ML18141A162
| ML18141A162 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 10/14/1983 |
| From: | Stewart W Virginia Power (Virginia Electric & Power Co) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18141A163 | List: |
| References | |
| 545, NUDOCS 8310190043 | |
| Download: ML18141A162 (2) | |
Text
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- e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS October 14, 1983 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
Dear Gentlemen:
Seri a 1 No.
545 PSE/SMB:
vdu Docket Nos:
50-280 50-281 50-338 50-339 License Nos:
DPR-32 DPR-37 NPF-4 NPF-7 NOMAD CODE AND MODEL Enclosed for your *review are forty (40) copies of the Vepco Topical Report VEP-NFE-1, 11The Vepco NOMAD Code and Model.
11 This report is one of a series of topical reports supplying general informa-tion pertaining to the nuclear reload licensing and core follow support cap-abilities which have been developed at Vepco.
It is our intention to use the Vepco NOMAD Code and Model documented herein in conjunction with the Vepco PDQ07 Discrete and One Zone models and the Vepco FLAME model described in our pre-viously submitted reports (VEP-FRD-19A, VEP-FRD-20A, VEP-FRD-2~A, respectively}
to perform reload core design and reload key parameter generation.
Our specific scope of application of NOMAD is discussed more fully in the report itself.
The recommendations of the North Anna and Surry Station Nuclear Safety and Operating Committees have been incorporated into this report. This report has also been reviewed by the Safety Evaluation and Control staff.
Further, it has been determined that the methodology and analysis capability described herein do not involve an unreviewed safety question as defined in 10CFR 50.59.
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e VIRolNIA ELEcTR1c AND PoWER CoMPANY To Mr. Haro 1 d R. Denton We are aware that a fee will be required for the topical report review and will transmit the assessed fee upon completion of the review.
If you have any questions on the material in this topical report, please contact us.
Enclosure cc:
Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. J.P. O'Reilly Regional Administrator Region II Very truly yours, JI /(
0 r,s-~~r W. L. Stewart