ML20082M571

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Safety Evaluation Supporting Amends 117 & 110 to Licenses DPR-42 & DPR-60,respectively
ML20082M571
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 04/18/1995
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082M559 List:
References
NUDOCS 9504240272
Download: ML20082M571 (2)


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UNITED STATES 7

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.117 AND 110 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NVCLEAR GENERATING PLANT. UNIT NOS. 1 AND 2 DOCKET N05. 50-282 AND 50-306

1.0 INTRODUCTION

By letters dated February 23 and March 3,1995, the Northern States Power Company (NSP or the licensee) requested amendments to the Technical Specifications (TS) appended to Facility Operating License Nos. DPR-42 and DPR-60 for the Prairie Island Nuclear Generating Plant, Unit Nos. I and 2.

The proposed amendments would revise Section 4.4.A.5 of the TS, Frequency of Containment Integrated Leakage Rate Test, to reference 10 CFR Part 50, Appendix J, as modified by approved exemptions. The March 3, 1995, letter provided clarifying information within the scope of the original submittal and did not change the staff's initial proposed no significant hazards consideration determination.

2.0 EVALUATION The proposed change is administrative. TS Section 4.4.A.5 currently states that the required frequency of the containment Integrated Leakage Rate Tests (ILRT) will be in accordance with 10 CFR Part 50, Appendix J.

The change would revise Section 4.4.A.5 to add the phrase "and all approved exemptions" after the reference to 10 CFR Part 50, Appendix J.

The revised wording is consistent with that used in the revised Standard TS for the required frequency of the ILRT.

Since the change is administrative in nature, in that it references the controlling regulations directly and recognizes approved exemptions, rather than paraphrasing the regulation, the NRC staff finds the proposed change to be acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendments change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no g2pDN P

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-ou-as s-m 2-significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (60 FR 14025). Accordingly, the 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 the amendments.

5.0 QNCLUSION 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 the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: C. Thomas Date:

April 18, 1995 f

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