ML20087L571

AO 76-3:during Refueling Outage from 751116-760108,nine Valves Exhibited Leak Rate in Excess of 2000 Cc/Minute. Caused by Loose Body to Bonnet Joint.Bolting Tightened

ML20087L571
Person / Time
Site:	Point Beach
Issue date:	02/02/1976
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:	Rusche B Office of Nuclear Reactor Regulation
Shared Package
ML20087L573	List: ML20087L571 ML20087L577 ML20087L593
References
AO-50-266-76-3, NUDOCS 8403270277
Download: ML20087L571 (3)

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Wisconsin Electncrowcacouraur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 1

February 2, 1976 IEFILE COPY ,. [

l Mr. Benard C. Rusche, Director C ^

i Office of Nuclear Reactor Regulation N_ 7/

i U. S. NUCLEAR REGULATORY COMMISSION - -

• Washington, D. C. 20555 -

Dear Mr. Rusche:

s, LICENSEE EVENT REPORT 50-266/76-3 POINT BEACH NUCLEAR PLANT LEAKAGE TESTS OF UNIT 1 CONTAINMENT ISOLATION VALVES DURING REFUELING OUTAGE TESTING This report follows an initial report to you~of i

May 3, 1974, in which we committed to filing an abnormal * "S occurrence on any valve which, when~first subjected to a local leak test of 60 psig (air) during refueling outages, exhibited a leak rate in excess of 2000 cc/ minute.

Nine valves fell into the above category during the Unit 1, Refueling 3 outage from November 16, 1975, to January 8, 1976. -

Each valve leak test which exceeded the above administrative limit during its leak test was reported to Mr. Dwane Boyd, Office of Inspection and Enforcement - Region ~

III, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of that valve failing its test.

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'2 The test performance of the nine valves is described on the attached table.

., Specific comments on each failure are as follows:

1. The body-to-bonnet bolted joint was found to be slightly open and the bolting was tightened.

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Mr. Benard C. Rusche February 2, 1976 2, 3, 4 , ~5 ,

6, 8, and 9. Dirt was found on the valve seats and

, general cleaning and in some cases lapping the seats and discs was performed.

7. The valve required adjustment to permit the valve plunger to bottom on the seat.

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Each of the above-reported valves is in series with

. a second containment isolation valve in that system. In each I case, the second isolation valve demonstrated an acceptable i

level of leak tightness. It is, therefore, not considered that the leakage of the above-reported valves constituted a potential hazard to the health and safety of the public.

A full report of the Type "B" and "C" tests conducted during the Unit 1 third refueling shutdown will be filed separately as required by Section V.B of 10 CFR 50, Appendix J, following the completion of the next containment Type "A" test, presently scheduled for 1977.

Very truly yours, sp ,

Exe utive Vice President Sol Burstein Attachment i

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Initial Final .

Leakage Date of Leakage Date of j Penetration Valve Piping System cc/ min Test cc/ min Test i 1. 9 2721 Reactor coolant drain tank and refueling 16,000 12-24-75 10 12-30-75 >

1 cavity drain .

2. 33A IA-33A Instrument air to containment 32,000 12-07-75 674 12-2

'j check l l

j 3. 33B IA-34A Instrument air to containment 13,000 12-07-75 350 12-22-75 check I 4. 33C Check Service air to containment 50,000 12-21-75 0 12-28-75 valve

- ; 5. 50 2045 "B" steam generator blowdown 2,000 12-08-75 2 12-23-75

- 6. X1 3200B Rll/R12 supply line 175,000 12-10-75 0 01-06-76

7. X2 3200A Rll/R12 return line 17,000 12-09-75 734 12-20-75

8. 15 755A Component cooling to "A" reactor coolant 10,000 11-29-75 17 12-08-75 l check pump -

i 9. 16 755B Component cooling to "B" reactor coolant >200,000* 11-29-75 454 12-09 check l

CCruld not measure with test rig.

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