ML19256A773
| ML19256A773 | |
| Person / Time | |
|---|---|
| Issue date: | 01/09/1979 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | James Anderson WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 7901160125 | |
| Download: ML19256A773 (2) | |
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JAh 9 kil Mr. Tom Anderson, Manager Nuclear Safety Department Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230
Dear Mr. Anderson:
This is in response to your letter dated November 6,1978 (NS-TMS-1989) regarding the forthcoming Semiscale M00-3 small break experiment.
You stated tha.t you did not see the need to predict this experiment since it had limited validity for small break phenomena verification.
In particular, you questioned the adequacy of the break flow behavior and the non-typicalities of the experiment resulting from the small pipe size, large metal heat, and the use of two different steam generators.
In addition, you requested that these matters be discussed at a meeting with all vendors, EG&G and NRC in attendance.
We have reviewed the information in your letter and agree that the size and physical arrangement of the M00-3 facility could influence the phenomena normally expected during postulated small breaks. However, in our vfew the proposed small break experiment should provide valuable information for the assessment of computer programs used for these analyses.
In particular, we note that you questioned the usefulness of the break discharge data due to potential microscopic effects.
$hould the';e small scale effects preclude the prediction of break flow by current models, the measured break flow could be imposed as a boundary condition an the calculation. The calculation could then proceed in the normal manner, and other features of the small break model could then be evaluated against the test data.
At the current time, there is limited integral test data available for small breaks. Accordingly, the proposed test will provide needed additional information in this area, and pretest predictions should be provided. We intend to inform you of the actual test conditions i; January 1979, and the Mntative submittal deadline for the calculations is April 1,1979.
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JAN 9 i !3 Mr. Tom Anderson With regard to your suggestion that a vendor meeting to discuss the M00-3 test facility be held in the near future, we note that this proposal was made at the Standard Problem Meeting on September 6, 1978. At that time, the vendors including Westinghouse did not support the proposal and stated that they would prefer to discuss items related to M00-3 on an individual basis with the staff.
In this regard, we are always available to discuss your concerns related to this program.
Sincerely, MJ k
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{G-N Roger J. Mattson, Director Division of Systens Safety Office of Nuclear Reactor Regulation O