ML18153D251

Forwards Suppl 1 to VEP-NAF-1, Pdq Two-Zone Model. Rept Describes Coarse Mesh 2-D Core Analysis Model to Be Used for in-house Reload Design for Facilities

ML18153D251
Person / Time
Site:	Surry, North Anna
Issue date:	03/01/1993
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18152A042	List: ML18152A041 ML18153D251
References
93-013, 93-13, NUDOCS 9303040015
Download: ML18153D251 (2)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 1, 1993 United States Nuclear Regulatory Commission Serial No.93-013 Attention: Document Control Desk NL&P/CGL R2 Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 TOPICAL REPORT SUPPLEMENT

• PDQ TWO ZONE MODEL Enclosed for your review and approval is Virginia Power Topical Report VEP-NAF-1, Supplement 1, entitled "The PDQ Two Zone Model" and dated November 1992. This report is a supplement to Topical Report VEP-NAF-1, which was previously submitted to the NRC for review and approval by an October 1, 1990 letter (Serial No.90-562).

The enclosed report has been reviewed and approved by the Station Nuclear Safety and Operating Committee at each station.

The supplemental report describes a coarse mesh 2-D core analysis model to be used for in-house reload design for Surry and North Anna. The 2-D model is closely related to the 3-D model described in Topical Report VEP-NAF-1. As previously indicated, the core design for Surry Unit 1 Cycle 13, which will include the insertion of axially zoned flux suppression inserts, requires use of the 3-D model. In a November 25, 1992 letter (Serial No.92-713), we indicated our intent to use Topical Report VEP-NAF-1 pursuant to 10CFR50.59 prior to receipt of the NRC approval of the report. In a similar fashion, we intend to use the enclosed supplement pursuant to 10CFR50.59 prior to NRC review and approval.

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e Our November 25, 1992 letter also requested that the NRC continue their review and approval of Topical Report VEP-NAF-1. We likewise request your review and approval of the enclosed supplemental report. Due to the similarity of Topical Report VEP-NAF-1 and the enclosed Supplement 1, a concurrent review of these two reports is suggested.

Very truly yours,

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W. L. Stewart Senior Vice President - Nuclear Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station