ML18141A159
| ML18141A159 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/06/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 521A, NUDOCS 8310140094 | |
| Download: ML18141A159 (2) | |
Text
I e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWA:RT VxcE P:aESIDENT NUCLEAR OPERATIONS October 6, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No.
Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Serial No. 521A PSE/WBR:lmf:0743C Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE In our letter dated September 13, 1983 (Serial No. 521) Vepco requested an amendment to operating licenses DPR-32 and DPR-37 to allow operation of Surry Unit Nos. 1 and 2 at reduced boron concentrations for the boron injection tank (BIT) and boric acid system.
On September 21, 1983, Vepco met with the NRC to review the submittal.
During the meeting several questions were raised relevant to the methodology used to analyze the steam lihe break assuming the BIT was at zero (0) ppm.
Vepco pointed out that the methodology used for those analyses is discussed in Vepco's topical report VEP-FRD-41 (copy attached) which had been submitted to the NRC in April 1981.
We propose a technical meeting with the staff to discuss in detail the analysis methods, codes, assumptions and results, etc.
Vepco would like to hold this meeting in the 3rd week of October 1983.
This should give your staff sufficient time to review the referenced topical report and our submittal, and to forward any questions to us for review prior to the meeting.
Should you have any questions, please contact us at your earliest convenience.
Very truly yours, J!U W. L. Stewart
Enclosure:
(1) Vepco Topical Report VEP-FRD-41 entitled "Reactor System Transient Analyses using the RETRAN Computer Code" dated March 1981.
831014(f094--83100.6 PDR ADOCK 05000280 P
e VIRGINIA ELECTRIC AND POWER COMPANY TO cc: Mr. James P. 0 1Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. Harold R. Denton Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No.
Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 2