ML20207E455

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: ML20207E455 ML20207E532
References
CON-NRC-86-123 VPNPD-86-513, NUDOCS 8701020185
Download: ML20207E455 (2)

Text

_ - _ _ _ _

1

=

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

=

-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  ?

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

November 1985. The Type A test was performed by the Bechtel lj 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 be retained by Wisconsin Electric and is available for NRC i

?

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. ] =

A M

1 8701020185 861229 -

PDR ADOCK 05000301 i P PDR g'}

dl

h g- ,

- - ].(

. H. R. Denton-

~

7 ' December 29, 1986 R

Page'2 Summary of Data

~

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