ML20024J321

LER 94-006-00:on 940909,failure to Perform Slave Relay Test Associated W/One Containment Isolation Valve Due to Improper Work Practices.Reviewed All Slave Relay Test Procedures & Trained All Qualified reviewers.W/941005 Ltr

ML20024J321
Person / Time
Site:	McGuire
Issue date:	10/05/1994
From:	Rick Deese, Mcmeekin T DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-006-01, LER-94-6-1, NUDOCS 9410130272
Download: ML20024J321 (6)

Text

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ll l Duke Pouvr Company (704)675 4000 McGuire Nuclear Station 12700 llagers Ferry Road fluntersville. NC 28078-8985 i DUKEPOWER October 5, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station Unit 1 Docket No. 50-369

..% 4, ., License.e Event Report 369/94-0Fy,,, , , . . , n.

Problem Investigation Process No.: 1-M94-0959 Gentlemen:

Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Licensee Event Report 369/94-06 concerning a missed Technical Specification Surveillance Test. This report is being submitted in accordance with 10 CFR 50.73 (a) (2) (1). This event is considered to be of no significance with respect to the health and safety of the public.

Very truly yours, fht T.C. McMeekin y

jca Attachment xc: Mr. S.D. Ebneter INPO Records Center Administrator, Region II Suite 1500 U.S. Nuclear Regulatory Commission 1100 Circle 75 Parkway 101 Marietta St., NW, Suite 2900 Atlanta, GA 30339 Atlanta, GA 30323 Mr. Victor Nerses Mr. George Maxwell U.S. Nuclear Regulatory Commission NRC Resident Inspector Office of Nuclear Reactor Regulation McGuire Nuclear Station Washington, D.C. 20555 9410130272 941005 PDR ADOCK 05000369

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r bxc: B . L '. Walsh (EC11C)

'P.R. Herran (MG01VP)

R.C. Norcutt (MG01WC)

K.L. Crane (MG01RC)

B.F. Caldwell (MG01VP)

R.N. Casler (EC05N)

S.G. Benesole (ONO3RC) ,

G.H. Savage (EC06E)

G.B. Swindlehurst (EC11-0842) ,

M.S. Tuckman (EC07H)

R.F. Cole (EC05N)

D.B. Cook (EC13A)

G.A. Copp (EC050)

Tim Becker (PB02L) i J.I. Glenn (MG02ME)  !

P.M. Abraham (EC08I)

Zach Taylor (CN01RC)

Wilkie (ON05SR)

L.V.  !

D.P. Kimball (CN03SR)

NSRB Support Staff (EC05N) i

366 U.S. NUCLEAR REGULA*IORY CCNMISSION QC, APPROVF g N,0 pg0-0104 LICENSEE EVENT REPORT (LER) I N FACINITY NAME(1) h h"  %$ '

PACE (3)

McGuire Nuclear Station, Unit 1 05000 369 1 OF 4 TITLE (4)

Failure To Perform A Slave Relay Test Associated With one Containment Isolation Valve Due To Improper Work Practices.

EVWP DATE(5) LER NUMBER (6) REPORT DATE(7) CffTIER FACILITIES TNVOLvED(B)

MGMH DAY YEAR YEAR SEQUENTIAL REVISION HONTH DAY YEAR FACILtTY NAMES DOCKET NUMBERfS)

NUMBER NUMBER N/A 05000 09 09 94 94 06 0 10 09 94 05000 OPERATING 1 'lHIS REPORT TS SUBMITTED PURSUANT '!O RIOUTRFMrr8 OF 10CFR (Check one or more of the fo110winq1(11)

MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

PowzR 100% 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 20.405(a)(1)(11) 50.36(c)(2) 50.73(a)(2)(vii) ER 20.405(a)(1)(111) N X 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) , ,

20.405(a)(1)(iv) 50.73(a)(2)(11) 50.73(a)(2)(v111)(B) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICEN3EE COFFACT FDR THIS LER(12)

NAME TELEP9ONE NIMBER Ricky J. Deese, Manager, McGuire Safety Review Group AREA CODE 704 875-4065 CNFLE'TE ONE LINE FOR EACH COMPun mT FAILURE DESCRIHED IN T IIS REPOIrI'{ I 3 )

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC'IVRER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTE)(141 EXPECTED MONTH DAY YEAR SUBMISSION lYES (If yes, ccanplete EXPECTED SUBMISSION DATE) X lNO DATE(15)

ABS'ntACT (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten lines (16)

On August 10, 1994, at 0845, a staff member in the Operations Procedure group was preparing a procedure change for both Unit 1 and Unit 2 Slave Relay Test Procedures. While comparing the procedures, a discrepancy was noted. Further investigation revealed that the Steam Generator 1B, Blowdown Line Sample Inside Containment Isolation Valve, 1NM200B, was not included in the Unit 1 procedure. The staff member revised the procedure and had the slave relay test performed. The test verified that the valve would have operated as designed. The valve is normally closed. The slave relay associated wiMTis valve was pt!hedically tested as required; however, the contacts associated with valve 1NM200B were not verified operable.

The cause of this event is attributed to improper Work Practices due to the failure to identify an error made during a procedure revision. The valve was inadvertently omitted from the procedure during a revision in August, 1991. Corrective actions include a review of all Slave Relay Test procedures to assure all equipment is tested and con *' *ing training for all Qualified Reviewers. Unit 1 was in Mode 1, Power Operation, at 100% power, at the time of discovery.

NkC Form Job

LERFON'. 360A U.S. NUCLEAR REGULA'IDH7 COM4ISSICO APPROVED BY CMB NO. 3150-0104 EXPIRES 3/31/93 LICENSEE EVENT REPORT ESTIMATED BURDEN PER RESPONSE 'IO CCMPLY WITH THIS INFORMATION COLLECTION REQUEST 50.0 HRS. FORWARD (LER) TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO 'IHE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULA'IORY CCMMISSION, WASHING' ION, DC 20555-0001, AND

'IO THE PAPERWORK REDUCTION PRCVECT ( 3150-0104), OFFICE OF MANACPVEN AND MUSCPT. W W !TN N N DO 7050}.

FACILITY NAME(1) DOCKFT NUMBER (2) LER NUMBER (6) PAGE(3)

YEAR SEQUElfrIAL REVISION NUMBER NUMBER McGuire Nuclear Station, Unit 1 05000 369 94 06 0 2 OF 4

_=

EVALUATION:

Description of Event In August of 1991, Performance personnel made administrative changes to the Unit 1 Train B Slave Relay (EIIS RLY) Test procedure, PT/1/A/4200/28B. The reissue included updating the procedure to incorporate several minor changes that had been made to the procedure previously and made some extensive changes to the procedure format. During the process, the Steam Generator (EIIS SG) 1B, Blowdown [EIIS2WI] Line Sample (NM System) [EIIS:KN]

Inside Containment Isolation Valve (EIIS:ISV), 1NM200B was inadvertently omitted from the procedure. The procedure change was approved on September 10, 1991. Subsequent quarterly slave relay tests failed to include a continuity check of the contacts associated with valve INM200B.

On August 10, 1994, a staff member in the Operations Procedure group was preparing a change to all four slave relay test procedures associated with Unit 1 and 2, Train A and B. A discrepancy was found between the Unit 1 and Unit 2, Train A procedures.

Investigation revealed that the Unit 1 procedure did not include valve INM200B. The valve was declared inoperable and entered into the Technical Specification Action Item Log book.

Action was then immediately taken to revise the procedure and perform the slave relay test associated with valve INM200B. The test was performed successfully on August 10, 1994, confirming the contacts had been operable since the last test. Unit 1 was in Mode 1, Power Operation, at 100% power, at the time of discovery.

Conclusion fuemmmaa. 4 This event is assigned a cause of improper Work Practices. Both the individual making the change and the individual performing the Qualified Review of the revision failed to identify the valve being omitted. Discussions with them during this investigation did not reveal a cause for the oversignt; however, both agreed that the omission of valve 1NM200B was an error and should have been identified during their review. Corrective actions include a review of all four slave relay test procedures to assure all components actuated by the slave relays are included in the test procedures. Also, management will r eview this LER with all Qualified Reviewers emphasizing their responsibility to assure procedures are changed accurately.

A review of the Problem Investigation Process (PIP) data base for the past 24 months revealed 4 reportable events which involve the failure to perform a TS required

'LERFO N 326A U.S. NUrLEAR REGUIAMR7 Cole (ISSIC APPROVED BY OMB CD. 3130-0104

, EXPIRES 5/31/95 LICENSEE EVENT REPORT EST1 MATED DURDEN PER RESPONSE 10 COMPLY WITH TIUS

, INFORMATION COLLECTION REQUEST: 50.0 ERS. FORWARD (LER) TEXT CONTINUATION COtHENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION e AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULAIORY COMMISSION, WASHINGION, DC 20555-0001, AND e-To THE PAPEHWORK REDUCTION PROJECT (3150-0104), OFFICE nP MANAnntrNT AND m mnTP . W1MUTM&PMN DC 20901.

' FACILITY NAME(1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3)

YEAR SEQUENTIAL REVISION NUMBER NUMBER McGuire Nuclear Station, Unit 1 05000 369 94 06 0 3 OP 4 i

surveillance due to improper Work Practices. These events were documented on Licensee Event Reports 369/93-07, 370/94-01, 370/94-02, and 370/94-03. Even though these events '

involved groups other than the Performance / Operations Test Group, as well as different procedures, and different improper actions; missed TS Surveillance Tests are a recurring problem. Corrective Actions were specific to those events and even though they were put-in place after this event, they would not have prevented this event from occurring. An adverse trend involving missed TS sur' vel.llance Tests had been 's~nt@ed Into the' Fre'5aia ~ e base prior to this event. A self assessment of the TS Surveillance Testing program has been completed. Corrective Actions associated with the self assessment have been identified.

This event is not Nerlear Plant Reliability Program (NPRDS) reportable.

There were no personnel injuries, radiation overexposures, or uncontrolled releases of radioactive material resulting from this event.

CORRECTIVE ACTIONS:

Inunediate: 1) OpereLions personnel declared valve INM200B inoperable and listed it in the Technical Specification Action Item Log book.

2) Operations Procedure Group personnel revised PT/1/A/4200/28B to include valve INM200B.

3) Operations Test Group personnel tested the slave relay associated with INM200B.

Subsequent: 1) Operations Procedure Group personnel originated PIP l-M94-0959 to document the discrepancy and have it investigated.

2) Performance personnel and the Qualified Reviewer responsible for the August, 1991 procedure change have reviewed this event and understand the significance of the error that was made.

9 w e n , r- -

'LetFDM 366A U.S. I'UCLEAR REGUIJt!ORY COletISSIC3 ADPROVED BY 04B NO. 3150-0104 EXPIRES 5/31/95 LICENSEE EVENT REPORT ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS

• INFORMATION COLLECTION REQUESTS 50.0 HRS. FORWARD

• (LER) TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO THE INFolNATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY CCHMISSION, WASHINGTON, DC 20555-0001, AND e 20 THE PAPERWORK REDUCTION PRG7ECT (3150-0104), OFFICE OF MANACFMENT AND TP fSCFT . WAWTNOTON DO 70901.

FACILITY NAME(1) DOCKrf NUMBER (2) LER NUMBER (6'l PAGE(3)

YEAR SEQUENTIAL REVISION NUMBER NUMBER McGuire Nuclear Station, Unit 1 05000 369 94 06 0 4 OF 4 Planned: 1) Electrical System Engineering personnel will coordinate a review of all slave relay test procedures to assure all components actuated by the relay are included in the appropriate procedure.

2) Site Management personnel will review this LER with all Qualified responsibilit __ to _asnttre ' nmcadorn I

%, +w e . ^

- - - -Reviewers emphasizina m- - cm.the..ir.p changes are implemented accurately.

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M m .- ,W d SAFETY ANALYSIS:

This event had minimal safety significance. Valve 1NM200B is a one inch Kerotest valve.

The slave relay for this valve was successfully tested on August 10, 1994. This test verified that during the time period the slave relay test for this valve was not being performed, (September 10, 1991, through August 10, 1994) the contacts would have operated as required. Chemistry personnel stopped using the sample line associated with this valve ,

in March of 1989. Since that time the normal state for the valve has been the closed position. Since valve INM200B is a containment isolation valve, the required position for an Engineered Safety Features (ESP) actuation signal is closed. The valve has been  ;

successfully tested during the ESF test performed during refueling outages. In addition i I

to these tests, the master relays have been checked on a monthly basis verifying that the slave relay for this valve would receive a signal. The slave relay for valve INM200B has been checked on a quarterly basis. These checks included operability verification of the relay and all associated components except valve INM200B. i I

At no time were the health and safety of the public or plant personnel affected by this event.

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