ML19308D836

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Forwards Review of BAW-10095.Rept Acceptable Ref in OL Applications.Requests Revision to Include NRC Acceptance Ltr within Three Months
ML19308D836
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/24/1975
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Malley J
BABCOCK & WILCOX CO.
Shared Package
ML19308D835 List:
References
NUDOCS 8003191031
Download: ML19308D836 (2)


Text

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UNITEJ STATES ilUCLEAR REGULATORY COMMISSIL h

WASHINGTON. D. c. 20555 JAIL 2.g 'J7$

Mr. James F. Mallay Manager, Licensing Babcock & Wilcox Nuclear Power Generation P. O. Box 1260 Lynchburg, Virginia 24505

Dear Mr. Mallay:

The Regulatory staff has completed its review of Babcock & Wilcox topical report number BAW-10095, "CONTETT-Computer Program for Predicting Containment Pressure - Temperature Response to a Loss-of-Coolant Accident". A summary of our evaluation is enclosed for your information.

As a result of our review, we have concluded that BAW-10095 is acceptable for ' reference as a topical report in license applications.

The CONTDTT computer program may be used to calculate the containment pressure response for ECCS analysis provided that the input assumptions are selected in accordance with topical report BAW-10091.

The staff does not intend to repeat its review of BAW-10095 when it appears as a reference in an application. However, for plants other than the 177 fuel assembly plants with lowered-loop arrangement, i.e.

for plants other than Oconee 1, 2 and 3, Three Mile Island 1, Arkansas 1, Rancho Seco, Crystal River 3 and Midland 1 and 2, we will require justification of the specific input assumptions used.

In accordance with established procedure, it is requested that B&W issue a revised version of BAW-10095 within three months of receipt of this letter to include the NRC acceptance letter.

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Should Regulatory criteria or regulations change, such that our conclusions regarding BAW-10095 are invalidated, you will be notified

.and given the opportunity to revise and resubmit the topical report for review, if you desire.

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a 2-If you have any questions concerning our evaluation of this report, please contact us.

Sincerely,

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A. Schwencer, Chief Light Water Reactors Branch 2-3 Division of Reactor Licensing

Enclosure:

Evaluation of BAW-10095 cc:

R. Schaffstall h

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