ML20207E455

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Forwards Summary Rept:1986 Unit 2 Integrated Leakage Rate Test. Summary of Type B & C Tests Includes Test Data Obtained During & Between Each Refueling Outage
ML20207E455
Person / Time
Site: Point Beach 
Issue date: 12/29/1986
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20207E460 List:
References
CON-NRC-86-123 VPNPD-86-513, NUDOCS 8701020185
Download: ML20207E455 (2)


Text

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1 Msconsin Electnc mm coumr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 (414)277-2345 g

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-a VPNPD-86-513 2

NRC-86-123 5

December 29, 1986 3

3 m

Mr. H. R. Denton, Director i

Office _of Nuclear Reactor Regulation

{

U. S. NUCLEAR REGULATORY COMMISSION Washington D.

C.

20555

Dear Mr. Denton:

3 a

DOCKET 50-301

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POINT BEACH NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE DPR-27

SUMMARY

TECHNICAL REPORT OF TYPE A, B,

AND C CONTAINMENT LEAK TESTS

-4 In accordance with Section 15.4.4.I.D. of the Point Beach E

Nuclear Plant Technical Specifications and Section V. B.

of 10 2

CFR 50 Appendix J, the following summary technical reports are y

submitted on the Type A containment integrated leakage rate i

test conducted during the Sept. ember 1986 Unit 2 refueling i

shut-down.

Also included are the results of the Type B and C 3

leak tests conducted since the last Type A test.

These vere i

performed during the refueling shut-downs of April - May 1982, i

lj March - July 1983, September - December 1984, and October -

November 1985.

The Type A test was performed by the Bechtel Power Corporation for Wisconsin Electric.

We have reviewed and i

approved their report and have enclosed a summary report d

prepared in accordance with the format specified in ANSI /ANS

]

56.8 - 1981.

The complete report, which includes all 1

procectures, equipment calibrations, test data, and results will i

be retained by Wisconsin Electric and is available for NRC

?

review at the plant.

f 5

A routine, announced NRC inspection by Messrs.

F. Mauer and R.

]

Mendez was conducted during the performance of the Type "A" integrated leakage rate test.

No items of non-compliance or 5

deviations were identifed with the 1986 ILRT.

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1 8701020185 861229 PDR ADOCK 05000301 i

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. H. R. Denton-

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' December 29, 1986 R

Page'2 Summary of Data

'The overall as-found : total time leakage rate of this Type A

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test was 0.115%/ day at the 95% upper confidence level.

This is 57.2% of the allowable leak -rate..The: leak rate reported

includes'a 0.013%/ day penalty for non-standard valve

~

. alignments, containment-volume changes, and nitrogen additions a

to the containment. -

The overall'as-found leakage of the Type B and C tests conducted.during:the.1982 refueling outage was 145,744 sec per minute.orl63.4% of 0.6L described in Section III.C.3 of

' Appendix J'to 10 CFR 50,.

After. repairs, the overall leakage

. rate was.10,474 sec per minute or 4.5% of 0.6L,.

.The~overall as-found leakage of the Type B and C tests conducted during the 1983 refueling outage was 99,390 sec per minute or143.2% of-0.6L.- After repairs, the overall leakage

. rate was 12,608 sec per, minute or 5.5% of 0.6L,.

The overall as-found leakage of the Type B.and C tests conddcted during the 1984 refueling outage was greater than

.(not quantifiable) 19,976 scc per minute or 8.7% of 0.6L After repairs, the overall leakage rate was 14,066 scc p8r.

minute or 16.1% of;0.6L,.

The.overall as-found leakage of the Type B and C tests conducted during the-1985 refueling outage was greater than (not quantifiable) 200,770 scc per minute or 87.3% of 0.6L

~

'After repairs,'the overall leakage rate was 12,328 sec per,.

minute or 5.4%-of 0.6L',,

Enclosed are summary l reports of the 1986 Type A test and the

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Type B and C tests between the April 1982 and October 1986 ILRT'S.

The summary-of the Type B'and C tests includes all of the test data obtained during and between cach of the refueling outages.

Also included with the Type B.and C results are comments concerning those penetrations whose leak rate approached the 0.6L, limit.

Very trul

yours,

(,

/

C. W. Fay Vice President Nuclear Power

. Enclosures Copies to NRC Resident Inspector NRC Document Control Desk Washington, D.C.

20555