ML19331E125
| ML19331E125 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/25/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331E111 | List: |
| References | |
| NUDOCS 8009050530 | |
| Download: ML19331E125 (2) | |
Text
e UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGToN, D. C. 20555 SAFETY EVALUATION BY THE DIVISION OF REACTOR LICENSING SUPPORTING AMENDMENT NO. 7 TO FACILITY LICENSE NO. DPR-38 CHANGE NO. 17 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 7 TO FACILITY LIC2NSE NO. DPR-47 CHANGE NO. 12 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 4 TO FACILITY LICENSE NO. DPR-55 CHANGE NO. 4 TO TECHNICAL SPECIFICATIONS; DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-270, AND 50-287 Introduction By letter dated December 31, 14, Duke Power Company (the licensee),
requested the Oconee Station Technical Specifications be' corrected to show the number of pressurizer and main' steam line code pressure relief valves to be checked each surveillance period.
Discussion The original Technical Specification Table 4.1-2 as issued for Oconee Unit 1 and 2 specified that 50 percent of the pressurizer and 25 percent of the main steam line code pressure relief valve set points be checked each refueling period. The surveillance period was reduced from refueling to annual with the issuance of the Unit 3 license on July 19, 1974; however, the number of valves to be tested, as stated in the earlier Technical Specifications, was inadvertently omitted.
Evaluation
'This technical specification change is basically an administrative correction of a previous action.
In the Unit 3 Licensing action (Amendment Nos. 3 & 3 for Units 1 & 2) which reduced the surveillance frequency from a refueling interval to annually there was no intent by the staff to increase the number of valves that are to be tested at each check. With this change, the resulting surveillance requirements are in confor=ance with Subsection 1W3510 of Section XI of the ASME Boiler and Pressure Vessel f* %e
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2-Code dated July 1, 1974, the current standard and are adequate to provide reasonable assurance that the valves will operate when required.
Conclusion We have concluded, based on the reasons discussed above, that the author'i-zation of these changes does not involve a significant hazards considera-tion. We also conclude that there is reasonable assurance (i) that the activities authorized by these amendments can be conducted without endangering the health and safety of the public, and (ii) that such activities will be egnducted 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.
Date: February 25, 1975 O
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UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-269, 50-270, AND 50-287 DUKE POWER COMPANY NorICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES Notice is hereby given that the U.S. Nuclear Regulatory Commission (the Commission) has issued Amendments No. 7, 7, and 4 to Facility Operating Licenses No. DPR-38, DPR-47, and DPR-55, respectively, issued er Duke Power Company which revised. Technical Specifications for operation of the Oconee Nuclear Station, Units 1, 2, and 3, located in Oconee County, South Carolina. The amendments are effective as of the date of issuance.
These amendments specify the number of pressure relief valves in the pressurizer and main steam line to be checked each surveillance period, a specification inadvertently omitted in a previous license amendment.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act.of 1954, as amended (the Act), and the Consnission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter 1, which are set forth in the license amendments.
For further details with respect to this action, see (1) the application for amendments dated December 31, 1974, (2) Amendments No. 7, 7, and 4 to Licenses No. DPR-38, DPR-48, and DPR-55, with any attachments, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, NW., Washington, D.C.
and at the'Oconee County Library, 201 South Spring Street, Walhalla, South Carolina 29691.
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A copy of items (2) and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Cotanission, Washington, D.C.
20555 Attention:
Director, Division of Reactor Licensing.
Dated at Bethesda, Maryland, this 25th day of February 1975.
MR THE NUCLEAR REGULATORY COFMISSOIN
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Robert A. Purple, Chief Operating Reactors Branch (/l Division of Reactor Licensing e
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