ML20055D442

Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 1,1990, Summary Rept

ML20055D442
Person / Time
Site:	Point Beach
Issue date:	07/03/1990
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20055D443	List: ML20055D442
References
CON-NRC-90-065, CON-NRC-90-65 VPNPD-90-312, NUDOCS 9007060307
Download: ML20055D442 (2)

Text

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' Electnc POWER COMPANY 231 w uctsm Ao tox 204i weoa w 53201 9u)22023e VPNPD-90-312 NRC-90-065 July 3, 1990 10 CFR 50, Appendix J Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 Washington, D. C. 20555 Gentlement DOCKET 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE DPR-20 REACTOR; CONTAINMENT BUII DING INTEGRATED LEAK RATE TEST InJaccordance with Section 15.4.4.I.D of the Point Beach Nuclear Plant Technical Specifications and Section V. B. of 10 CFR 50 Appendix J, the following summary technical report is submitted on the Type A containment integrated leakage rate test conducted during the 1990 Unit 1 refueling outage. Also included is a summary of the results from the type B and C leak tests conducted

,since the last Type A test. These were~ performed during the refueling outages of April-May 1987, April-May 1988, and April-May 1989. The type A test was performed by Wisconsin Electric with assistnce from Bechtel Power Corporation. We have enclosed a summary report prepared in accordance with the format specified in ANSI /ANS 56.8-1987. The complete documentation, which includes 2

-all procedures, equipmentzcalibrations, test data, and results will be retained by Wisconsin Electric and'is available for NRC review at the plant.

Summary of Data

'The overall as .found mass point leakage rate of this Type A test

-was 0.067%/ day at the 95% upper confidence level. This is 32% of the allowable operational leakage rate. The leakage rate reported included a 0.002%/ day penalty for non-standard valve alignments, valve modifications, containment volume changes, and air additions to the containment.

The total as-found leakage of the Type B and C tests conducted during the 1987 refueling outage was greater than 9,498 standard cubic centimeters per minute (sccm), or greater than 4% of 0.6La '

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' July 3,-1990 Page 2 As described further.in LER No. 87-003-00, dated May 20, 1987, the actual value could not be quantified because excessive leakage during one Type C test made it impossible to achieve test pressure. However, after repairs, the overall as-left leakage-rate was 8,236 sccm, or 3% of 0.6L a'

The total as-found leakage of the type B and C tests conducted during the 1988 refueling outage was a" eater than 60,723 scem, or greater than 25% of 0.6L . As described further in LER No.

88-004-00,. dated May 13,a1988, the actual value could not be quantified because excessive leakage during two separate Type C tests made it impossible to achieve test pressure. However, after repairs, the overall as-left leakage rate was 11,358 sccm, or 5%

of 0.6L a*

The total as-founo leakage of the Type B and C tests conducted during the 1989 refueling outage was greater than 20,943 scem, or g:: eater than 9% of 0.6L , As described further in LER No.

a 89-002-00, dated May 12 1989, the actual value could not be quantified because excessive leakage during one Type C test made it impossible to achieve test pressure. However, after repairs, the overall as-left leakage rate was 12,504 secm, or 5% of 0.6L

• a If you have any questions concerning Lois report, please feel free to contact us.

-Very trul' yours, d

C. W. .ay Vice President Nuclear. Power Enclosure Copies.to NRC Regional Administrator, Region III NRC Resident Inspector

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