05000353/LER-1998-001, Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys

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Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys
Person / Time
ML20236H867
Site:	Limerick
Issue date:	07/02/1998
From:	Gallagher M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20236H870	List: 05000353/LER-1998-001, Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys 05000353/LER-1998-001-03, :on 980602,three Barksdale Model C9622-3-B Pressure Switches Located on Relayed Emergency Trip Sys Found Inoperable from Common Cause.Caused by Inadequate Allowances for Switch Performance.Trip Setpoint Revised
References
NUDOCS 9807070397
Download: ML20236H867 (1)
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LER-1998-001, Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
3531998001R00 - NRC Website
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text

_.

Michael P. Gilla;ha, P.E.

Plant Manager Umenck Generating Station PECO NUCLEAR PECO Energy Company i

bmerick Generating Station A Unit of PECO Energy SSn a. P 19464-0920 610 718 2000 July 2, 1998 Docket No. 50-352 License No. NPF-39 U.S. Nuclear Regulatory Commission Attn.:

Document Control Desk Washington, DC 20555

SUBJECT:

Licensee Event Report l

Limerick Generatina Station - Unit 2 This LER concerns the discovery of three Barksdale Model C9622-3-B differential pressure switches located on the Main Turbine Relayed Emergency Trip System that were determined to be inoperable from a common cause.

These switches provide input to the Reactor Recirculation Pump End-of-Cycle i

Trip and Reactor Protection System.

This condition resulted in two or more independent trains of a single safety system being inoperable due to a common cause.

Reference:

Docket No. 50-352 Report Number:

2-98-001 Revision Number:

00 Event Date:

June 2, 1998 Report Date:

July 2, 1998 Facility:

Limerick Generating Station P.O. Box 2300, Sanatoga, PA 19464 This LER is being submitted pursuant to the requirements of 10CFR50.73 (a) (2) (vii).

Very truly yours, l

MCK cc:

H.

J. Miller, Administrator Region I, USNRC A. L.

Burritt, USNRC Senior Resident Inspector, LGS l

l l

9907070397 990702

'f }- '

PDR ADOCK 05000353 S

Licensee Event Report

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		Reporting criterion
05000352/LER-1998-001, :on 980124,Unit 1 HPCI Sys Initiation Occurred. Caused by Less than Adequate Understanding for Potential Loss of Grounding Signal Upon Troubleshooting Control Form. Event Will Be Reviewed by All Work Group Personnel	on 980124,Unit 1 HPCI Sys Initiation Occurred. Caused by Less than Adequate Understanding for Potential Loss of Grounding Signal Upon Troubleshooting Control Form. Event Will Be Reviewed by All Work Group Personnel	10 CFR 50.73(a)(2)(iv), System Actuation
05000353/LER-1998-001-03, :on 980602,three Barksdale Model C9622-3-B Pressure Switches Located on Relayed Emergency Trip Sys Found Inoperable from Common Cause.Caused by Inadequate Allowances for Switch Performance.Trip Setpoint Revised	on 980602,three Barksdale Model C9622-3-B Pressure Switches Located on Relayed Emergency Trip Sys Found Inoperable from Common Cause.Caused by Inadequate Allowances for Switch Performance.Trip Setpoint Revised
05000353/LER-1998-001, Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys	Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000352/LER-1998-002, :on 980206,primary Containment & Rv Isolation Control Sys Actuation Occurred.Caused by Personnel Error. Fuse Was Replaced & All Isolations Were Reset within 55 Minutes	on 980206,primary Containment & Rv Isolation Control Sys Actuation Occurred.Caused by Personnel Error. Fuse Was Replaced & All Isolations Were Reset within 55 Minutes	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000353/LER-1998-002-01, :on 980603,automatic Isolation of Reactor Water Cleanup Suction Valve,Occurred.Caused by Electromagnetic Interference.Ferrite Torroids Were Added to Wires Entering & Leaving RRCS Hpoi Cards to Filter Out High Frequency Spike	on 980603,automatic Isolation of Reactor Water Cleanup Suction Valve,Occurred.Caused by Electromagnetic Interference.Ferrite Torroids Were Added to Wires Entering & Leaving RRCS Hpoi Cards to Filter Out High Frequency Spikes	10 CFR 50.73(a)(2)(iv), System Actuation
05000353/LER-1998-002, Forwards LER 98-002-00,reporting Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Occurring When Electromagnetic Interference Due to Component Testing Inducing Signal in Redundant Reactivity Control Sys C	Forwards LER 98-002-00,reporting Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Occurring When Electromagnetic Interference Due to Component Testing Inducing Signal in Redundant Reactivity Control Sys Cable
05000353/LER-1998-003, Forwards LER 98-003-00 Re 980622 Inoperability of Main Condenser Offgas pre-treatment Radioactivity Monitor Skid Which Resulted from Incorrect Procedure	Forwards LER 98-003-00 Re 980622 Inoperability of Main Condenser Offgas pre-treatment Radioactivity Monitor Skid Which Resulted from Incorrect Procedure	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000353/LER-1998-003-02, :on 980622,determined That Main Condenser Offgas pre-treatment Rad Monitor Was Inoperable.Caused by Incorrect Procedure.Sys Procedure Has Been Revised to Remove Incorrect Procedure	on 980622,determined That Main Condenser Offgas pre-treatment Rad Monitor Was Inoperable.Caused by Incorrect Procedure.Sys Procedure Has Been Revised to Remove Incorrect Procedure	10 CFR 50.73(a)(2)(1)
05000352/LER-1998-003, :on 980213,ESF Actuation Due to Incidental Contact W/Rv Instrument Rack Occurred.Caused by Personnel Error.Counseled Individual Involved & Training for Site Personnel	on 980213,ESF Actuation Due to Incidental Contact W/Rv Instrument Rack Occurred.Caused by Personnel Error.Counseled Individual Involved & Training for Site Personnel	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000353/LER-1998-004, Forwards LER 98-004-00,reporting Manual Actions Taken in Response to Plant Conditions,To Perform Secondary Containment Isolation,Sgts Initiation & RERS Initiation	Forwards LER 98-004-00,reporting Manual Actions Taken in Response to Plant Conditions,To Perform Secondary Containment Isolation,Sgts Initiation & RERS Initiation	10 CFR 50.73(a)(2)(iv), System Actuation
05000353/LER-1998-004-02, :on 980626,secondary Containment Isolation, SGTS & RERS Initiation Manual Action,Occurred.Caused by Failure of Normal Reactor Enclosure HVAC to Maintain Negative Pressure.Repaired B Train SGTS Control Components	on 980626,secondary Containment Isolation, SGTS & RERS Initiation Manual Action,Occurred.Caused by Failure of Normal Reactor Enclosure HVAC to Maintain Negative Pressure.Repaired B Train SGTS Control Components	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation
05000352/LER-1998-004, :on 980320,missing Fire Dampers in Safe Shutdown Barriers Were Noted.Caused by Inadequate Design Review of Initial Fire barrier.Fire-watches Previously Established for Thermo-lag Issues Were Verified	on 980320,missing Fire Dampers in Safe Shutdown Barriers Were Noted.Caused by Inadequate Design Review of Initial Fire barrier.Fire-watches Previously Established for Thermo-lag Issues Were Verified	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000353/LER-1998-005-01, :on 980629,discovered That Procedure ST-6-107-887-2 Which Has Weekly Frequency Had Exceeded TS Surveillance Period W/Applicable TS Action Not Being Met. Caused by Personnel Error.Developed Routine OOS Rept	on 980629,discovered That Procedure ST-6-107-887-2 Which Has Weekly Frequency Had Exceeded TS Surveillance Period W/Applicable TS Action Not Being Met. Caused by Personnel Error.Developed Routine OOS Rept	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000353/LER-1998-005, Forwards LER 98-005-00,reporting Condition Prohibited by TS in That Surveillance Test Exceeded TS Surveillance Requirement Time Period & Applicable TS Action Had Not Been Met	Forwards LER 98-005-00,reporting Condition Prohibited by TS in That Surveillance Test Exceeded TS Surveillance Requirement Time Period & Applicable TS Action Had Not Been Met	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-1998-005, :on 980322,load Ctr Feedwater Breaker 124B-62 tripped,de-energizing Components Supported by Load Ctr 124B. Caused by Combination of pre-existing Steam Leak in 1A RWCU Pump Room Circuit Breaker Replaced	on 980322,load Ctr Feedwater Breaker 124B-62 tripped,de-energizing Components Supported by Load Ctr 124B. Caused by Combination of pre-existing Steam Leak in 1A RWCU Pump Room Circuit Breaker Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
05000352/LER-1998-006, :on 980405,post Maint Surveillance Test Was Not Performed for A2 RPS Channel Relay Replacement.Caused by Incomplete Document Review.Relay Work Was Reviewed to Evaluate & Resolve Impact of Relay Work on Any Required Sys	on 980405,post Maint Surveillance Test Was Not Performed for A2 RPS Channel Relay Replacement.Caused by Incomplete Document Review.Relay Work Was Reviewed to Evaluate & Resolve Impact of Relay Work on Any Required Sys	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000353/LER-1998-006-01, :on 980726,noted Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Caused by Personnel Error. Counseled Personnel & Conducted Training Re Event	on 980726,noted Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Caused by Personnel Error. Counseled Personnel & Conducted Training Re Event	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000353/LER-1998-006, Forwards LER 98-006-00 Re Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Cause of 980726 Event Is Attributed to Personnel Error	Forwards LER 98-006-00 Re Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Cause of 980726 Event Is Attributed to Personnel Error
05000352/LER-1998-007, :on 980422,discovered Three Itt Barton Model 580A Differential Pressure Switches Inoperable.Caused by Misapplication.Replaced Subject Itt Barton Differential Pressure Switches in safety-related Applications	on 980422,discovered Three Itt Barton Model 580A Differential Pressure Switches Inoperable.Caused by Misapplication.Replaced Subject Itt Barton Differential Pressure Switches in safety-related Applications
05000353/LER-1998-007-01, :on 971210,personnel Determined That Surveillance Requirements Were Not Met for RHR Heat Exchanger Discharge Line High Radiation Indication. Caused by Personnel Error.Test for Common Monitor Revised	on 971210,personnel Determined That Surveillance Requirements Were Not Met for RHR Heat Exchanger Discharge Line High Radiation Indication. Caused by Personnel Error.Test for Common Monitor Revised	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000353/LER-1998-007, Forwards LER 98-007-00,reporting Condition Prohibited by TS, in That Remote Shutdown Panel Instrument Calibr Was Not within Required Frequency & Required Actions Were Not Taken. Event Occurred Due to Administrative Error	Forwards LER 98-007-00,reporting Condition Prohibited by TS, in That Remote Shutdown Panel Instrument Calibr Was Not within Required Frequency & Required Actions Were Not Taken. Event Occurred Due to Administrative Error	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000353/LER-1998-008-02, :on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced	on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000353/LER-1998-008, Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl	Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-1998-008-01, Forwards LER 98-008-01 Re Pressure Setpoint Drift of Thirteen Main Steam Sys SRVs Primarily Caused by Corrosion Induced Bonding within SRVs	Forwards LER 98-008-01 Re Pressure Setpoint Drift of Thirteen Main Steam Sys SRVs Primarily Caused by Corrosion Induced Bonding within SRVs
05000352/LER-1998-008, :on 980429,discovered Pressure Setpoint Drift of Five Main Steam Sys Srvs.Caused by Corrosion Induced Bonding.Replaced Fourteen SRV Pilot Valves W/Calibr Spares During 1R07 & Util Is Evaluating three-stage SRV Design	on 980429,discovered Pressure Setpoint Drift of Five Main Steam Sys Srvs.Caused by Corrosion Induced Bonding.Replaced Fourteen SRV Pilot Valves W/Calibr Spares During 1R07 & Util Is Evaluating three-stage SRV Design	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000352/LER-1998-009, :on 841026,noted That Primary Containment Overcurrent Protection Circuits May Not Have Provided Redundant Protection.Caused by Original Licensing Basis Interpretation.Corrected Affected Subject Circuits	on 841026,noted That Primary Containment Overcurrent Protection Circuits May Not Have Provided Redundant Protection.Caused by Original Licensing Basis Interpretation.Corrected Affected Subject Circuits	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000352/LER-1998-010, :on 980526,identified Two Surveillance Tests Associated W/Rc Recirculation Sys Flow Units A/C & B/D Calibr,Respectively.Caused Attributed to Personnel Error. Units Satisfactorily Tested	on 980526,identified Two Surveillance Tests Associated W/Rc Recirculation Sys Flow Units A/C & B/D Calibr,Respectively.Caused Attributed to Personnel Error. Units Satisfactorily Tested	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000352/LER-1998-011, :on 970901,1B RHR Pump Was Inoperable Due to Intermittent Min Flow Valve Closures.Caused by Failed Rosemount 510DU Trip Unit.Failed Trip Unit Was Replaced	on 970901,1B RHR Pump Was Inoperable Due to Intermittent Min Flow Valve Closures.Caused by Failed Rosemount 510DU Trip Unit.Failed Trip Unit Was Replaced	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-1998-012, :on 980530,HPCIS Declared Inoperable.Caused by Locking Tab Piece from Older Style & Piece Broke Off of Currently Installed Locking Tab.Conducted Internal Insp of HPCI Turbine on Each Unit	on 980530,HPCIS Declared Inoperable.Caused by Locking Tab Piece from Older Style & Piece Broke Off of Currently Installed Locking Tab.Conducted Internal Insp of HPCI Turbine on Each Unit	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000352/LER-1998-013, :on 841026,failed to Meet Max Travel Distance Limitation & Guidance for Class a Extinguisher Replacement W/Hose Stations.Caused by Failure to Provide Deviation Documentation.Place Extinguishers in Fire Brigade Locker	on 841026,failed to Meet Max Travel Distance Limitation & Guidance for Class a Extinguisher Replacement W/Hose Stations.Caused by Failure to Provide Deviation Documentation.Place Extinguishers in Fire Brigade Locker
05000352/LER-1998-014, :on 980128,several Rwcs Isolations Were on High Differential Flow Signals.Caused by Sys Perturbations. Shift Update Notice Was Issued to All Operations Personnel	on 980128,several Rwcs Isolations Were on High Differential Flow Signals.Caused by Sys Perturbations. Shift Update Notice Was Issued to All Operations Personnel	10 CFR 50.73(a)(2)(iv), System Actuation
05000352/LER-1998-015-01, Forwards LER 98-015-01,re Condition Prohibited by TS Due to Calibration Error.Rev Makes Editorial Corrections to Description of Event	Forwards LER 98-015-01,re Condition Prohibited by TS Due to Calibration Error.Rev Makes Editorial Corrections to Description of Event
05000352/LER-1998-015, :on 950216,discovered That Error in Calibr of CS Internal Line Break Detection Instrumentation Resulted in Setpoints Being Outside Required TS Limit.Recalibr Affected Instrumentation to Account for Change in Baseline Dp	on 950216,discovered That Error in Calibr of CS Internal Line Break Detection Instrumentation Resulted in Setpoints Being Outside Required TS Limit.Recalibr Affected Instrumentation to Account for Change in Baseline Dp	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-1998-016, :on 980728,manual Main CR Ventilation Isolation & CR Emergency Fresh Air Sys Was Initiated Due to Small Freon Leak.Caused by Lack of Preventive Maint.Freon Leak Was Repaired & Chiller Was Tested Satisfactorily	on 980728,manual Main CR Ventilation Isolation & CR Emergency Fresh Air Sys Was Initiated Due to Small Freon Leak.Caused by Lack of Preventive Maint.Freon Leak Was Repaired & Chiller Was Tested Satisfactorily	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000352/LER-1998-017, :on 841026,failure of Fire Protection Hatchway Flow Control Valves to Actuate Was Noted.Caused by Lack of Understanding of Hardware.Modified Hatchway Flow Control Valves & Revised Associated Surveillance Tests	on 841026,failure of Fire Protection Hatchway Flow Control Valves to Actuate Was Noted.Caused by Lack of Understanding of Hardware.Modified Hatchway Flow Control Valves & Revised Associated Surveillance Tests	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-1998-018, :on 980911,potential Loss of EDG Control in Event of Fire,Was Determined.Caused by fire-induced Damage to Unprotected Voltage & Speed Control Cables.Ncr 98-02422 Was Generated to Disposition Identified Deficiencies	on 980911,potential Loss of EDG Control in Event of Fire,Was Determined.Caused by fire-induced Damage to Unprotected Voltage & Speed Control Cables.Ncr 98-02422 Was Generated to Disposition Identified Deficiencies	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000352/LER-1998-019, :on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk	on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk	10 CFR 50.73(a)(2)(viii)(A)

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