ML18113A774
| ML18113A774 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 12/28/1978 |
| From: | Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901150136 | |
| Download: ML18113A774 (1) | |
Text
- (* ~..,,.
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,V:IRGINIA 23261 Hr. H. R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Dear Mr. Denton; December 28, 1978
- Serial No. :. 532A FR/RWC:
mvc Docket Nos.:
50-280 50-281 50-338 50-339 License Nos.:
DPR-32 DPR-37 NPF-4 TOPICAL REPORT.ON VEPCO THER11AL HYDRAULIC MODEL In the.A. Schwence:r (NRC) to W. L. Proffitt (Vepco) letter dated December 4, 1978, several aspects of the Nuclear Regulatory Commission (NRG) review of the Vepco Topical Report VEP-FRD-23, "Reactor Core Thermal Hydraulic Analysis Model Using LYNX 1 and LY~ 2 Computer Codes" were addressed.
Con-cerning topical report review fees, Vepco is aware that a fee will be ch~rged for the NRC review of VEP-FRD-23.
However, we would anticipate that the NRC review effort would be minimized by the fact that the LYNX *computer codes will already have been reviewed and only our application of these codes to the Surry and North A...,na units remains to be reviewed.
Your indicated review of VEP-FRD-23, tentatively scheduled for com-pletion in the* second quarter of 1979, is compatible with our internal planning.
However, it shoul~ be noted that we will be providing additional topical reports in the core therinal-hydraulic area during the second* quarter.of 1979, and as a result, we may wish to lower the prio.rity on the review of VEP-FRD-23.
In this event, we will formally advise you.
In addition, your letter requested References 9 and 12 of topical*
report VEP-FPJ)-23.* Both references contain proprietary material received from Westinghouse Electric Corporation.
Reference 9 provides fuel assembly pressure drop data specifically for*Surry Units No. 1 and 2.
Pages 3-2 and 3-3 of VEP-FRD-23 explain the methodology and equations in which the specific values indicated in Reference 9 are used.
Reference 12 provides relative power infor-mation adapted for use in Vepco analyses.
Pages 4-3, 4-5 and 4-6 of VEP-FRD-23 provide further information on the use of the specific values provided in Reference 12. It is believed that a review*of the portions of the text indi-cated above will provide sufficient information to complete your review.*
Should you require more information, we would like to meet with you at your earliest convenience.
Ver; ~ru.ly yours,/
- 4 /_?) ~/;)£ -_,
7C/Ot/5013, W. N. Thomas Vice President Fuel Resources cc:
Hr. James P. O'Reilly