ML20029C536
| ML20029C536 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1994 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Taylor J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML20029C535 | List: |
| References | |
| BAW-10166P, NUDOCS 9402180049 | |
| Download: ML20029C536 (2) | |
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WASHINGTON D.C. 20555-0001 Jar.uary 31, 1994 Mr. J. H. Taylor, Manager Licensing Services B&W Nuclear Technologies 3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935
Dear Mr. Taylor:
SUBJECT:
ACCEPTANCE FOR REFERENCING OF TOPICAL REPORT BAW-10166P, REV. 4,
" BEACH: BEST ESTIMATE ANALYSIS CORE HEAT TRANSFER",
The staff reviewed Topical Report BAW-10166P, which describes the B&W Nuclear Technologies computer code for predicting reflood heat transfer during large-break loss-of-coolant accidents (LOCAs). The code is a special-purpose usage of the RELAP5/ MOD 2-B&W code for emergency core cooling systems (ECCS) evaluation model reflood heat transfer analysis.
B&W Nuclear Technologies submitted the core heat transfer methodology in this topical report to support licensing applications for B&W plants.
The staff finds the application of BAW-10166P to be acceptable for referencing in license applications to the extent specified, and the limitations stated in BAW-10166P and the associated U.S. Nuclear Regulatory Commission (NRC) technical evaluation.
The safety evaluation. report defines the basis for accepting this topical report.
The staff will not repeat its review of the matters found acceptable as described in BAW-10166P when the report appears as a reference in license applications, except to verify that the material presented in licensing applications applies to the specific plant involved.
Our acceptance applies only to the matters described in the application of BAW-10166P.
In accordance with procedures established in NUREG-0390, the staff requests that the B&W Nuclear Technologies publish accepted versions of this topical report, proprietary and non-proprietary, within 3 months of receiving this letter.
The accepted version shall include an "-A" (designating accepted) following the report identification symbol.
9402180049 940131 PDR TOPRP EMVBW C
. January 31, 1994 If the staff's criteria or regulations change so that its conclusions about the acceptability of the report are invalidated, B&W Nuclear Tectacingles or the applicants referencing the topical report, or both, should re...e and resubmit their respective documentation or submit justification for the continued effective applicability of the topical report without revising their respective documentation.
Sincerely, h4 W^
Asho. C. Thadani, Director Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation i
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