ML20065L778

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Forwards Fort St Vrain Accident Reanalysis Code (Reca 3) Verification Following Region Outlet Temp Redistribution, Per 810210 Meeting Commitment.Code Accurately Predicts Transient Behavior in Temp Redistribution Configuration
ML20065L778
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 10/06/1982
From: Brey H
PUBLIC SERVICE CO. OF COLORADO
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20065L783 List:
References
FSV-3A, P-82440, NUDOCS 8210190701
Download: ML20065L778 (1)


Text

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Public Service Company *f Ochado 5909 East 38th Avenue, Denver, Colorado 80207 October 6, 1982 Fort St. Vrain Unit No. 1 P-82440 F Sd - 34 Mr. Thomas M. Novak Assistant Director for Operating Reactors Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

FSV RECA Verification

REFERENCE:

PSC Letter from Mr. F.E. Swart to Mr. J.E. Miller, P-81054, dated February 18, 1981

Dear Mr. Novak:

In the February 10, 1981 meeting between PSC/GA/NRC, PSC committed to evaluate a plant transient from a " temperature redistribution" using the RECA 3 code. Since 1981 there has only been one transient suitable for this analysis. The results of this analysis show that the RECA 3 code does accurately pre 11ct plant transient behavior, even in a temperature redistribution configuration.

Enclosed are 40 copies of " Fort St. Vrain Accident Reanalysis Code (RECA 3) Verification Following A Region Outlet Temperature Redistribution."

Should you have any questions, please contact Mr. M.H. Holmes at (303) 571-6711.

Very truly yours, C

H. L. Brey, Manager Nuclear Engineering Division HLB /JCS:pa Enclosures 8210190701 821006 h  ;

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