ML20039B257

LER 81-014/01T-1:on 811010,while Performing Refueling Leakage Tests of Containment Isolation valves,4-inch Check Valve in Svc Air Supply Found to Have Leakage Exceeding Tech Specs.Caused by Foreign Matl in Internals

ML20039B257
Person / Time
Site:	Point Beach
Issue date:	12/11/1981
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20039B253	List: ML20039B252 ML20039B257
References
LER-81-014-01T, LER-81-14-1T, NUDOCS 8112220465
Download: ML20039B257 (2)

Text

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I NRC FORM 366 ~ U.S. NUCLEAR REGULATORY COMMISSION 87 77)

LICENSEE EVENT REPORT

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7 8 69 75 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121 IWhile performing refueling leakage tests of containment isolation valves l g lon 10/10/81, one valve was found to have leakage such that the limit in l l0 l4 l lT . S. 15.4.4.III.B was exceeded. This 4" check valve (2-C) in the ser- l lOlsllvice air supply to containment Jeaked 145 1/ min. This valve is in series l l0Isllwith a second containment isolation valve which demonstrated an accept- l l 0 l 7 l lable level of leak-tightness. LER 79-003/0lT-0 is similar. This event l l O la il l s reportable in accordance with T. S. 15.6.9.2.A.3. l 7 8 9 80 DE CODE SU8C E COMPONENT CODE SU8 DE SU E 7

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]g 42 l N lg 43 l P l 3 l0 l 5 lg 44 47 CAUSE DESCRIPTlvN AND CORRECTIVE ACTIONS h lil0l[This 4" Wm. Powell Co. drawing 036032 check valve leaked through becausel i lof fcreign matter accumulations in the internals. The check valve was i li121l cleaned, reassembled and successfully retested. l i 3 ( l 1 i 141 l l 7 8 9 80 ST S  % POWER OTHER STATUS OtS O RY DISCOVERY DESCRIPTION i s [Hj@ l 0l 0 l 0l@l N/A l l C l@l Surveillance testing l ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE (1_[6_] [Zj @ lZ_j@l N/A l l N/A l 7 8 9 to 11 44 45 80 PER$ONNEL EXPOSURES NUMBER TYPE DFSCRIPTION l i l 7 l l 0 l 0 l 0' l@l Z l@l N/A i l

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s ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-014/0lT-0 Wisccasin Electric Power Company Point Beach Nuclear Plant, Unit 1 Docket No. 50-266 While performirg refueling leakage tests of containment isolation valves on October 10, one valve was found to have leakage such that the limit in Technical Specification 15.4.4.III.B was exceeded. The mani.facturer's nameplate data for the affected valve are as follows:

Plant Application: Service Air To Containment Plant Valve Number: 2-C Manufacturer: Wm. Powell Company Type: Swing Check Valve Pressure Rating: 150 psig Size: 4" Drawing Number: 036032 Foreign matter accumulated in the valve internals and prevented proper sealing of the check valve disc. The check valve was cleaned, reassembled, and successfully retested.

This valve is in series with a second containment isolation valve in the service air system. The second isolation valve demonstrated an acceptable level of leak-tightness.

Therefore, the leakage of the above-reported valve did not constitute a hazard to the health and safety of the public.

This event is reportable in accordance with Technical Specification 15.6.9.2.A.3, " Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment". The Resident Inspector was notified of this event.

All testing of Unit 1 containment isolation valves was concluded on December 4. This is the final report upon conclusion of testing.

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