ML20111B461
| ML20111B461 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/03/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20111B410 | List: |
| References | |
| NUDOCS 8501080644 | |
| Download: ML20111B461 (2) | |
Text
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n rer UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON. D. C. 20555 g
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NO. 59 AND NO.43 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION, UNITS NO. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
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Introduction:==
By letters dated July 26, 1983 and March 30, 1984 the Virginia Electric and Power Company (the licensee) requested a change to the Technical Specifications (TS) to Facility Operating License Nos. NPF-4 and NPF-7 for the. North Anna Power Station, Units No. I and No. 2 (NA-1&2). The proposed changes would allow the licensee to submit the Core Surveillance Report at a reduced time interval with In addition, in the event that the F specific written approval by the NRC.
limit should change requiring a new Core Surveillance Report submittal or aEY amended submittal, the Core Surveillance Report would be submitted 60 days prior to the date the limit would become effective unless otherwise approved by Commission Letter.
Discussion:
As presently specified in the NA-1&2 TS, the Core Surveillance Report which describes the F limits and the surnilMce power level for each reload cycle must be s5funitted to the NRC 50 days prior to initial criticality for each reload cy::le. The licensee's proposed change would permit a reduction in the time that a report must be submitted prior to criticality providing the time reduction has been approved by NRC letter. The reduction in submittal time will allow more flexibility in scheduling core design tasks and refueling outage planning.
Evaluation:
Use of the proposed change represents a reduction in the time interval (prior i
to initial criticality) for subn:itting the Core Surveillance Report to the NRC.
However, use of the proposed change requires prior written approval by the NRC.
In addition, the change will not affect the validity of information and conclusions contained in the Core Surveillance Report nor will it affect required axial power distribution surveillance. Finally, the proposed change is consistent with the provisions of NUREG-0452, Revision 4, Standard Technical Specifications W'DWOS 38 P
.. for Westinghouse PWRs, dated fall 1981 which are appropriately applied to NA-1&P. Therefore, on this basis, we find the proposed changes to be acceptable.
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.
The staff has 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 offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, these amend-ments 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.
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Conclusion:==
We have concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner, and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Comission's regula-tions and the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Date: December 3, 1984 Principal Contributors L. Engle, DL/0RBf3 M. Chatterton DSI/CPB