ML18136A020
| ML18136A020 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/28/1979 |
| From: | Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18136A021 | List: |
| References | |
| 795, NUDOCS 7910020391 | |
| Download: ML18136A020 (2) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 28261 September 28, i979 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
Serial No. 795 FR/FWS:
mvc Docket Nos.
50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 License Nos.
VEPCO REACTOR CORE THERMAL-HYDRAULIC ANALYSIS Enclosed for your review are forty (40) copies of the Vepco Topical Report VEP-FRD-33, "Vepco Reactor Core Thermal-Hydraulic Analysis using the COBRA IIIC/MIT Computer Code".
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 documented herein as the primary analysis tool to perform appropriate reload safety analysis and operational support in the near future.
The thermal-hydraulic capability docu-mented in the Vepco Topical Report VEP-FRD-23 transmitted by my letter to you dated September 19, 1978, Serial No. 532 will be used to supplement the capability of this current Vepco model and is of lower priority from an NRG review standpoint.
Additional topical reports in the general area of system safety analysis, which will complement* the capability documented in VEP-FRD-33, will be provided in the future.
This report has been reviewed by both the North Anna and Surry Station Nuclear Safety and Operating Committees and the System Nuclear Safety and Operating Committee.
Further, it has been determined that the methodology and analysis capability described herein do not involve an unreviewed safety question as defined in 10 CFR 50.59.
We are aware that a fee will be required for the topical review and will 1910020J'I/
,I VrRornIA ELECTRIC AND PowEn CoMPANY To Mr. H. R. Denton transmit the assessed fee upon completion of the review.
If you have any ques-tions on the material in this topical report, please contact us.
Enclosures W. N. Thomas Vice President Fuel Resources