ML19094A816
| ML19094A816 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/29/1976 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Reid R, Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19094A816 (1) | |
Text
e VIRGINIA ELECTRIC.AND POWER COMPANY RICHMOND, VUlGINI.A 23261 January 29, 1976 Mr. Benard C. Rusche Director of Nuclear Reactor Regulation Attn:
Mr. R. W. Reid, Chief Operating Reactor Branch 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Rusche:
Serial No. 876 FR/MLB:cel Docket Nos.
License SUPPLEMENTAL INFORMATION IN SUPPORT OF AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 TECHNICAL SPECIFICATION CHANGE NO. 30
- sURRY POWER STATION*...;. UNIT NOS.
- 1 *AND *2 *
- In response to Mr. M. Fairtile's informal questions provided to Vepco on October 3," 1975, and Mr. Robert W. Reid's letter of December 22, 1975, the necessary information for you to initiate your final review of our proposed Technical Specifications Change No. 30, which was transmitted to you by our letter of June 5," 1975- (Serial No.* 553) and which concerns the operation of Surry Unit Nos. 1 and 2 with a slightly positive moderator temperature coefficient, is provided in Attaclunent 1.
The response to the last question from Mr. Reid's letter (which differed from the earlier informal request for additional information) is not provided in Attachment" 1.
The additional information required to answer this question is still in preparation but will be provided to*you in the very near future.
The attached additional information is in consonance with the safety analysis reports for operation of Surry Unit Nos; 1 and 2 with a positive moderator temperature coefficient already provided to you in our letters of June 5, 1975 (Serial No. 553) and September 8," 1975 (Serial No.
686).
This additional information, along with the above safety analysis reports, continue to support the conclusion that operation with the proposed positiv~ moderator temperature coefficient will not result in accident consequences more severe than the.acceptable limits already established in applicable safety analyses.
If you should have any questions or comments, we would be most happy to discuss them with you at your earliest convenience and prior to our planned March 1, 1976 submittal on the upcoming Surry Unit 2 reload.
Attachments cc:
Mr. Norman C. Moseley Very truly yours,
'to./)JJ,?~zcc~e,,,:.~r C. M. Stallings Vice President-Power Supply
- and Production Operations 949