ML20055B470

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Forwards Repts Containing post-test Analyses of Fftf Natural Circulation Tests,Providing Addl Assurance That Analytical Models Used to Predict Natural Circulation Can Predict Reactor/Plant Performance in Natural Circulation Transient
ML20055B470
Person / Time
Site: Clinch River
Issue date: 07/15/1982
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Check P
Office of Nuclear Reactor Regulation
Shared Package
ML20055B471 List:
References
HQ:S:82:068, HQ:S:82:68, NUDOCS 8207220402
Download: ML20055B470 (2)


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Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:068 JUL 151982 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commis!. ion Washington, D.C. 20555

Dear Mr. Check:

TRANSMITTAL 0F REPORTS ON NATURAL CIRCULATION VERIFICATION

References:

(1) Letter HQ:S:82-042, J. R. Longenecker to P. S. Check,

" Transmittal of Verification of Natural Circulation in the Clinch River Breeder Reactor Plant--An Update,"

dated June 10, 1982 (2) Letter PS:80:359, R. L. Copeland to D. G. Eisenhut,

" Pre-test Prediction of FFTF Natural Circulation,"

dated November 28, 1980 (3) Letter PS:81:080, R. L. Copeland to D. G. Eisenhut,

" Pre-test Prediction of FFTF Natural Circulation Tests," dated February 26, 1981 In the Referenced (1) letter, the Project provided an update to the natural circulation verification plan. Included as part of the verification plan was the verification of the codes used to predict natural circulation by pre-test and post-test analysis of the' FFTF natural circulation tests. The pre-test predictions of the FFTF natural circulation tests initiated from 35 percent power were provided in Reference (2). Reference (3) provided pre-test predictions for the FFTF natural circulation tests initiated from 75 percent and 100 percent power.

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9 8207220402 820715 PDR ADOCK 05000537 A PDR N

2 This letter transmits 70 copies of the following reports which contain the post-test analyses of the FFTF natural circulation tests:

1. CRBRP-ARD-0310 Verification of the CRBRP Natural Circulation Core Analyses Methodology with Data from FFTF Natural Circulation Tests -

June 1982

2. WARD-NC-94000-6 DEM0 Post Test Analysis of the FFTF Transient Natural Circulation Tests - June 1982 These reports provide additional assurance that the analytical models used to predict natural circulation can adequately predict the reactor and plant perfonnance in a natural circulation transient and provide confidence that natural circulation can be relied upon as a means of shutdown heat removal.

Sincerely,

&- . og tre b tt N JhnR.Longen' er Acting Director, Office of the Clinch River Breeder Reactor Plant Project Office of Nuclear Energy Enclosures cc: Service List Standard Distribution Licensing Distribution l

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