05000237/LER-1981-005, Forwards Updated LER 81-005/03X-L.Deviation Rept Encl

Forwards Updated LER 81-005/03X-L.Deviation Rept Encl

ML20009C056
Person / Time
Site:	Dresden
Issue date:	06/16/1981
From:	Scott D COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20009C057	List: 05000237/LER-1981-005, Forwards Updated LER 81-005/03X-L.Deviation Rept Encl 05000237/LER-1981-005-03, During Local Leak Rate Testing,Measured Leakage of Single Isolation Valve Exceeded Tech Specs.Caused by Normal Deterioration of Valve Seat. Valve Replaced
References
81-409, NUDOCS 8107200226
Download: ML20009C056 (2)

LER-1981-005, Forwards Updated LER 81-005/03X-L.Deviation Rept Encl

Event date:
Report date:
2371981005R00 - NRC Website

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\\/,N.,]I] IQ' James G. Keppler, Regional Director M/

Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatary Commission 799 Roosevelt Road Glen Ellyn, IL 60137 i.

Reportable Occurrence Report #81-05/03X-1, Docket #050-237 is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2. (b), conditions leading to operation in a degraded mode permitted by a limiting condition for operation. The reason for the revision is to update the cause de-scription and corrective actions taken and future action portions of the Licensee Event Report.

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Enclosure cc: Director of Inspection & Enforcement I

Director of Management Information & Program Control U.S. NRC, Document Mgt. Branch File /NRC Jhs

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DEVIAT10N REPORT

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Commonwealth Etiisan su UNIT YEAR NO.

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17 Il T l TLE O F CEVIATICN CCCU RRED l-17 91 1100 Failure of 2-1601-23 Valve to Pass LLRT am we SYSTEM AFFECTED 1600 PLANT CON 0iTIONS TESTING L_J Pressure Suppression uccEShutdown zwp e w-i 0

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YES NO CESCRIPTICN CF iVENT During LLRT of Drywell and torus vent, 2-1601-23 valve failed to hold pressure. Leak Rate i

determined to be 1715.55 SCFH DESCRIPTION CF CAUSE Unknown at this time OTHER APPLICABLE INFORMATION Reactor in cold shutdown Primary Containment not required.

EOUlPMENT C YES OR NO.

'WR NO.

FAlt,URE i

(NO N/A Dll279 K. R. Zirwas 1_17_gi PART 2 ) OPERATING ENGINEERS CCMMENTS The measured leakage exceeded the limit for a single isolation valve (29 38 SCFH. T.S. 4.7.A).

? leakage was determined to be through the 2-1601-23 valve toward the drvwell.

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TYPE OF CEVI ATION EVENT OF POTENTI AL TECH SPEC l NCN-REPORTABLE ANNUAL RELATED REPORTABLE OCCURRENCE PUBLIC INTEREST v!OLATION OCCURRENCE REPCRTING WR ISCUED i

f 10CFR21

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~ l X l 30 C AY hTICN NO NO l

RE?ORTABLE CCCUPRENCE ACTICN ITEM NO.

P9CMPT CN-SI TE NOTI FI CATICN l

NUMBER R. M. Ragan 1/22/81 1200 Xti5 81-05/03X-1 Tl RE CATE ME TI TLE CATE TIME l

24-HOUR NRC NOTI FI CATION I RCMPT OFF-SI TE NOTI FICATION

'PH N/A F. A. Palmer 1/22/81 1:33 REG ON lli OATE lME TI TLE DATE TIME TGM N/A REGIGN III a CCL CATE TIME Tl TLE CATE TIME RESPCNSI SLE COM' ANY O FFI CER INF0P9ED OF 10 CFR 21 "Nor-icNs 2NO wrio occ0=* 'O Not T I TL E CATE

'W REvi Ew AND COMPLETED. John W. Wuici,a 1/20/81 CP E R AT I NG iNG I N t-H CATE ACCE?TANCE SY STATICN REVfEW

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