ML17037C520
| 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:
Niagara Mohawk Power Corporation
. Syracuse;.
N. Y.
,13202 R.
R. Schneider DATE OF DOC 10-3-73 DATE REC'D 10-9-73 LTR MEMO RPT OTHER TO:
Mr. O'Lear ORIG 1 si ned CC OTHER SENT AEC PDR X
SENT LOCAL PDR X
CLASS 'NCLASS PROP INFO
'NPUT NO C
S REC'D DOCKET NO:
XXX DESCRIPTION:
Ltr trans the following:
PLANT NATE:Nine Mile Unit 0 1
50-220 ENCLOSURES:
REPORT: '"Secondary Containment Integrated Leak 'Rate Test".
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40 cye rec'd)
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D~<CJ7e'moyen FOR ACTION/INFORMATION 10-10-73 AB BUTLER(L)
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NIAGARA MOHAWK POWER CORPORATION IIllW NIAGARA~
MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE, N.Y. IS202 October 3, 1973 Ot TB $73 '"
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 Enclosures CP 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
4, A
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FIGURE 3.4.1 REACTOR BUlLDlNGPRESSURE 10 12 WIND SPEEO 16
)8 20
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