ML18136A095
| ML18136A095 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 10/18/1979 |
| From: | Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18130A262 | List: |
| References | |
| 856, NUDOCS 7910240544 | |
| Download: ML18136A095 (1) | |
Text
e VIRGINIA ELECTRIC A.ND PowER Co:>>FANY B.rCHMOND,VrRGINIA 2326ll October 18, 1979 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, DC 20555
Dear Mr. Denton:
Serial No. 856 FR/FWS:
mvc Docket Nos. :
License Nos.:
50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 VEPCO VERSION OF THE COBRA IIIC/MIT COMPUTER CODE MANUAL Enclosed are ten (10) copies of the Vepco version of the COBRA IIIC/MIT computer code manual.
This information is being sent to facilitate your review of the Vepco Topical Report VEP-FRD~33 transmitted by my letter to you dated September 28, 1979, Serial No. 795.
The enclosed report was prepared by the Massachusetts Institute of Technology for the Electric Power Research Institute, and it documents the development of the COBRA IIIC/MIT computer code.
Appendix 12 of this report, "New INPUT DATA Presentation," has been modified to reflect the new input data requirements resulting from the Vepco modifications described in VEP-FRD-33.
Appendix 12 documented herein thus presents the input option which is currently utilized in the Vepco Reactor Core Thermal-Hydraulic Analysis Capability.
If you have any questions on the material in this report, please contact us.
Enclosures Very truly ~oury'
~{b; vC/£~
W. N. Thomas Vice President Fuel Resources