ML20005E230

Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 2, Summary Rept,Per 10CFR50,App J.Type A,B & C Leak Test Results Provided

ML20005E230
Person / Time
Site:	Point Beach
Issue date:	12/21/1989
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20005E231	List: ML20005E230 ML20005E235
References
CON-NRC-89-166 VPNPD-89-674, NUDOCS 9001040127
Download: ML20005E230 (2)

Text

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Electnc POWER COMPANY E 231 W Michgon, PO. Box 204$. Mdwovkw WI 53201 (414)221 2345 VPNPD 67 4 NRC' -

89- 166 December. 21,11989 10 CPR 50, Appendix J Document Control Desk-1U. S.. NUCLEAR-REGULATORY COMMISSION MailLStation P1-137

-Washington,-D.C.- 20555

,. Gentlemen:

DOCKET 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2

. FACILITY OPERATING LICENSE DPR-27

. REACTOR CONTAINMENT BUILDING-INTEGRATED LEAK RATE TEST Irr accordance -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 reports are submitted on the Type A containment integrated leakage. rate test conducted during the 1989 Unit 2 refueling shut-down. . Also included are a summary of the results from the Type B andLC' leak tests conducted since the last Type A test. These were performed during the: refueling shut-downs of' September-November 1986, October-November 1987, and-October-November 1988. The Type A test was performed by Wisconsin Electric with assistance 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 all procedures, equipment calibrations, 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 total time leakage rate of this Type A test was 0.ll6%/ day at the 95% upper confidence level. This is 58% of the allowable operational leakage rate. The leakage rate reported includes a.0.001%/ day penalty for non-standard valve alignments, containment volume changes, and air additions to the containment.

b The total as-found leakage of the Type B and C tests conducted during the 1986 refueling outage was greater than 198,901 standard cubic centimeters per minute (sccm), or greater than 86% of 0.6L a*

9001040127 891221 PDR ADOCK 05000301 [ON P PDC i (

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• Page'27 F :As described'further-in LER No. 86-005-00,- dated-October 131,.1986-

.-and:LER-No. 86-005-01,- dated February _.9, 1987, the. actual value G. Lcould not be_: quantified because excessive leakage duringftwo 7

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separate. Type C tests.made it impossible to achieve: test pressure.. <

.However, after; repairs,.-the overall as-left leakage rate was 14,840 .

': , scem, or'6%-of 0.6Lg.

I iThe overall'as-found leakageoof;the Type-B and.C tests' conducted

,' during:the-1987' refueling outage was?32,554 sccm or 14% of 0.6L

.e After repairs, the overall leakage rate was 12,115 scem or 5%?of, 0.6Lf.

Theloverall as-found leakage of the Type B and Citests conducted during the'1988 refueling outage was 23,364 secm or 10% of 0.6L After repairs, the overall leakage-rate was 13,736 scem or 6% of,

0.6Lf.

If.you have any questionstconcerning-this report, please feel 1 free to contact us.-

'Veryltruly, o u r s ,---

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..C. W.EFay.

Vice President Nuclear Power.

. Enclosures Copiesito NRC Regional l Administrator,. Region III

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NRC Resident? Inspector

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