ML15113A108
| ML15113A108 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 08/27/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15113A106 | List: |
| References | |
| NUDOCS 8409070309 | |
| Download: ML15113A108 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 130 TO FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 130 TO FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 127 TO FACILITY OPERATING LICENSE NO. DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS NOS. 1, 2, AND 3 DOCKETS NOS. 50-269, 50-270 AND 50-287 INTRODUCTION By letter dated February 10, 1983, Duke Power Company (the Licensee) proposed changes to the Technical Specifications (TSs) of Facility Operating Licenses Nos. DPR-'38, DPR-47, and DPR-55 for the Oconee Nuclear Station, Units Nos. 1, 2, and 3. These amendments would consist of changes to the Station's common TSs. Other changes requested in the February 10, 1983 submittal are still under staff review and will be addressed by separate safety evaluation and license amendment.
TSs 4.5.1.2.1, 4.5.2.2.1, 4.9.1, and 4.9.2 would be revised to make the surveillance frequencies of certain pumps and valves.consistent with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda, as required by 10 CFR 50.55a(g)(4).
EVALUATION The proposed changes are purely administrative changes to the TSs for the sake of consistency. Specification 4.0.4 already specifies the surveillance frequencies for Code-related hardware, in conformance with 10 CFR 50.55a(g)(4). The proposed changes would bring the affected sections of the TSs into conformance with TS 4.0.4 and achieve consistency with the TSs for the surveillance frequencies of certain pumps and valves which are governed by Section XI of the ASME Code. Therefore, based on our review, we find acceptable the proposed changes to the Technical Specifications.
8409070309 840827 PDR ADOCK 05000269
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-2 ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a change in surveillance requirements. We have determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released cffsite, and that there is no significant increase in individual or cumulative occupational radiation 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. 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.
CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
August 27, 1984 Principal Contributors: N. Economos, H. Nicolaras