ML18149A544
| ML18149A544 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/23/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18149A545 | List: |
| References | |
| 87-001, 87-1, NUDOCS 8703030021 | |
| Download: ML18149A544 (2) | |
Text
e 10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
- w. L. STEWART V1cE PRESIDENT NUCLEAR OPERATIONS February 23, 1987 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNITS 1 AND 2 INCREASED FQ(Z) AND ACCUMULATOR VOLUME OPERATING BAND Serial No.87-001 E&C/GLD/vlh Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Pursuant to 10 CFR 50.90, the Virginia Company) requests an amendment, in the form Specifications, to Operating License Nos.
Power Station Units 1 and 2.
Electric and Power Company (the of changes to the Technical DPR-32 and DPR-37 for the Surry A LOCA-ECCS reanalysis for Surry Units 1 and 2 has been performed using the NRC approved Westinghouse 1981 ECCS Large Break Evaluation Model with the BART Code.
The evaluation model changes described in Reference 1 were included in this analysis.
The analysis has been performed in compliance with Appendix K to 10 CFR 50 and meets the acceptance criteria delineated in 10 CFR 50.46.
This analysis was performed by the Company's Engineering Staff and the results will support continued full power operation for both Surry Units at steam generator tube plugging levels of up to 7 percent.
The results of this reanalysis also support a new FQ limit of 2.32.
In addition, the ana1yses will allow accumulator water volume to vary between 975 and 1025 ft per accumulator.
These results are provided in Attachment 2.
Proposed changes to the Technical Specifications, consistent with the reanalysis, are provided in.
This request has been.reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that this request does not involve any unreviewed safety questions as defined in 10 CFR 50.59 nor a significant hazards consideration as defined in 10 CFR 50.92.
/ 8703030021 870223 PDR ADOCK 05000280.
P PDR
e We have evaluated this request in accordance with the criteria in 10 CFR 170.
Accordingly, a
voucher check in the amount of
$150 is enclosed as an application fee.
Very truly yours,
~s.~
W. L. Stewart Attachments
- 1.
Proposed Technical Specification Changes.
- 2.
LOCA-ECCS Safety Evaluation for Surry Units 1 and 2.
- 3.
Voucher Check for $150.
References
- 1.
- M. Y. Young, "Addendum to BART-Al:
A Computer Code for the Best Estimate Analysis of Reload Transients" (Special Report:
Thimble Modeling in Westinghouse ECCS Evaluation Model):
WCAP-9561-P, Addendum 3, Revision 1, July, 1986.
cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, GA 30323 Mr. William Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219