ML20236D377
| ML20236D377 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/22/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236D380 | List: |
| References | |
| CON-NRC-87-76 VPNPD-87-319, NUDOCS 8707300429 | |
| Download: ML20236D377 (2) | |
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WISCONSIN Electnc mm coumr 231 W. MICHIGAN P.O. BOX 2046, MILWAUKEE,Wl53201 (414)277-2345 VPNPD-87-319-NRC-87-76 July 22, 1987
-Document ~ Control Desk U.S.
NUCLEAR REGULATORY COMMISSION Washington, D.C.
20555' Gentlemen:
DOCKET.50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE DPR-24 REACTOR < CONTAO4 MENT BUILDING INTEGRATED LEAK RATE TEST In accordance with Section 15.4.4.I.D. of the Point Beach Nuclear' Plant Technical Specifications and Section V.B.
of 10 CFR150 Appendix J, a summary technical report on the Type A containment integrated leakage rate-test conducted during the 5
April 1987 Unit I refueling and maintenance outage'is enclosed.
The results of the Type B and Type C leakage tests conducted since the April 1984 Type A test are included.
1 The Type A test was performed by Bechtel Power Corporation; the report was reviewed and approved by Wisconsin Electric.
The complete report, including all procedures,. equipment calibration J
records, test data, and results, is available at Point Beach for review.
A summary report,' prepared in accordance with ANSI /ANS-l 56.8-1981, is enclosed herewith.
A routine, announced NRC inspection was conducted by Mr. R.
'Mendez during the performance of the Type A test.
No items of i
non-compliance or deviations were identified in Inspection Report No. 50-266/87008; 50-301/87008, dated April 29, 1987.
The overall, as-found, total time leakage rate for this Type A test was 0.297%/ day at the 95% upper confidence level.
This value includes a 0.010%/ day correction for non-standard valve alignments, containment volume changes, gas additions to the containment, and a penalty of 0.155%/ day for the packing leakage from four. steam generator level transmitter isolation valves that were leak-tested and replaced with new valves prior to the B707300429 B70722 fDl k
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Nuclear Regulatory Commission July 22,-1987 Page Two l
l Type A test.
They are not containment isolation valves but are j
part of the containment boundary.
The new valves were included l
in the Type A test boundary.
As a result of adding in the l
penalty for these valves, the calculated leak rate for the as-found condition exceeds the allowable operational leak rate of'0.212%/ day.
This was reported in Licensee Event Report (LER)
No. 87-002-00, dated May 6, 1987.
The overall, as-left, total time leakage rate for this Type A I
test was 0.142%/ day at the 95% upper confidence level, i.e.,-
l 67.0% of the allowable operational leakage rate.
This includes a 0.010%/ day correction for r on -standard valve alignments, containment volume changes, end gas additions to the containment.
leakage of the Type B and C tests The overall, as-found...985 refueling outage was 27,967 secm or conducted during the 11.7% of 0.6L After repairs, the overall, as-left, leakage rate was 11,138 Lecm or 4.7% of 0.6L a*
The overall, as-found, leakage of the. Type B and C tests l
conducted during the 1986 refueling outage was greater than 164,420 seem or greater than 68.6% of 0.6L As described in LER No. 86-002-00, dated May 16, 1986, 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 12,711 sccm or 5.3% of 0.6La*
If you have any questions concerning this report, please feel free to contact us.
Very truly yours,
/
lW- "g C.
W.
Fay Vice President Nuclear Power Enclosure Copies to Regional Administrator, Region III Resident Inspector