ML20082M878
| ML20082M878 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/18/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082M873 | List: |
| References | |
| NUDOCS 9504240410 | |
| Download: ML20082M878 (2) | |
Text
i i
- psora
~O-ye
_4 UNITED STATES j
E NUCLEAR REGULATORY COMMISSION
{
WASHINGTON, D.C. 20eeM001 h
%..... p$
l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.1% TO FACILITY OPERATING LICENSE N0. DPR-32 AND AMEN 0 MENT NO.1% TO FACILITY OPERATING LICENSE NO.' DPR-37 VIRGINIA ELECTKIC AND POWER COMPANY SURRY POWER STATION. UNIT NOS. 1 Alm 2 QOCKET NOS. 50-280 AND 50-281 I
l
1.0 INTRODUCTION
l By letter dated February 14, 1995, the Virginia Electric and Power Company I
(the licensee) submitted a request for changes to the Surry Power Station, Units I and 2 Technical Specifications (TSs). The requested changes would revise Section 4.4.D. of the TS, Retest Schedule, to reference 10 CFR Part 50, j
Appendix J, as modified by approved exemptions, directly.
i 2.0 EVALUATION The proposed change is administrative. TS Section 4.4.D. currently paraphrases 10 CFR Part 50, Appendix J, for the required frequency of the containment Integrated Leakage Rate Test (ILRT). The change would revise Section 4.4.D. to reference 10 CFR Part 50, Appendix J, as modified by approved exemptions, directly. The revised wording is consistent with that used in the revised Standard Technical Specifications for the required frequency of the ILRT. Since the change is administrative in nature,.in that t
it references the controlling regulations directly and recognizes approved i
exemptions, rather than paraphrasing the regulation, the NRC staff finds the i
proposed change to be acceptable.
j
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendment. The State official had no comment.
4.0 ENVIR0letENTAL CONSIDERATION The amendments change a requirement with respect to installation or use of a i
facility component located within the restricted area as defined in 10 CFR i
Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant charige in the types.
of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation i
I 950424o41o 95o41e PDR ADOCK o O
p
2 exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (60 FR
).
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the'public.
Principal Contributor:
B. Buckley Date: April 18, 1995