ML19312C504
| ML19312C504 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/20/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C499 | List: |
| References | |
| NUDOCS 7912160065 | |
| Download: ML19312C504 (3) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20566
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- *..' SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT 0x REGULATION SUPPORTING AMENDMENT NO. 40 TO FACILITY LICF'[iE NO. DPR-38 AMENDMENT N0. 40 TO FACILITY LICENSE N0. DPR-47 AMENDMENT N0. 37 TO FACILITY LICENSE NO. DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNIT N05. 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 Introduction By letter dated May 6,1977, Duke Power Company (the licensee) requested a change to paragraph 4.18.1 of the common Technical Specifications incor-porated in the operating licenses of Unit Nos.1, 2 and 3 of the Oconee Nuclear Station.
This proposed license amendment would extend the current Oconee Unit No. 2 hydraulic shock suppressors (snubbers) inspection interval to allow a limited delay in the start of the next inspection.
Discussion The proposed amendmentswould allow the licensee to continue to operate Oconee Unit No. 2 for a brief period of time past the end of the present snubber inspection interval.
If this one tim extension were not granted, Oconee Unit No. 2 would have to be shut down May 22, 1977, to perform an inspection of the inaccessible snubbers.
The initial Oconee Unit No.
2 snubber inspection in accordance with the Technical Specifications was performed on December 20, 1976.
During that inspection, 4 snubbers in the " inaccessible during normal operation" group were determined to be inoperable.
Based on paragraph 4.18.1 of the Technical Specifications, that required the next inspection to be performed in 4 months + 1 month, making the latest date to perfonn the inspection May 22, 1977. _
Since Oconee Unit No. 2 has been operating essentially continuously since the initial inspection, the licensee has, with justification, been taking advantage of the 1 month margin to avoid a shutdown just for the snubber inspection and requested this amendment as a contingency of an unexpected Oconee Unit No.1 forced outage.
Coincidently, on May 7,1977, an unplanned shutdown of Unit No.1 was required because of a leak in a steam generator.
Unless the steam generator of Unit No.1 'is repaired in time for that unit y9121so C#f '
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The purpose of this safety evaluation is therefore to determine whether a delay in performance of the snubbers inspection will have a significant impact on the health and safety of the public.
Evaluation During the initial inspection of the snubbers on Oconee Unit No. 2, 4 snubbers were found to be inoperable out of a total of 93.
In accordance with the Oconee Technical Specifications, this required going to a tightened inspection program.
Had no snubbers been found inoperable the licensee would have been permitted to go to a reduced inspection program wherein the next inspection would not have been required until 12 months + 3 months after December 20, 1976.
Thus, a ' asis has been established for requiring more frequent inspections unt.1 the licensee deomonstrates t:.at appropriate corrective measures have been taken to improve the availability of operable snubbers.
A. ver.v limited extension until June 4, 1977, which is still somewhat tightened inspection interval when compared to the initial inspection interval, is judged to be acceptable for this one time.
This is two weeks less than requested but should be adequate.
This extension represents only about a 9 percent increase in the inspection interval-that would otherwise have been allowed by the Technical Specifications.
Also, since only 4 snubbers out of a total of 93 were found to be inoperable on the initial inspection after no formal inspection requirements from installation during plar.t construction until December 1976, a period of over 3 years, there is reasonable assurance that the performance of the snubbers will not be compromised during the short extension period being considered.
We have also taken this opportunity, with the licensee's agreement, to add standard technical specification wording on maximum combined interval time.
Based en the above, the limited relaxation of the tightened inspection interval for Oconee Unit No. 2 to permit a delay until no later than June 4,1977, to conduct the next inspection of the inaccessible snubbers is acceptable.
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~ Environmental Consideration We have determined that these amendments do not authorize a change in effluent types or total amounts nor an increase -in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that these amendments involve an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental state-ment, negative declaration, or environmental appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) 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.
Date:
May 20, 1977 l
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UNITED STATES NUCLEAR REGULATORY COMilSSION DOCKET NOS. 50-269, 50-270 AND 50-287 DUKE POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U.S. Nuclear Regulatory Commission (the Comission) has issued Amendment Nos. 40, 40, and 37 to Facility Operating License Nos.
DPR-38, DPR-47, and DPR-55, respectively, issued to Duke Power Company which revised the Technical Specifications for operation of the Oconee Nuclaar Station, Unit Nos.1, 2 and 3, located in Oconee County, South Ca rol ina.
The amendments are effective as of the date of issuance.
These amendments revise paragraph 4.18.1 of the common Technical Specifications to provide a one time extension in the inspection interval for the shock suppressors (snubbers) for Oconee Unit No. 2 to not longer than June 4, 1977.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations.
The Comission has made appropriate findings as requir;d by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
The Comission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 151.5(c)(4) an environmental impact statement or negative n4 7 '? / W O W
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. declaration and environmental impact appraisal need not be prepared in l
connection with the issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated May 6, 1977, (2) Amendment Nos. 40,
40 and 37 to License Nos. DPR-38, DPR-47 and DPR-55, respectively, and (3) the Comission's related Safety Evaluation.
All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, NW., Washington, D.C. and at the Oconee County Library, 201 South Spring Street, Walhalla, Suth Carolina 29691.
A copy of items (2) and (3) may be obtained con request addressed to the U.S. Nuclear Regulatory Comission, Washington, D.C.
- 20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 20th day of May 1977.
FOR THE NUCLEAR REGULATORY COMMISSION l'
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A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
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