCU 'lD' Non-Regenerative Heat Exchanger (NRHX) room area. The~ Daily Surveillance Test requires the performance of channel checks on each isolation actuation instrumentation channel every shift (once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />), to meet Technical Specifications (TS) Surveillance Requirement 4.3.2.1.
Immediately after the selector switch was placed to the " READ" position, an-unexpected NSSSS Group III, Division 4 isolation actuation occurred. The isolation signal caused RWCU valve HV-1 44-lF004 to close, and the RWCU pumps then t. ripped on low flow.
The isolation was accompanied by a."Div 4 Steam Leak Det Sys Hi Temp"' annunciator. alarm in the Main Control Room (MCR) as y expected..
_ MCR operators then notified the shift Instrumentation and Controls (I&C) technicians of the RWCU system isolation event.
Upon investigation, I&C technicians discovered that the selector switch was defective.- The technicians repositioned the selector switch in order that the isolation signal could be reset by the MCR operators. I&C also performed the calibration functional test for the trip unit and verified that the trip unit would perform its design function if required.. -
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The MCR operators then reset the isolation signal at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, y in accordance with General Plant (GP) procedure GP-8, " Primary j and Secondary Containment Isolation Verification and Reset," and ,
the RWCU system was returned to service at 0154 hours0.00178 days <br />0.0428 hours <br />2.546296e-4 weeks <br />5.8597e-5 months <br />. The RWCU system was out of service for nineteen (19) minutes.
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. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION <movio oue iso aimaio.
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"""* I Limerick Generat'ing Station, Unit 1 l
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0l5l6 0l 0 0l 3 cF 0 14 ven s. m.w aac a-a mna v on A'four hour notification was made to the NRC'on November 19, at 0402. hours, in accordance with the requirements of 10 CFR 50.72 (b)(2)(ii) since the event resulted in the automatic actuation of (
an ESF. Accordingly, this event is being reported in accordance with the. requirements of 10 CFR 50.73 (a)(2)(iv).
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 i this event. The RWCU system isolated, as designed, when the '
defective selector switch initiated a NSSSS Group III, Division 4 isolation signal. Additionally, the reactor water level and chemistry were not affected by-the RWCU system isolation. l l
In the event the outboard RWCU system isolation valve failed to
'close on an actual high NRHX room area temperature, the redundant j
' channel inboard isolation valve would have closed to isolate the ;
system. l Cause of the Event:
l l
The RWCU system isolation was caused by a defective " READ-SET" selector switch on the SLD system 'lB' NRHX room area transmitter trip unit.- When the selector switch was placed to the " READ" position, the trip unit circuitry was de-energized which initiated a RWCU outboard isolation.
Corrective Actions:
The I&C technicians repositioned the selector switch in order that the isolation signal could be reset by the MCR operators, and performed the calibration functional test to verify that the trip unit would-perform its design function if required. A "Do .
Not Operate" tag wan placed on the selector switch, and the MCR operators were instructed to notify I&C when temperature readings from the trip unit were to be taken until the selector switch was q repaired. The MCR operators then reset the isolation signal using GP-8 at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, and the RWCU system was returned to ,
service at 0154 hours0.00178 days <br />0.0428 hours <br />2.546296e-4 weeks <br />5.8597e-5 months <br />, g.,.a..
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i.lCENSEE EVENT REPORT (LER) TEXT CONTINUATl N ovio e.
, ,,.', ameias: e m as pagatify smaast tu . Decst? asume6a es tem esunseca 663 Past tal Limerick Generating Station, Unit 1 f 0 l5 l0 l0 l0 l3 l Sl 2 8; 9 ._
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0l 0 01 4 0F 0 l4 vent . . a sm aac e mna v on Actions Taken to Prevent Recurrence:
On November 20, 1989 at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />, I&C technicians replaced temperature transmitter trip unit, TTS-44-lN600M, which had the defective selector switch.
There are approximately eighty six (86) Unit 1 Riley Corp.
temperature transmitter trip units with " READ-SET" selector switches being operated daily by plant operators. Each selector switch _is operated over ninety (90) times per month. No other incidents have occurred as a result of a defective selector switch on the Unit 1 Riley trip units. There have been no trip units previously replaced due to a broken or defective selector switch. Additionally, the Riley temperature transmitter trip unit in question was installed in SLD system on April 12, 1989, and is not the_ original Riley trip unit that was installed during the Unit 1 construction phase. There are identical Riley trip units which have been in operation since Unit I start-up
'(approximately six (6) years), with-no selector switch problems.
Therefore this event is considered to be an isolated occurrence.
Additionally, the Riley temperature transmitter. trip' unit with
.the defective _ selector. switch will be sent to_Riley Corp. for a ,
failure cause analysis, i
Previous Similar Occurrences:
f
! There are no previous similar-occurrences, however, LER's 84-12, 26, 34, 35, 36; 85-01, 25, 27, 35, 55; 86-13, and 87-052 reported isolations of the RWCU system resulting from a design deficiency of the Riley Corp. temperature transmitter trip unit circuitry.
There was not a design deficiency in the selector switch portion of the trip unit. Therefore, the design change performed for the l
previous events could not have prevented the occurrence of this event.
Tracking Codes: X Other, unexpected failure '
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