05000249/LER-1980-007, Forwards LER 80-007/03L-0

Forwards LER 80-007/03L-0

ML17192A581
Person / Time
Site:	Dresden
Issue date:	03/12/1980
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17192A582	List: 05000249/LER-1980-007, Forwards LER 80-007/03L-0 05000249/LER-1980-007-03, /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats
References
80-205, NUDOCS 8003190551
Download: ML17192A581 (2)

LER-1980-007, Forwards LER 80-007/03L-0

Event date:
Report date:
2491980007R00 - NRC Website

text

Commonweal.di son Dresden Nuclear Po.,;.,er Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR 1180-205 James G. Keppler, Regional Director March 12, 1980 Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commissiqn 799 Roosevelt Road Glen Ellyn, IL 60137

• ~

Reportable Occurrence Report #80-7/03L-0,Docket #050-249, is being submitted to your office in accordance with Dresden Nuclear Power.

Station Technical Specification 6.6.B.2.(d), abnormal degradation of systems other than those specified in item B.l.e: above designed to contain radioactive material-resulting from the fission process.

Through discussions with the resident NRC inspectors from your office, an.extension until March 14, 1980~ in submitting this LER was ob-*

tained until equipment was made available in order to complete our investigation of the event.

BBS/leg.

Enclosure tep son*

Station Superintendent Dresden Nuclear Power Station cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRG

RC FORM 366

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.ENSEE EVENT REPORT e

CONTRoL"ITT:.0-cK~ l I ! J Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!

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l"r I L I D IR Is I 3 101 o I o I - I 9

LICENSEE CODE 14 15

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s o I o *1 o I o J o I - I o I o 101 4 11 11 11 I i 101 I I 0 LICEl\\:SE NUMBER 25 26 LICENSE TY?E 30 57 CAT 58 ON'T

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60 61 DOCKET NUMBER 6S 69 EVENT DATE 74 75 REPORT DATE 80

~--EVENT DESCRIPTION Ar:fD PROBABLE CONSEQUENCES@

l)T21 I During local leak rate test of the containment vent line, the measured leakage was J~

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lCIIJ I 1,990 SCFH which is in excess of the Tech Spec. limit for a single containment isolatiory l~ I valve (29. 38 SCFH).

Upon investigation A0-3-1601:--23 was found leaking through.

No jO}] I leakage was detected at the other boundary :Valves. This event was of minimal safety [ID I significance because all leakage was contained in the vent line and was into the dry-

[:TI] I well.

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Similar events

50-237/76-10,79-017 & 50-249/76-16.

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8 9 80 till 8

SYSTEM CODE Is ID I@

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0. LE R/RO CV ENT YEAR

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REPORT I 8 I 0 I NUMBER 21 22

CAUSE

CAUSE CODE SUBCODE COMPONENT CODE lEJ@ l!J@ Iv I A IL Iv IE 1x 18 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO.

CODE I 0 I 0 I 7 J I/]

J 0 13 I 23 24 26 27 28 29 COMP.

SUBCODE L!J@

19 REF'ORT TYPE L!:J 30 VALVE SUBCODE

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20 31 PRIME COMP.

TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED NPRD-4 FORM SUB.

SUPPL! ER REVISION NO.

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32 COMPONENT MANUFACTURER ACTION FUTURE EFFECT SHUTDOWN

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3 3 34 35 36 3 7 4 0 4 1

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

42 43 44 47 I A0-3-1601-23 was replaced and the vent line retested.

The leakage was 8.71 SCFH.

AO-3-1601-23 is a 18 11 rubber seated butterfly valve, model No. 2FII.

Leakage was due to trIJ I normal expected wear of the.rubber seats.

No further correctiv.e. action is deemed

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tm till necessary.

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1Q 12 11 ACTIVITY CONTENT r:;-;;,,

RELED.SED OF RELEASE AMOUNT OF ACTIVITY ~

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10 11 44 44 PERSONNEL EXPOSURES r:;;:::,.

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11 12 cOSS OF OR DD.MAGE TO FACILITY 143\\

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