05000413/LER-1997-011, Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public

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Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public
Person / Time
ML20202B223
Site:	Catawba
Issue date:	01/29/1998
From:	Gordon Peterson DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20202B227	List: 05000413/LER-1997-011, Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public 05000413/LER-1997-011-02, :on 971230,operators Indentified RCS Leak. Caused by Leakage Through Two Drain Valves,Tightly Closed. Leaking Valves Located & Closed
References
NUDOCS 9802110148
Download: ML20202B223 (1)
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LER-1997-011, Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public

Event date:
Report date:
4131997011R00 - NRC Website
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York, $C 29745 Guy R. Prsetoon (803) 8314231 Ornct

\\ke h nident (403) 8313426ux January 29,1998 U.S. Nuclear Rel; statory Commission Docurnent Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station Docket No. 50-413 LER 413/97-011 Gentlemen:

Attacher 1 is Licensee Event Report 413/97-011 concoming ESF Actuation due to Reactor Coolant System Leakage from Loop Drain Valves.

This event is considered to be of no significance with respect to the health and safety of the public.

Sinc W FM Da eterson Attachment cc:

Mr. Luis Raies INPO Records C9nter Regicral Administrator, Region ll 700 Galleria Place.

.f U.S. Nuclear Regulatory Commission Atlanta, G A 30339-5957 61 Forsyth Street, S.W., Suite 23T85 Atlanta, GA 30303 Mr. P. S. Tam Marsh & McLennan Inc.

g[ g U.S. Nuclear Regulatory Comn'.ission Mr. Kenneth W. Gannaway Mall Stop O-14 h25 100 N. Tryon Street 11555 Rockville Pike Charlotte, NC 28202 s

Rockville, MD 20852 2738 j..

Mr. Darrell Roberts NRC_Retident inspector Catawba Nuclear Sta'Jon 3iUO2O 990'2110148 990129 PDR ADOCK 05000413 S.

Licensee Event Report

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		Reporting criterion
05000414/LER-1997-001, :on 970103,maint Found Nitrogen Supply Isolation Valves for Power Operated Relief Valve (PORV) 2SV-1 Closed.Caused by Poor Work Practices.Nitrogen Isolation Valves for 2SV-1 & 2SV-13 Opened	on 970103,maint Found Nitrogen Supply Isolation Valves for Power Operated Relief Valve (PORV) 2SV-1 Closed.Caused by Poor Work Practices.Nitrogen Isolation Valves for 2SV-1 & 2SV-13 Opened
05000413/LER-1997-001-02, :on 970210,unanalyzed Postulated Single Failure Affected SG Tube Rupture Analysis.Caused by Less than Adequate Single Failure Analysis of SG Porv.Proposed Amend to TS 3/4.7.1.6 & UFSAR Has Been Submitted	on 970210,unanalyzed Postulated Single Failure Affected SG Tube Rupture Analysis.Caused by Less than Adequate Single Failure Analysis of SG Porv.Proposed Amend to TS 3/4.7.1.6 & UFSAR Has Been Submitted	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)
05000414/LER-1997-002, :on 970107,new Incore Fission Detector Was Installed in Unit 2 Reactor & 43 Days Had Elapsed Since Last Survey.Caused by Inadequate Procedural Guidance.Procedure Revised	on 970107,new Incore Fission Detector Was Installed in Unit 2 Reactor & 43 Days Had Elapsed Since Last Survey.Caused by Inadequate Procedural Guidance.Procedure Revised
05000414/LER-1997-002-02, Has Been Cancelled	Has Been Cancelled
05000413/LER-1997-002-04, :on 970403,determined That Feedwater Containment Isolation Valve Was Inoperable.Caused by Inadequate Info.Nitrogen Pressure Was Restored & Oac Alarm Response Has Been Revised	on 970403,determined That Feedwater Containment Isolation Valve Was Inoperable.Caused by Inadequate Info.Nitrogen Pressure Was Restored & Oac Alarm Response Has Been Revised	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)(B)
05000414/LER-1997-003-01, :on 970217,component Cooling Sys Unavailability Was Caused by Failure of Breaker Charging Springs Motor Coils When Breaker Was Closed on 970125.Failed Breaker Was Replaced W/Refurbished Spare Breaker	on 970217,component Cooling Sys Unavailability Was Caused by Failure of Breaker Charging Springs Motor Coils When Breaker Was Closed on 970125.Failed Breaker Was Replaced W/Refurbished Spare Breaker	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000413/LER-1997-003-04, :on 970515,AFW Sys Was Found Outside of Design Basis.Caused by Unanticipated Interaction of Systems or Components.Cacst Was Isolated Pending Further Evaluation on 970515	on 970515,AFW Sys Was Found Outside of Design Basis.Caused by Unanticipated Interaction of Systems or Components.Cacst Was Isolated Pending Further Evaluation on 970515	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)(1)
05000413/LER-1997-004-02, :on 970514,inadequate Surveillance Determined. Caused by Interpretation of Conflicting TS Requirements. Station Procedures Revised to Ensure TS Surveillance 4.5.3.2 Is Met	on 970514,inadequate Surveillance Determined. Caused by Interpretation of Conflicting TS Requirements. Station Procedures Revised to Ensure TS Surveillance 4.5.3.2 Is Met	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000414/LER-1997-004-03, :on 970424,inadequate Test of Containment Isolation Valve Identified.Caused by Inadequate Work Practices.Personnel Involved Counseled Re Improved Performance	on 970424,inadequate Test of Containment Isolation Valve Identified.Caused by Inadequate Work Practices.Personnel Involved Counseled Re Improved Performance
05000414/LER-1997-005-02, :on 970626,automatic Reactor Trip Occurred While in Mode 1.Caused by Equipment Failure of Cutler-Hammer E30JY5 Close/Trip Push Button Switch.Maint & Engineering Found & Replaced Defective Switch	on 970626,automatic Reactor Trip Occurred While in Mode 1.Caused by Equipment Failure of Cutler-Hammer E30JY5 Close/Trip Push Button Switch.Maint & Engineering Found & Replaced Defective Switch	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000413/LER-1997-005-01, :on 970623,violation of TS 4.0.5 Was Determined.Caused by Inadequate Surveillance Procedure. Affected Check Valves Were Successfully Tested for Reverse Flow Prevention	on 970623,violation of TS 4.0.5 Was Determined.Caused by Inadequate Surveillance Procedure. Affected Check Valves Were Successfully Tested for Reverse Flow Prevention	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000413/LER-1997-006-03, :on 970804,discovered Missed TS Surveillance on P-11 P-13 Permissive Interlocks.Caused by Inadequate Procedures.Tested Subject Interlocks Successfully & Revised Analog Channel Operational Test Procedures	on 970804,discovered Missed TS Surveillance on P-11 P-13 Permissive Interlocks.Caused by Inadequate Procedures.Tested Subject Interlocks Successfully & Revised Analog Channel Operational Test Procedures
05000414/LER-1997-006-02, :on 970726,manual Reactor Trips Occurred Due to Closure of MSIV 2SM-1.Caused by Failure of Digital Optical Isolator (Doi) within Control Circuitry of MSIV 2SM-1. Replaced Failed Dois & Improved Doi Testing	on 970726,manual Reactor Trips Occurred Due to Closure of MSIV 2SM-1.Caused by Failure of Digital Optical Isolator (Doi) within Control Circuitry of MSIV 2SM-1. Replaced Failed Dois & Improved Doi Testing	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000413/LER-1997-007-03, :on 971023,TS 3.2.5 Was Inadequate for Reduced Flow Operation.Caused by Deficiency of Analysis.Ts Interpretation Was Issued That Prohibited Reduced Power Operation by TS Figure 3.2-1	on 971023,TS 3.2.5 Was Inadequate for Reduced Flow Operation.Caused by Deficiency of Analysis.Ts Interpretation Was Issued That Prohibited Reduced Power Operation by TS Figure 3.2-1
05000413/LER-1997-008-02, :on 971111,inadequate Solid State Protection Sys Surveillance Testing Occurred.Caused by Inadequate Test Design Supplied by Vendor.Surveillance Procedures for Solid State Protection Sys on Unit Revised	on 971111,inadequate Solid State Protection Sys Surveillance Testing Occurred.Caused by Inadequate Test Design Supplied by Vendor.Surveillance Procedures for Solid State Protection Sys on Unit Revised
05000413/LER-1997-008, Forwards LER 97-008-00 Re Inadequate Solid State Protection Sys Surveillance Testing.Event Considered to Be No Significance W/Respect to Health & Safety of Public	Forwards LER 97-008-00 Re Inadequate Solid State Protection Sys Surveillance Testing.Event Considered to Be No Significance W/Respect to Health & Safety of Public
05000413/LER-1997-009-01, Forwards LER 97-009-01 Re Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis.Event Considered to Be of No Significance W/Respect to Health & Safety of Public	Forwards LER 97-009-01 Re Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis.Event Considered to Be of No Significance W/Respect to Health & Safety of Public
05000413/LER-1997-010-02, :on 971229,reactor Trip Breakers Opened Due to Uncertainty of Rod Position.Caused by Failure of Detector/ Encoder Card in Data a Cabinet of Drpi Sys.Replaced Failed Detector/Encoder Card W/New Card	on 971229,reactor Trip Breakers Opened Due to Uncertainty of Rod Position.Caused by Failure of Detector/ Encoder Card in Data a Cabinet of Drpi Sys.Replaced Failed Detector/Encoder Card W/New Card
05000413/LER-1997-011, Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public	Forwards LER 97-011-00 Re ESF Actuation Due to RCS Leakage from Loop Drain Valves.Event Considered to Be of No Significance W/Respect to Health & Safety of Public
05000413/LER-1997-011-02, :on 971230,operators Indentified RCS Leak. Caused by Leakage Through Two Drain Valves,Tightly Closed. Leaking Valves Located & Closed	on 971230,operators Indentified RCS Leak. Caused by Leakage Through Two Drain Valves,Tightly Closed. Leaking Valves Located & Closed
05000413/LER-1997-012, :on 971231,determined That TS 3.3.2 Violated in Past History of Plant Due to Method of Performing Incore Thermocouple & RTD Cross Calibrs.Caused by Inadequate Process for Identifying Commitments.Instructions Provided	on 971231,determined That TS 3.3.2 Violated in Past History of Plant Due to Method of Performing Incore Thermocouple & RTD Cross Calibrs.Caused by Inadequate Process for Identifying Commitments.Instructions Provided

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