Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors
Person / Time
ML20078L594
Site:	Arkansas Nuclear
Issue date:	11/21/1994
From:	Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078L597	List: 05000368/LER-1994-001, Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors 05000368/LER-1994-001-01, :on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test for Other Channels Tested During Outage in Progress Revised
References
2CAN119405, NUDOCS 9411300290
Download: ML20078L594 (2)
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LER-1994-001, Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3681994001R00 - NRC Website
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f November 21,1994 2CANI19405 i

U. S. Nuclear Regulatory Commission Document Control Desk i

Mail Station P1-137 l

Washington, DC 20555 i

Subject:

Arkansas Nuclear One - Unit 2 i

Docket No. 50-368 License No. NPF-6 Licensee Event Report 50-368/94-001-01 Gentlemen:

In accordance with 10CFR50.73(a)(2)(i)(B), enclosed is the subject report concerning excore nuclear instrumentation.

This supplement is being submitted to revise the commitment regarding the future post-maintenance testing method used to verify continuity of cable connectors.

i Very truly yours, b

AfC.W/i Dwight C. Mims Director, Licensing DCM/TFS/mmg enclosure 1

1 280024 9411300290 941121

'h",

PDR ADOCK 05000368 i

S PDR Ii i

U. S. NRC November 21,1994 2CANI19405 Page 2 cc:

Mr. Leonard J. Callan Regional Administrator i

U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 i

l Institute ofNuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 j

)

Licensee Event Report

Arkansas Nuclear

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		Reporting criterion
05000368/LER-1994-001-01, :on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test for Other Channels Tested During Outage in Progress Revised	on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test for Other Channels Tested During Outage in Progress Revised	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)(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) 10 CFR 50.73(a)(2)(viii)(B)
05000368/LER-1994-001, Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors	Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000313/LER-1994-001-03, :on 940201,inoperable Emergency Feedwater Sys Flowpath Occurred.Caused by Operators Inattention to Detail While Taking & Reviewing Logs.Operations Shift Mgt & Crew Meeting to Discuss Lessons Learned from Event	on 940201,inoperable Emergency Feedwater Sys Flowpath Occurred.Caused by Operators Inattention to Detail While Taking & Reviewing Logs.Operations Shift Mgt & Crew Meeting to Discuss Lessons Learned from Event	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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000368/LER-1994-001-04, :on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test Methods Enhanced	on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test Methods Enhanced	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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000368/LER-1994-002-04, :on 940422,steam-driven Emergency Feedwater Pump Remained Inoperable Longer than Allowed by Ts.Caused by Inadequate Spec of Replacement Valve Characteristics.Valve Replaced w/pre-mod Model	on 940422,steam-driven Emergency Feedwater Pump Remained Inoperable Longer than Allowed by Ts.Caused by Inadequate Spec of Replacement Valve Characteristics.Valve Replaced w/pre-mod Model	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000313/LER-1994-002-03, :on 940411,reactor Automatically Tripped.Caused by Over Voltage Condition.Power Restored to EFIC Channel of B & D by Opening Breaker for Channel & Allowing Protective Devices to Reset	on 940411,reactor Automatically Tripped.Caused by Over Voltage Condition.Power Restored to EFIC Channel of B & D by Opening Breaker for Channel & Allowing Protective Devices to Reset	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)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)
05000313/LER-1994-003-04, :on 941008,surveillance Testing of Some Engineered Safeguards Components Did Not Verify Operability as Required by Ts,Due to Procedural Deficiencies Resulting from Inadequate Definition of Testing Requirements	on 941008,surveillance Testing of Some Engineered Safeguards Components Did Not Verify Operability as Required by Ts,Due to Procedural Deficiencies Resulting from Inadequate Definition of Testing Requirements	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)
05000313/LER-1994-003, :on 941008,tested Surveillance of Some Engineered Safeguards Components Did Not Verify Operability as Required by TS Due to Procedural Deficiencies.Existing Testing Program Evaluated	on 941008,tested Surveillance of Some Engineered Safeguards Components Did Not Verify Operability as Required by TS Due to Procedural Deficiencies.Existing Testing Program Evaluated	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)(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)
05000368/LER-1994-003-03, :on 940824,discovered That Surveillance Testing of CEA Position Indication Not Performed as Required by TS Due to Personnel Error Associated W/Computer Software Change.Pms Software Revised	on 940824,discovered That Surveillance Testing of CEA Position Indication Not Performed as Required by TS Due to Personnel Error Associated W/Computer Software Change.Pms Software Revised	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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000313/LER-1994-004-04, :on 940804,ANO Sys Engineering Personnel Determined That Functional Test Procedure for Reactor Bldg H Analyzers Was Not Adequate to Alert Personnel of Blocked Analyzer Outlet Flowpath Due to Personnel Oversight	on 940804,ANO Sys Engineering Personnel Determined That Functional Test Procedure for Reactor Bldg H Analyzers Was Not Adequate to Alert Personnel of Blocked Analyzer Outlet Flowpath Due to Personnel Oversight	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)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000368/LER-1994-004-03, :on 941007,surveillance Testing of One HP SI Pump Did Not Verify Operability as Required by TS Due to Procedure Deficiencies.Individuals from Several Sites Reviewed All 4160V SR Schemes	on 941007,surveillance Testing of One HP SI Pump Did Not Verify Operability as Required by TS Due to Procedure Deficiencies.Individuals from Several Sites Reviewed All 4160V SR Schemes	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)
05000368/LER-1994-005-03, :on 941121,ANO I&C Technician Inadvertently Reset Variable Setpoint for a Channel of Low SG Pressure Trip,Causing Setpoints Below Min Allowed by Ts.Caused by Personnel Error.Crew Briefed on self-checking	on 941121,ANO I&C Technician Inadvertently Reset Variable Setpoint for a Channel of Low SG Pressure Trip,Causing Setpoints Below Min Allowed by Ts.Caused by Personnel Error.Crew Briefed on self-checking	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)(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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(8)

05000368/LER-1994-001, Forwards Rev 1 to LER 94-001 Re Excore Nuclear Instrumentation.Rev Revises Commitment Re Future post-maint Testing Method Used to Verify Continuity of Cable Connectors

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