ML20043C900

LER 90-009-00:on 900507,determined That Tech Spec 4.6.1.1 Requirements Not Met After Performing Monthly Periodic Test 2.2.4a.Caused by Inadequate Procedure.Recommended Procedure Revs to Prevent Recurrence Being evaluated.W/900601 Ltr

ML20043C900
Person / Time
Site:	Brunswick
Issue date:	06/01/1990
From:	Harness J, Harris T CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-0416, BSEP-90-416, LER-90-009-01, LER-90-9-1, NUDOCS 9006060321
Download: ML20043C900 (2)

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Carolina Power & Light Company BrunswickNucfearf'ro]ect P. O. Box 10429 Southport, N.C. 28461 0429

<- June 1, 1990 FILE: B09 13510C 10CFR50.73 STRIAL: BSEP/90 0416 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 )

DOCKET NO. 50 324 LICENSE NO. DPR 62-LICENSEE EVENT REPORT 1 90-009 Gentlemon:

In accordance with Title 10 of the Code of Federal Regulations, the enclosed-Licensee Event Report is submitted. This re ort fulfills the requirement for a written report within thirty (30) days o a reportable occurrence - and is i submitted in accordance with the format set forth in NUREG 1022, September 1983.  !

Very truly yours, t, Lar w J . L. Ilarness, General Manager i Brunswick Nuclear Project Til/ j Enclosure l cc: Mr. S. D. Ebneter a' Mr. N. B. Le BSEP NRC Resident Office I

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j NRC FORM 306 , U.S. NUCLEAR REOULATORY COMMISSION AIPROVED OMB NO. 31504104 EX81RES 4/33,02 e ESTIMATED BURDEN PER RESK)NSE TO COMPLY WITH 1HiS INFORMATION COLLECTION REQUEST:50.0 HRS. FORWARD E "

, UCENSEE EVENT REPORT (LER) C*"ng,5 co s MM y,%Rtu,%,is*,l3333, U.S. NUOLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAtYRWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILffY NAME (1) DOCKET NUMBER (2) 8 ADE (3)

Brunswick Steam Electric Plant Unit 1 ,ppi,pppp , , or g , ,

TITLE (4)

Required Surveillance Not Performed on 1/2 E11 F103A ami 1/2 E11 F1038 PCIS Valves EVENT DATE (5) LfR NUMBER (6) REPORT DATE (7) OTHER FACtUTIES INVOLVED (8) i MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACluTY NAMES DOCKET NUMDERIS)

NUMBER NUMBER gry ng wic k U ngt g 0l5l0l0l0 l3 l2 l4 0l$ 0l7 9l0 9l0 0l0l0 Ojo 0l6 0l1 9l0 0lSl0l0l0 l l l CPERATINO THIS REPORT is SUBMITTED PURSUANT TO THE HEOUIREMENTS OF 10CFR$: (CHECK ONE OR MORE OF THE FOU.OWING) (11)

MODE (9) l 1 FOWER ,,,,,,, 20.402(b) ,,,,_, 20.405(c) _, 50.73(a)(2)(lv) _ 73.71(b)

LEVEL ,,,,,,_ 20.405(a)(1)(1) ,,,,,,, 50.36(c)(1) ,,,,,,_ 50.73(a)(2)(v) ,,_,,,, 73.71(c) i (10) 1 l0 l0 20.405(a)(1)(II) _ 50.36(c)(2) ,,,,,,,, 50.73(a)(2)(vP) ,,_,,,, OTHER (SPECIFY IN l

, 20.405(a)(1)(ill) ,,X,,l 50.73(a)(2)(1) ,,,,,,, 50.73(a)(2)(v61)(A) ABSTRACT BELOW i ,,,,,,,, 20.405(a)(1)(lv) ,,,,,,, 50.73(a)(2)(U) ,,,,,,_ 50.73(a)(2)(vill)(B) AND IN TEXT, NRC l

,,,,, 20.405(a)(1)(V) ,,,,,,,, 50.73(s)(2)(lii) .,,,,,, 50.73(a)(2)(u) FORM 366A)

I I UcENSEE CONTACT FOR THl$ LER (12) )

NAME TElfPHONE NUMBER Tcny Harris, Regulatory Compliance Specialist ,ng, cog, 9l1l9 4l5l7l-l2l0l3j6 COMPLETE ONE UNE FOR CACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC- REFORTABLE CAUSC SYSTEM COMFONENT MANUFAC- REPORTABLE TURER TO NPROS TURER TO NPROS I Iil i ll i III Ill i IIi llI I IIl 11I

' $UPPLEMENTAL REPORT EXPECTED 04) EXPECTED MONTH DAY YEAR f SUBMIS$10N X l YES (1F YES. COMPLETE EXPECTED SUBMISSION DATE) l40 DATE (15) 0l7 3l1 9l0 ABSTRACT (Umit to 1400 spaces,l.a.,approximately fif*een sangte space typewritten lines) (16)

On May 7,1990, while pethrming monthly Periodic Test (PT) 2.2.4a, it was determined that the requirements of Technical Specification (TS) 4.6.1.1 were not met. Specifically, Unit 1 and Unit 2 Residual Heat Removal (RHR)

Primary Containment Isolation (PCIS) valves E11 F103A/B were not verified to be in the closed position during pts performed on 3/20/90 and 4/20/90, per the requirements of TS 4.6.1.1. The valves had been placed under clearance in the closed position with their respective breakers off on 2/14/90.

A Human Performance Evaluation is being completed on this event. The initial evaluation has determined the cause of i the error to be the result of an inadequate procedure. Recommended procedure revisions to prevent recurrence of this ,

l event are currently being evaluated. Results of this evaluation will be included in a supplement to this LER. The supplement will be issued by 7/31/90. The safety significance of this event is considered minimal, since the valves were under clearance in the closed position during the entire period of missed survelHances.

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