ML19320C209
| ML19320C209 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/02/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML19320C210 | List: |
| References | |
| NUDOCS 8007160421 | |
| Download: ML19320C209 (3) | |
Text
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UNITED STATES E
o NUCLEAR REGULATORY COMMISSION t,
t WASHINGTON, D. C. 20555
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June 2, 1980 Docket No. 50-29 Mr. James A. Kay Senior Engineer-Licensing Yankee atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581
Dear Mr. Kay:
The Commission has issued the enclosed Amendment No. 60 to Facility Operating License No. DPR-3 for the Yankee Nuclear Power Station (Yankee-Rowe).
This amendment is in response to your application (Proposed Change No.163) dated January 30, 1980.
The amendment adds surveillance requirements for the auxiliary feedwater system in Section 3/4.7.2 " Emergency Boiler Feedwater System."
Our letter dated November 9,1979, transmitted to you our Bulletin and Orders Task Force's evaluation of the Yankee-Rowe auxiliary feedwater system.
Our evaluation identified requirements for improving auxiliary feedwater system reliability at Yankee-Rowe.
Some of these requirements involved upgrading of the Technical Specifications to avoid or mitigate potential system or operator failures.
Specifically, we requested that you propose Technical Specifications that require:
(1) at least monthly inspections to verify that each valve in the flow path that could interrupt all auxiliary feedwater flow is locked open, and (2) a flow test, before plant startup following an extended cold shutdown, to verify the normal flow path from the auxiliary feedwater system water source to the steam generators.
We have reviewed your January 30, 1980 application and find that your proposed changes to the Technical Specifications would implement our requirements and are, therefore, acceptable.
We have determined that the amendment does 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 furtherconcludedthattheamendmentinvolvesanactionwhichisins{gnificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement or negative declaration anc environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
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d s We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the proba-bility or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a signifi-i cant hazard consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by o;cr-tinn in the proposed manner, and (3) such activities will be conducted in compi*ance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
The related Notice of Issuance is also enclosed.
Sincerely, ennis
. Crutchfield, Chi Operating Reactors Branch #5 Division of Licensing
Enclosures:
1.
Amendment No. 60 to License No. DPR-3 2.
Notice of Issuance l
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