ML19345B779

Forwards Prediction of Fftf Natural Circulation Test Results Using Clinch River Breeder Reactor Plant Project Methodology, & Demo Pretest Predictions for Fftf Natural Circulation Tests. Info Available in Central Files Only

ML19345B779
Person / Time
Site:	Clinch River
Issue date:	11/28/1980
From:	Copeland P ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML19345B780	List: ML19345B779 ML19345B783 ML19345B788 ML19345B796
References
NUDOCS 8012020497
Download: ML19345B779 (2)

Text

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7 C v s d N.b,e$ N Department of Energy 7

Clinch River Breeder Reactor ._

Plant Project Office R O. Box U  ;

Oak Ridge, Tennessee 37830

]

Docket No. 50-537 g a

No; ember 28, 1980 Mr. Darrell G. Eisenhut, Director Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Eisenhut:

PRE-TES' PREDICTION OF FFTF NATURAL CIRCULATION

Reference:

Letter S:L:1195, A. R. Buhl to R. S. Boyd, " Natural Circulation Decay Heat Removal Verification Plan," dated June 21, 1976.

This letter transmits information concerning the pre-test predict;un of the results of the natural circulation test scheduled for early December 1980 at the Fast Flux Test Facility (FFTF). The pre-test prediction is based on CRBRP methodology and computer codes as discussed in the refer-ence. This pre-test prediction is provided to clearly document that the data and methodology which will be used in the post-test analyses were selected prior to the test.

The pre-test prediction assumes reactor scram and trip of the sodium circulating pumps from a pre-existing condition of 35% of full power and 75% of full flow. A test with similar conditions is scheduled for December if80. Additional tests will be performed for conditions of (1) 75% pawer and 75% flow and (2) 100% power and 100% flow. Pre-test predictiors utilizing CRBRP methodology and computer codes will be performed for those tests. The results will be provided to you prior to the test,.

Following completion of all three natural circulation tests, post-test analyses will be performed utilizing the actual test boundary conditions.

The pre-test predictions are, of necessity, based on boundary conditions (e.g. , power history and heat sink temperature) selected by the analysts.

It is unlikely that these boundary conditions will be duplicated during

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the actual tests. Accordingly, the post-test analyses will be used for comparison with experimental data. A report will be compiled to consol-i 9,g})

idate all of the pre-test and post-test predictions and discuss any  %@g ,

diffet ences between those analytical results and the test data. 1 f aainoso y

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v Mr. Darrell G. Eisenhut November 28, 1980 The pre-test and post-test predictions wili be considered " successful" if thcy demonstrate (1) that the Project methodology provides a reason-able characterization of the phenomena controlling natural circulation flow and heat transfer in both the reactor and the heat transport loops and (2) that use of the methodology results in a conservative prediction of the critical plant parameters (e.g., core hot channel sodium temper-ature and heat transport system flow rates). Section 8.2 of Attachment II (WARD-94000-00321) discusses the methodology utilized to gene ate the acceptance boundary curves for the pre-test predictions. The same methodology will be utilized to generate acceptance boundary curves for the post-test predictions. The prediction methodology will be consid-ered acceptable if the measured flows for the tests are equal to or greater than the acceptance boundary curves.

The contents of each of the attachments are as follows:

Attachment I Overall prediction methodology description Attachment II WARD-94000-00321, "DEM0 Pre-Test Predictions for the FFTF Transient Natural Circulation Tests," base case prediction in terms of heat transport system flow rates Attachment III Parametric variation and sensitivity case predic-tions in terms of heat transport system flow rates Attachment IV Base and sensitivity case prediction: in terms of reactor core hot channel temperatures Attachment V Archive listing of input data for FORE-2M and COBRA-WC cases Attachment VI Microfiche a; chive copy of DEMD base case input, output, and program modifications We would be pleased to answer any questions you may have on the attach-ments or to discuss the analyses at your convenience.

l Sincerely, am . # A Ra nond . Copeiana PS:80:359 A ting Assistant Directo for Public Safety Attachments cc: Standard Distribution Service List Licensing Distribution