ML18139C059

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Forwards Errata to Topical Rept VEP-FRD-33, VEPCO Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code
ML18139C059
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 10/04/1982
From: Leasburg R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML18139C060 List:
References
284A, NUDOCS 8210120297
Download: ML18139C059 (2)


Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND? VIRGINIA 23261 R.H. LEASBURG VICE PRESIDENT NUCLEAR OPERATIONS October 4, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. D. G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Gentlemen:

Serial No:

FR/KLB:

plc Docket Nos:

License Nos:

VIRGINIA ELECTRIC AND POWER COMPANY TOPICAL REPORT VEP-FRD-33 "Vepco Reactor Core Thermal-Hydraulic Analysis Using the COBRA Ille/MIT Computer Code" 284A 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 Enclosed as Attachment 1 is supplemental information to our most recent response to Nuclear Regulatory Commission (NRC) Staff questions on the Vepco Topical Report, VEP-FRD-33, "Vepco Reactor Core Thermal Hydraulic Analysis Using the COBRA-Ille/MIT Computer Code",

transmitted by the R.

H. Leasburg (Vepco) to H. R. Denton (NRC) letter, Serial No.

284, dated May 23, 1982.

As requested informally by the Staff, this supplement adds a

seventh COBRA/THINC-I benchmark comparison, using an alternate axial power distribution, to the six cases provided by our May 23, 1982 submittal.

If you require additional information, please contact us.

Attachment cc:

Mr. R. L. Tedesco Assistant Director for Licensing Mr. C.H. Berlinger Branch Chief, Core Performance Branch Mr. J. S. Berggren Standardization and Special Projects Branch

[- -8210120297 -821004

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R.H. Leasburg

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