ML19316A723
| ML19316A723 | |
| Person / Time | |
|---|---|
| Issue date: | 03/24/1980 |
| From: | Denise R Office of Nuclear Reactor Regulation |
| To: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| NUDOCS 8005230781 | |
| Download: ML19316A723 (2) | |
Text
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m,..g ifr. A. E. Scherer Licensing !!anager Cor bustien Engineering 1000 Prospect Hill Road Windsor, Connecticut 06095 l
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Dear Mr. Scherer:
Reference:
Letter from R. L. Baer, Chief, Light Water Reactors Branch No.
- 2. Division of Project Management to A. E. Scherer, Licensing Manager, of February 12, 1979,
Subject:
Staff Evaluation of Topical Report EENPD-252-P The flRC safety evaluation of your topical report on LOCA blowdown loads, see reference, included a commitment on your part to perform a pre-test analysis of an HDR blowdown experiment when test conditions could be defined. 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 pre-test data art now available and are provided in the enclosure. The HDR analyses will supplement those previously perfomed for the CSE, Semi-scale and LOFT test facilities.
The NRC has selected test V.31 as the case to be analyzed. This case is typical of PHR 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 tne vessel geometry is not s clean as had been anticipated 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 and bypass, see pages 2-8, 2-13 to 2-15 of the enclosure, will be
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open to the vessel during the test. As a result, some wave reflect. ions are expected at these locations.
It is recommended that the "S" and "T' nozzles o 1-be modeled. Consideration should be given to modeling the mixed water exit
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loop and bypass systems, based on your judgement of their expected influence on the results.
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- !r. A. E. Scnerer ' list of the data to be nrovided, in addition to nocal diagrams and innut
': tings, is ;iven in Sacacn 6 of the enclosure. 'lila stric Wherence to the data format is not mandatory, all listad data is to be provided in qranhical fem.
Each araoh should be clearly identified with the name and data type.
In addition to these data, the data shown on naces 3-17 for the "S" and "T" nozzles is to be provided.
The differential nressure comouted across the core barrel, from the 273* to the 90* reference, for each axial elevation modeled should also be provided.
Questions concerning the ther,al-hydraulic aspect of the analyns should be directed to E. Throm, Analysis Branch, nivision of Systems Safety (301-492-9458). Questions concerning the structural aspect of the analysis should be directed to R. Bosnak, Chief, Pechanical Engineering Branch, Division of Systems Safety (201-492-7456).
The analyses should be provided no later than June 15, 1980.
If you cannot meet this dt.te, olease infom this office and provide a schedule for the submission of the analyses.
Sincerely, Original Signed By Richard P. OBUI5' Richard P. Denise, Acting Assistant Director for Reacur Safety Division of Systems Safety
Enclosure:
!!DR-Safety Procran (Research Project RS 123) Special Project 3000: Blowdown-Experiments (2)
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bec: (Letter only) sztoczy DISTRIBUTION J. Knight, MEB R. Bosnak, MEB NRR Rdg P. Chen, MEB AB Rdg S. Hou, NEB Central Files P. Norian RDenise L. Shotkin, RES E. Throm ACRS PDR OFFDCEh.,
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