ML19095A300

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Enclosed Topical Report VEP-FRD-23, VEPCO Reactor Core Thermal Hydraulic Analysis Model Using LYNX1 & LYNX2 Computer Codes
ML19095A300
Person / Time
Site: Surry, North Anna  Dominion icon.png
Issue date: 09/19/1978
From: Thomas W
Virginia Electric & Power Co (VEPCO)
To: Harold Denton, Schwencer A
Office of Nuclear Reactor Regulation
References
Serial No. 532
Download: ML19095A300 (1)


Text

luLATORY DOCKEf FILE VrROINIA ELECTR.IC AND POWER COMPANY Ri:CHMOND, VJ:BGJ:N ~

23261 Septembtr 19, 1978 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Alb.ert Schwencer, Chief Operating Reactors Branch No. l Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

Serial No. 532 FR/MLS :-iw ; ~

Docket Nos.-

50-280 50-281 50-338 50-339 Lic~~se Nos~

DPR~32 DPR.:..:3-2

~*c:

NP.F-4,.

  • VEPCO THERMAL. HYDRAULIC ANALYSIS MODEL Enclosed are forty (40} copies of* the Vepco topical report VEP-FRD-23> "Vepco Reactor Core Thermal Hydraulic Analysis Model using LYNX!

and LYNX2 Computer Codesl'.

This-report is one in.. a series of topical reports being prepared to supply general information pertaining to-the nuclear reload licensing process and core follow support. of the Surry and North Anna Nuclear Power Stations. It is our intention to use the Vepco Core Thermal Hydraulic Model to perform appropriate reload safety analysis and* operational support in the near future. Additional topical reports in the general area of core thermal hydraulic analysis which will augment the capability documented in VEP-FRD-23 will be provided in the* future.

If you have questions on the material in this topical report>

please contact us*.

Enclosures Very truly yours~

,,,;:r,) '/L.co W. N. Thomas Vice President Fuel Resources COP~

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