ML20206F012
| ML20206F012 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/10/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206F009 | List: |
| References | |
| NUDOCS 8606240097 | |
| Download: ML20206F012 (2) | |
Text
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. as FACILITY OPERATING LICENSE NO. NPF-4 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338
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Introduction:==
By letter dated February 5,1986, the Virginia Electric and Power Company (the licensee) proposed a change to the Technical Specifications (TS) for the North Anna Power Station, Unit No. 1 (NA-1). Specifically, the proposed change would correct a typographical error presently existing in the NA-TS Table 3.3-1 which identifies instrument operability requirements and associated action statements for Reactor Trip System (RTS) instrumentation.
Discussion:
The proposed changes to the NA-1 Table 3.3-1 correct a typographical error in the action statements for the Overtemperature Delta T and Overpower Delta T trip function instrumentation. Action statement number 2 is presently specified. The correct action statement number is 7.
Correcting this error makes the Unit I table consistent with Unit 2 and the Westinghouse Standard TS.
It is believed that the presently specified number is the result of a typographical error which was introduced during initial plant licensing.
Action statement number 2 is clearly not applicable as it refers to nuclear instrumentation inoperability. The licensee intends to follow the correct l
action statement (i.e., #7) for these trip functions during three loop operation pending correction of this error.
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Evaluation:
The proposed change is administrative in nature and corrects an error as presently specified in the NA-1 TS Table 3.3-1.
In addition, the proposed change would provide consistency to the NA-1A2 TS and be in conformance with the NRC approved Westinghouse Standard TS. Therefore, we find the proposed change to be acceptable.
8606240097 860610 PDR ADOCK 05000338 p
8 Environmental Consideration:
This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no 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 Comission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).
Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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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 Comission's regulations, and the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Date: June 10,1986 Principal Contributor:
L. Engle
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