ML20045D646

Forwards Summary Rept,Reactor Containment Bldg Ilrt,Point Beach Nuclear Plant,Unit 1,1993. Unit 1,Type a ILRT Conducted,Per 10CFR50,App J & Bechtel Corp Topical Rept BN-TOP-1.Summaries of Type B & C Leak Tests Also Included

ML20045D646
Person / Time
Site:	Point Beach
Issue date:	06/18/1993
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045D647	List: ML20045D646 ML20045D652
References
NRC93-076, NRC93-76, VPNPD-93-118, NUDOCS 9306290257
Download: ML20045D646 (2)

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Ui i Wisconsin 1 i Electnc POWER COMPANY f 231 W Michigan. PO Box 2046 M iwoukee. WI 53201 (414)221-2345 l VPNPD-93-118 i NRC-93-076 June 18, 1993 10 CFR 50, Appendix J

{ Document Control Desk '

U.S. NUCLEAR REGULATORY COMMISSION Mail Section P1-137 i f Washington, DC 20555 j

Dear Gentlemen:

i DOCKET 50-266 i j REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST POINT BEACH NUCLEAR PLANT, UNIT 1 i

In accordance with Section 15.4.4, " Containment Tests,"

i Specification I.D of the Point Beach Nuclear Plant Technical '

Specifications and Section V.B of 10 CFR 50 Appendix J, this technical report is submitted summarizing the Type A containment integrated leakage rate test conducted during our 1993 Unit 1

refueling outage. Also included are summaries of the results from j the Type B and C leak tests conducted subsequent to our 1990 Type A

., test. The Type B and C leak tests were performed during the refueling outages of March-May 1990, April-May.1991, and April-j June 1992. The 1993 Type A test was performed by Wisconsin Electric nith the assistance from Bechtel Power Corporation.

j 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-1 j

Wisconsin Electric and is.available for NRC review at Point Beach Nuclear Plant.

i l Our 1993, Unit 1, Type A integrated leak rate test was conducted in

accordance with 10 CFR 50,' Appendix J, Point Beach Nuclear Plant Operations Refueling Tests (ORT)-17, " Containment-Integrated Leak l f Rate Test, Unit 1," and Bechtel Corporation Topical Report I

(BN-TOP-1), " Testing Criteria for Integrated Leakage Rate Testing

, of Containment Structures for Nuclear Power Plants." Our Type B

'; and Type C penetration tests were conducted in accordance with 10 CFR 50, Appendix J, and various Point Beach Nuclear Plant operations Refueling Tests.

TYPE A TEST

SUMMARY

The as-found total. time leakage rate of the 1993 Type A test was e

0.094%/ day at the 95% upper confidence level. This is 44.3% of the operational leakage rate allowed by. Point Beach Nuclear Plan 3 9306290257 930618 -- I1 Ob i

f PDR P.

ADOCK 05000266' PDR h4 D

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Document Control Desk June 18, 1993 Page 2 Technical Specifications. The leakage rate reported includes a 0.009%/ day penalty for non-standard valve alignments, containment net free volume changes, and pressurized component additions to the containment.

TYPE B AND C TEST SUMMARIES The total as-found leakage of the Type B and C tests conducted during the 1990 refueling outage was 16,383 standard cubic centimeters per minute (sccm) or 7% of 0.6L. After repairs, the overall leakage rate was 7,904 sccm or 3% of 0.6L, (0.6L, is 60% of the maximum allowable leakage as allowed by Point Beach Nuclear Plant Technical Specifications).

The total as-fotnd leakage of the Type B and C tests conducted during the 1991 refueling outage was 233,924 seem which exceeded 0.6L, (LER 91-003, PBNP Unit 1). After repairs, the overall leakage rate was 8,985 scem or 4% of 0.6L,.

The total as-found leakage of the Type B and C tests conducted during the 1992 refueling outage was 9,197 sccm or 4% of 0.6L,.

After repairs, the overall leakage rate was 5,165 sccm or 2%

of 0.6L,.

l The results of all Type A, Type B, and Type C tests performed subsequent to our 1990 Unit 1 outage, are within the requirements of Point Beach Plant Technical Specifications and Section III of 10 CFR 50, Appendix J, with the exception of the total as-found leakage of the Type B and C tests conducted during the 1991 refueling outage noted above. A brief summary of LER 91-003 is provided in Section 9.0 of this report.

If you have any questions concerning this report or rnquire additional information, please feel free to contact us.

Sincerely, q

' Bob Link Vice President Nuclear Power DMC/akf Enclosures cc: NRC Regional Administrator, Region III NRC Resident Inspector ,

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