ML18139B241
| ML18139B241 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/14/1981 |
| From: | Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18139B242 | List: |
| References | |
| 215, NUDOCS 8104160326 | |
| Download: ML18139B241 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHh!OND,VIROINIA. 23261 April 14, 1981 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, DC 20555
Dear Mr. Denton:
Serial No.:
FR/NAS:
mvc Docket Nos, :
License Nos. :
215 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 N-PF-7 VEPCO REACTOR SYSTEM TRANSIENT ANALYSES Enclosed for your review are forty (40) copies of the Vepco Topical Report VEP-FRD-41, "Vepco Reactor System Transient Analyses using the RETRAN Computer Code".
This report is one of a series of topical reports supplying general information pertaining to the nuclear reload licensing and core follow support capabilities which have been developed at Vepco.
It is our intention to use the Vepco Reactor System Transient Analysis capability documented herein in conjunction with the Core Thermal-Hydraulic Analysis capability described in our previously submitted report (VEP-FRD-33, transmitted by my letter to you dated September 28, 1979, Serial No. 795) to analyze certain transients which are determined to require reanalysis as a result of core reloads or other operational or design changes at our nuclear units.
Our specific scope of appli-cation of RETRAN is discussed more fully in the report itself.
As indicated in my letter to you dated October 17, 1980, Serial No. 856, we may be supporting reload license amendments with this capability in the fourth quarter of 1981.
This report has been reviewed by Energy Incorporated, the RETRAN code developer.
In addition, it 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 10CFR 50.59.
We are aware that a fee will be review and will transmit the assessed fee you have any questions on the material in required for the topical report upon completion of the review.
If this topical report, please contact us.
~
7;r~ly;,ou~ ~:014) ~'-
- . LB I o. 4 1 6 o 3) u, f
l,, -_ ~7 ~;i~~y o*
\\ \\
W. N. Thomas pP Vice President J~
Fuel Resources Attachments