ML19312C412
| ML19312C412 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/04/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C397 | List: |
| References | |
| NUDOCS 7912130934 | |
| Download: ML19312C412 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT N0. 37 TO FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 34 TO FACILITY OPERATING LICENSE NO. DPR-55_
DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS NOS.1, 2 AND 3 00CKETS NOS. 50-269, 50-270 AND 50-287 Introduction By letter dated June 11, 1976, Duke Power Company (the licensee) requested changes to the Technical Specifications appended to facility Operating Licenses Nos. DPR-38, DPR-47 and DPR-55 for the Oconee Nuclear Station.
These changes will increase the flux / flow trip setpoint for Unit 1 from 1.055 to 1.07.
Discussion In cur letters dated June 30, 1976, and October 22, 1976, we issued amendments to the Oconee Nuclear Station Technical Specifications which provided for the elimination of a 4.4% vent valve flow renalty for Oconee Units 2 and 3.
The June 30, 1976, amendment alst, provided surveillance requirements for all three units which would demonstrate, at each refueling outage, that the '/ent valves are not stu:k ooen.
This evaluation covers a proposed amendment to eliminate the vent valve flow penalty for Unit 1.
Evaluation In the past, a 4.6% reactor coolant flow penalty had been assumed in the thermal-hydraulic design analysis for the Oconee units.
This penalty was assessed to allow for the potential of a core vent valve being stuck open during normal cperation.
The core vent valves are incorporated into the design of the reactor internals to oreclude tne possibility of a vapor lock developing in the core following a postu"ated cold-leg break.
By letter dated January 30, 1976, we advised the licensee that we had l
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I concluded that sufficient evidence had been provided by B&W to assure that the core vent valves would remain closed during normal operation and that it could, therefore, submit an application for a license amendment to eliminate the vent valve flow penalty.
In addition, the submittal should include appropriate surveillance requirements to demonstrate, at each refueling outage, that the vent valves are not stuck open and that they operate freely.
Our evaluation of the elimination of the vent valve flow cenalty, discussed in our Safety Evaluation Report dated June 30, 1976 for Unit 2, is applicable to Unit 1 also.
In that SER we found that the elimination of this cenalty is acceptable. We therefore conclude that the elimination of the vent valve flow penalty for Unit 1 is acceptable.
The Technical Specifications proposed by the licensee reflect the elimination of the vent valve flow penalty by raising the flux / flow trip setpoint to 1.07 from 1.055.
We have determined that the 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 the amendments involve an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR %51.5(d)(4) that an environmental imoact statement or negative declaration and environmental imoact 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) 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.
Date: February 4, 1977 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETS 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 Commission) has issued Amendments Nos. 37, 37 and 34 to Facility Operating Licenses Nos. DPR-38, DPR-47 and DPR-55, respectively, issued to Duke Power Company which revised the licenses for operation of the Oconee Nuclear Station Units Nos.1, 2 and 3, located in Oconee County, South Carolina.
The amendments are effective as of the date of issuance.
These amendments will increase the flux / flow trio setpoint of the Reactor Protective System for Unit i from 1.055 to 1.07.
This increase results from the elimination of the reactor internals vent valve flow penalty.
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 Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Notice of Proposed Issuance of Amendment to Facility Operating License No. CPR-38 in connection with this action was published in the FEDERAL REGISTER on July 1S,1976 (41 FR 29229).
No request for a hearing or petition for leave to intervene was filed following notice of the proposed action.
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. The Comission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 651.5(d)(4) an environmental impact statement or negative e
declaration and environmental impact appraisal need not be prepared in Y
connection with the issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated June 11,1976,(2) Amendments Nos. 37,
37-and 34 to Licenses 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, South Carolina 29691. A copy of items (2) and (3) may be obtained upon request addressed to the U. S.
Nuclear Regulatory Comission, Washington, D. C.
20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 4th day of February 1977.
FOR THE NUCLEAR REGULATORY COMMISSION K f/ N@'Wd&
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors 6
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