ML19312E467
| ML19312E467 | |
| Person / Time | |
|---|---|
| Issue date: | 04/01/1980 |
| From: | Denise R Office of Nuclear Reactor Regulation |
| To: | Eicheldinger C WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 8006040490 | |
| Download: ML19312E467 (2) | |
Text
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f F e AB Rdg. File APR1 1980
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Mr. C. P cheldinger, Manager Nuclear Safety Department Westinghouse Electric Corporation i
P.O. Box 355 Pittsburgh, Penasylvania 15230
Reference:
Letter from J. Stolz, Chief, Light Water Reactors Branch No.1, l
Division of Project Management to C. Eiche1dinger, Manager, Nuclear Safety Dep?rtment of June 17, 1979.
Subject:
" Evaluation of Westinghouse Topical Reports WCAP-8708(P) and WCAP-8709(NP)."
Dear Mr. Eicheldinger:
The NRC safety evaluation of your topical report on LOCA blowdown loads, see reference, was based in part on your analyses of some existing small scale tests for the fluid-structure coupled techniques used in MULTIFLEX.
Additional experimental data to evaluate fluid-structure interaction during subcooled decompression will be obtained at the HDR test facility in the Federal Republic of Germany. The HDR is the largest known test facility especially designed to obtain high quality experimental data required for the verification of related analysis methods. The enclosure is provided for reference on the HDR blowdown program.
We have been informed by the Office of Nuclear Reactor Research, NRC, that Westinghouse is an active participant in the HDR blowdown program and plans to perform pre-test calculations using the MULTIFLEX computer program.
Since i
these analyses should provide further confirmation of the methods used in MULTIFLEX, we request that Westinghouse also provide the Office of Nuclear Reactor Regulation with your pre-test analyses for a representative experiment.
We have selected Test V.31 as the case to be provided.
This case is typical of PWR operating conditions and should provide the best set of data for computer program verification.
Both the thermal-hydraulic and the structural analyses associated with the test are to be provided. The test schedule is provided in the enclosure in Section 9.
A submittal date of June 15, 1980 has been chosen for this analysis in order to keep within the test program schedule and to provide ample time to perform the analyses.
It should be noted that the vessel geometry is not as clean as had been antici-pated in that several fluid loops are included.
Specifically, nozzles "S" and "T", see pages 2-16 and 3-14 of the enclosure, and the mixed water exit loop g,
and bypass, see pages 2-8, 2-13 to 2-15 of the e vessel during the test. As a result, some wave reflections are expected at t t these locations.
It is recomended that the "S" and "T" nozzles be modeled.
s Consideration should be given to modeling the mixed water exit loop and bypass systems, based on your judgement of their expected influence on the results.
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APR 1 1980
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Mr. C. Eiche1dinger A list of the data to be provided, in addition to nodal diagrams and input listings, is given in Section 6 of the enclosure. While strict adherence to the deta format is not mandatory, all listed data is to be provided in graphical form.
Each graph should be clearly identified with the narne and dets type.
In addition to these data, the data shown on page 3-17 for the "S" and "T" nozzles is to be provided. The differential pressure computed across the core barrel, from the 270 to the 90 reference, for each axial elevation modeled should also be provided.
Questions concerning the thermal-hydraulic aspect of the analysis should be directed to E. Throm, Analysis Branch, Division of Systems Safety (301-492-9458).
Questions concerning the structural aspect of the analysis should be directed to R. Bosnak, Chief, Mechanical Engineering Branch, Division of Systems Safety (301-492-7456).
The analyses should be provided no later than June 15, 1980.
If you cannot meet this date, please inform this Office and provide a schedule for the submission of the analyses.
Sincerely.
Original Signed By Richard P. Danise Richard P. Denise, Acting Assistant Director for Reactor Safety Division of Systems Safety
Enclosure:
As stated bec: (LetterOnly)
Z. Rosztoczy J. Knight, MEB R. Bosnak, MEB P.Y. Chen, MEB S. Hou, MEB P. Norian L. Shotkin, RES E. Throm NRC PDR R. Fraley, ACRS
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