ML17037C520

Submits 40 Copies of the Secondary Containment Leak Rate Test Completed During the Last Operating Cycle

ML17037C520
Person / Time
Site:	Nine Mile Point
Issue date:	10/03/1973
From:	Schneider R Niagara Mohawk Power Corp
To:	O'Leary J US Atomic Energy Commission (AEC)
References
Download: ML17037C520 (12)

Text

AEC DIST UTION FOR PART 50 DOCKET MATE~)

(TEMPORARY FORM) CONTROL NO: 7497 FILE:

FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Niagara Mohawk Power Corporation

. Syracuse;. N. Y. ,13202 R. R. Schneider 10-3-73 10-9-73 TO: ORIG CC OTHER SENT AEC PDR X SENT LOCAL PDR X Mr. O'Lear 1 si ned CLASS 'NCLASS PROP INFO 'NPUT NO C S REC'D DOCKET NO:

XXX 50-220 DESCRIPTION: ENCLOSURES:

Ltr trans the following: REPORT: '"Secondary Containment Integrated Leak 'Rate Test".

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October 3, 1973 II~" g ", dI gp I /~md A Mr. John F. O'eary, Direct'or of Licensing United States Atomic Energy Commission lltashington, D. C. 20545

Dear Mr. O'eary:

Nine Mile Point Nuclear Station Unit 1 Provisional. Operating License DPR-17 Docket No. 50-220 In conformance with the Technical Specifications for Nine Mile Point Nuclear 'Station Unit 1, we are enclosing forty,'(40) copies of the Secondary Containment Leak Rate Test completed during the.

last operating cycle.

Very truly yours, Sc ei er Vice President - Electric Operations RRS:cm CP Enclosures MNHED tl Ot:T9 1973~

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SECONDARY CONTAINMENT ?NTEGRATED LEAK TEST

SUMMARY

REPORT SECONDARY CONTAINMENT INTEGRATED LEAK TEST 1.0 PURPOSE The purpose of the test(s) was to investigate the leak rate of the secondary containment under various wind conditions. The results of the test were used to verify compliance with license limits. (See Technical Specifications 3.4.1 and 4.4.1) 2.0 PROCEDURE The Reactor Building was isolated and one of the two emergency ventilation systems placed into operation.

2.1 The door into the Reactor Building Railway Bay was open so that leakage through the railroad door is taken into account.

3. 0 TEST (S) DATA The test data is presented in the following Table:

TABLE I - TEST DATA 4-11-73 4-11-73

¹ll ¹12 i(ind Speed (mph) 10 10 llind Direction SSÃ SS!U Outside Temp. ('F) 29'F 29 F Inside Temp. ('F) 72 F 72 F Rx. Bldg. hP ("H20) .32 .32 Emer. Vent Flow Rate (cfm) 1500 1SOO 4.0 SPECIFICATION Figure 3.4.1 of the Tcchnical Specifications represents the allowable limit.

The differential pressure between the Reactor Building and the external static pressure shall be at least as negative as shown on Figure 3.4.1 for August 1973

2 4.0 SPECIFICATION CONT'D the test condition windspeed and an emergency ventilation fan flow rate of less than 2000 cfm.

5.0 EVALUATION OF REACTOR BUILDING LEAK RATE TESTS Leak rate test was performed on the Reactor Building on April 11, 1973.

In both tests each emergency ventilation fan was tested. The results of the test show the Reactor Building Leak Rate to be within allowable limits.

The wind conditions existing for each System tested was 10 MPH from the South. The emergency ventilation fan flow rate necessary to obtain the required BP ( ~ -. 28 "H20) was well below the maximum allowed. A fan flow rate of + 1500 cim produced a building differential of -.32 to

-.37 "H20.

August 1973

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FIGURE 3.4.1 REACTOR BUlLDlNG PRESSURE 10 12 16 )8 20 WIND SPEEO

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