05000333/LER-1996-010-01, Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of

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Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of Commitments
Person / Time
ML20138D776
Site:	FitzPatrick
Issue date:	04/22/1997
From:	Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138D781	List: 05000333/LER-1996-010, :on 960916,plant Was Shut Down Re Inadvertent Connection of Two Terminals While Calibrating Protective Relay Due to Human Error.Personnel Responsible for Initiating Event Have Been Counseled 05000333/LER-1996-010-01, Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of
References
JAFP-97-0153, JAFP-97-153, NUDOCS 9705010235
Download: ML20138D776 (2)
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LER-1996-010, Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of Commitments

Event date:
Report date:
3331996010R01 - NRC Website
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text

-

. _.., g Jsmes A. FitzPatrick P

Nuct:ar Powir PI:nt P.O. Box 41 Lycoming. New York 13093 315 342-3840

& Authon.IkPOEOI OE Edaeu. Colomb ty site executive Orrice, April 22, 1997 JAFP-97-0153 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C.

20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Licensee Event Report: LER-96-010-01 1

Plant Shutdown Due to Human Error Inadvertently Connecting Two Terminals While Calibrating Protective Relay

Dear Sir:

This report was submitted in accordance with [10 CFR I

50. 73 (a) (2) (iv), "Any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF) including the reactor protection system (RPS)").

This submittal revises the report to include corrective action for human performance deficiencies.

Questions concerning this report may be addressed to Mr. Mark Abramski at (315) 349-6305.

4 Very truly yours,

?

f e

MICHAEL J.

COLOM

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MJC:MA:las 4

Enclosure

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cc:

USNRC, Region I USNRC Resident Inspector 1

INPO Records Center 010022 lll lll lil l b lil lll ll 1

9705010235 970422 lli lli lll lllllll l.ll l1 1 PDR ADOCK 05000333; s

Licensee Event Report

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		Reporting criterion
05000333/LER-1996-001-01, :on 960125,failed to Implement RM Instrumentation Setpoint Changes Following Revision to Odcm. Caused by Personnel Error.Rm Alarm Setpoints Verified & Personnel Counseled	on 960125,failed to Implement RM Instrumentation Setpoint Changes Following Revision to Odcm. Caused by Personnel Error.Rm Alarm Setpoints Verified & Personnel Counseled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000333/LER-1996-002-01, :on 960212,potential Common Mode Failure of Circuit Breakers in Both Safety Divisions Occurred Due to Design or Installation Error.Replaced Contacts in Failed Circuit Breakers	on 960212,potential Common Mode Failure of Circuit Breakers in Both Safety Divisions Occurred Due to Design or Installation Error.Replaced Contacts in Failed Circuit Breakers	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)
05000333/LER-1996-003-01, :on 960222,plant Shutdown Due to Degraded Control Rod Scram Times & Manual Scram.Caused by Leak in Main Turbine EHC Sys.C/A:Bypass Valves Replaced	on 960222,plant Shutdown Due to Degraded Control Rod Scram Times & Manual Scram.Caused by Leak in Main Turbine EHC Sys.C/A:Bypass Valves Replaced	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)
05000333/LER-1996-004-01, :on 960228,multiple SRV Pilot Solenoid Failed Due to Foreign Matls,Vendor Deficiencies & Procedural Errors.Replaced Pilot Solenoid Valve W/Another Rebuilt Assembly	on 960228,multiple SRV Pilot Solenoid Failed Due to Foreign Matls,Vendor Deficiencies & Procedural Errors.Replaced Pilot Solenoid Valve W/Another Rebuilt Assembly
05000333/LER-1996-005-01, :on 960506,error in Safety Limit Minimum Critical Power Ratio (MCPR) Calculation Occurred.Caused by Error in Calculation of Methodology.Administrative Controls Re Operating MCPR Instituted	on 960506,error in Safety Limit Minimum Critical Power Ratio (MCPR) Calculation Occurred.Caused by Error in Calculation of Methodology.Administrative Controls Re Operating MCPR Instituted	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)
05000333/LER-1996-006-01, :on 960511,isolation of Reactor Core Isolation Cooling Sys Occurred.Caused by Failure of Master Trip Unit. Master Trip Unit Replaced W/Vendor Current Model	on 960511,isolation of Reactor Core Isolation Cooling Sys Occurred.Caused by Failure of Master Trip Unit. Master Trip Unit Replaced W/Vendor Current Model	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000333/LER-1996-007-01, :on 960522,sys Isolations & Standby Gas Treatment Initiation Occurred.Caused by False High Radiation Trip Signal.Detector Replaced W/Vendor Current Model	on 960522,sys Isolations & Standby Gas Treatment Initiation Occurred.Caused by False High Radiation Trip Signal.Detector Replaced W/Vendor Current Model	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000333/LER-1996-008-01, :on 960906,HPCI Sys Declared Inoperable Due to Failed DC to AC Power Inverter.Failed C11 Capacitor Located in HPCI Inverter 23INV-79 Replaced	on 960906,HPCI Sys Declared Inoperable Due to Failed DC to AC Power Inverter.Failed C11 Capacitor Located in HPCI Inverter 23INV-79 Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000333/LER-1996-009-01, :on 960722,EDG B Failed to Complete Startup Sequence.Caused by Incorrect Installation of Agastat Relays. Calibr & Placed Devices 93-62-1EDGB01,93-62-1EDGB12 & 93-52A-1EDGB01 in Correct Locations	on 960722,EDG B Failed to Complete Startup Sequence.Caused by Incorrect Installation of Agastat Relays. Calibr & Placed Devices 93-62-1EDGB01,93-62-1EDGB12 & 93-52A-1EDGB01 in Correct Locations	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000333/LER-1996-010-01, Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of	Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of Commitments
05000333/LER-1996-010, :on 960916,plant Was Shut Down Re Inadvertent Connection of Two Terminals While Calibrating Protective Relay Due to Human Error.Personnel Responsible for Initiating Event Have Been Counseled	on 960916,plant Was Shut Down Re Inadvertent Connection of Two Terminals While Calibrating Protective Relay Due to Human Error.Personnel Responsible for Initiating Event Have Been Counseled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000333/LER-1996-011-01, :on 961028,both Standby Liquid Control Subsystems Determined Inoperable.Due to Inoperable Pump Discharge Pressure Relief Valves.Slc Sys Pump Discharge Pressure Relief Valve 11SV-39A Was Replaced	on 961028,both Standby Liquid Control Subsystems Determined Inoperable.Due to Inoperable Pump Discharge Pressure Relief Valves.Slc Sys Pump Discharge Pressure Relief Valve 11SV-39A Was Replaced	10 CFR 50.73(a)(2)(1)
05000333/LER-1996-012-01, :on 961111,primary Containment Accumulative Leakage in Excess of Maximum Allowed by TS Occurred.Caused by Build Up on Valve Seat Areas.Efes Were Completed for Each Failed Valve	on 961111,primary Containment Accumulative Leakage in Excess of Maximum Allowed by TS Occurred.Caused by Build Up on Valve Seat Areas.Efes Were Completed for Each Failed Valve	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1)
05000333/LER-1996-013-01, :on 961116,reactor Protection & Primary Containment Isolation Sys Actuation on False Low Reactor Water Level Occurred Due to Personnel Error.Instrument Surveillance Procedure Changed	on 961116,reactor Protection & Primary Containment Isolation Sys Actuation on False Low Reactor Water Level Occurred Due to Personnel Error.Instrument Surveillance Procedure Changed	10 CFR 50.73(a)(2)(iv), System Actuation
05000333/LER-1996-014, :on 961215,manual Scram Occurred Due to Leak in Main Turbine electro-hydraulic Control Sys.Failed Actuator Seal Was Repaired & Equipment Failure Evaluation of 29BPV-4 Actuator Seal Was Completed	on 961215,manual Scram Occurred Due to Leak in Main Turbine electro-hydraulic Control Sys.Failed Actuator Seal Was Repaired & Equipment Failure Evaluation of 29BPV-4 Actuator Seal Was Completed	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000333/LER-1996-015-01, :on 961218,determined Bypass Flow Path Around Offgas Isolation Valve.Caused by Design Deficiency.Installed Check Valve in Common Drain Line to Prevent Reverse Flow from Steam Jet Air Ejector Discharge	on 961218,determined Bypass Flow Path Around Offgas Isolation Valve.Caused by Design Deficiency.Installed Check Valve in Common Drain Line to Prevent Reverse Flow from Steam Jet Air Ejector Discharge	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)

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