ML18139B310
| ML18139B310 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/15/1981 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 303, NUDOCS 8105190088 | |
| Download: ML18139B310 (2) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIROXN IA 23261 May 15, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNITS NO. 1 AND NO. 2 SUPPLEMENTAL INFORMATION Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requested an amendment to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station Units No. 1 and No. 2 in our letter to you dated April 28, 1981 (Serial No.
232).
The amendment proposed Technical Specifications changes to support operation of Surry Unit 1 with replacement steam generators.
Transmitted herewith is supplemental information to our April 28, 1981 sub-N mittal regarding the deletion of two LOCA related F Lill limits identified as F N LOCA and F N LOCA These limits were imposed in our letter from Lill Assembly Lill Rod Mr. C. M. Stallings (Vepco) to Mr. E. G. Case (NRC) date.a August 26, 1977 (Serial No. 372) and October 14, 1977 (Serial No. 403B), respectively.
These limits were previously required to ensure that the limiting condition assumed in the LOCA-ECCS analysis was not exceeded for operation of the Surry units with steam generator tube plugging levels greater than approximately 20
.percent.
These limits are no longer required by the current LOCA-ECCS Aool 5
1/0 f
8105190068
e VIRGINIA ELECTRIC AND POWER COMPANY TO 2
analysis, submitted in our letter from Mr. C. M. Stallings (Vepco) to you dated May 31, 1979 (Serial No. 388), to support operation of the Surry units with replacement steam generators.
N Although not required by our May 31, 1979 submittal, the LOCA F till Technical Specifications entries were not deleted for Surry Unit No. 2 due to their continued requirement for Surry Unit No. 1 which was still operating with degraded steam generators.
- However, since both Surry units will now be operating with replacement steam generators, our April 28, 1981 submittal has N
deleted the LOCA Ftill limits from the Technical Specifications.
This change is consistent with our F~ limits prior to reaching large steam generator tube plugging levels in 1977.
Should you have any questions or comments, we would be happy to discuss this with you at your earliest convenience.
cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II Very truly yours, 10f~
'\\)
B. R. Sylvia Manager - Nuclear Operations and Maintenance