ML20045D646
| 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: |
| References | |
| NRC93-076, NRC93-76, VPNPD-93-118, NUDOCS 9306290257 | |
| Download: ML20045D646 (2) | |
Text
l Ui l
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 Wisconsin Electric and is.available for NRC review at Point j
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 0.094%/ day at the 95% upper confidence level.
This is 44.3% of the e
operational leakage rate allowed by. Point Beach Nuclear Plan 3
9306290257 930618 --
I1 Ob i
PDR ADOCK 05000266' h4 s
f P.
PDR D
t g,
~~-
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
__..__