[Federal Register Volume 61, Number 41 (Thursday, February 29, 1996)]
[Notices]
[Pages 7824-7825]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-4682]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-309]
Maine Yankee Atomic Power Company, Maine Yankee Atomic Power
Station; Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of an amendment to Facility Operating License No.
DPR-36, issued to Maine Yankee Atomic Power Company (the licensee), for
operation of Maine Yankee Atomic Power Station, located in Lincoln
County, Maine.
Environmental Assessment
Identification of the Proposed Action
The proposed amendment would allow the use of fuel having an
initial composition of natural or slightly enriched uranium dioxide as
fuel material, consistent with the limitation of NUREG-1432, ``Standard
Technical Specifications for Combustion Engineering Plants.''
Currently, Maine Yankee Technical Specification (TS) 1.3.A, Reactor
Core, specifies ``The maximum as-fabricated radially-averaged
enrichment of any axial enrichment zone within a fuel assembly shall be
3.95 weight percent U-235.'' The proposed action is in accordance with
the licensee's application for amendment dated August 30, 1995, as
supplemented by letter dated January 15, 1996.
The Need for the Proposed Action
The proposed amendment is needed so that the licensee may use fuel
having a higher enrichment than currently allowed by its license.
Higher
[[Page 7825]]
enrichment fuel would allow extended fuel irradiation and thus achieve
longer fuel cycles in the future.
Environmental Impacts of the Proposed Action
The Commission has completed its evaluation of the proposed
revision to the TS. The proposed revision would allow the use of fuel
having an initial composition of natural or slightly enriched uranium
dioxide as fuel material, consistent with the limitation of NUREG-1432,
``Standard Technical Specifications for Combustion Engineering
Plants.'' In effect, the fuel would be limited to a maximum uranium-235
enrichment of 4.5 weight percent, as specified in TS 4.3.1.1 and
4.3.1.2, relating to the spent fuel pool limits for storing new and
spent fuel. The safety considerations associated with the use of such
fuel have been evaluated by the NRC staff. The staff has concluded that
such a change would not adversely affect plant safety. The proposed
change has no adverse effect on the probability of any accident. No
change is being made in the types or amounts of any radiological
effluents that may be released offsite. There is no significant
increase in the allowable individual or cumulative occupational
radiation exposure.
The environmental impacts of transportation resulting from the use
of higher enrichment fuel and extended irradiation (an enveloping case
for the Maine Yankee Atomic Power Station, because fuel burnup remains
unchanged) were published and discussed in the staff assessment titled,
``NRC Assessment of the Environmental Effects of Transportation
Resulting from Extended Fuel Enrichment and Irradiation,'' dated July
7, 1988, and published in the Federal Register on August 11, 1988 (53
FR 30355), as corrected on August 24, 1988 (53 FR 32322), in connection
with Shearon Harris Nuclear Power Plant Unit 1: Environmental
Assessment and Finding of No Significant Impact. As indicated therein,
the environmental cost contribution of the proposed increase in the
fuel enrichment and irradiation limits are either unchanged or may, in
fact, be reduced from those summarized in Summary Table S-4 of 10 CFR
51.52(c). Accordingly, the Commission concludes that there are no
significant radiological environmental impacts associated with the
proposed amendment.
With regard to potential nonradiological impacts of reactor
operation with higher enrichment, the proposed action involves features
located entirely within the restricted area as defined in 10 CFR Part
20. The proposed action does not affect nonradiological plant effluents
and has no other environmental impact. Accordingly, the Commission
concludes that there are no significant nonradiological environmental
impacts associated with the proposed action.
Alternatives to the Proposed Action
Since the Commission has concluded there is no measurable
environmental impact associated with the proposed action, any
alternatives with equal or greater environmental impact need not be
evaluated. As an alternative to the proposed action, the staff
considered denial of the proposed action. Denial of the application
would result in no change in current environmental impacts. The
environmental impacts of the proposed action and the alternative action
are similar.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement for Maine
Yankee Atomic Power Station.
Agencies and Persons Consulted
In accordance with its stated policy, on October 26, 1995, the
staff consulted with the Maine State official, Mr. Patrick J. Dostie of
the Department of Human Services, regarding the environmental impact of
the proposed action. The State official had no comments.
Finding of No Significant Impact
Based upon the environmental assessment, the Commission concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the Commission has
determined not to prepare an environmental impact statement for the
proposed action.
For further details with respect to the proposed action, see the
licensee's letters dated August 30, 1995, and January 15, 1996, which
are available for public inspection at the Commission's Public Document
Room, The Gelman Building, 2120 L Street, NW, Washington, DC, and at
the local public document room located at the Wiscasset Public Library,
High Street, P.O. Box 367, Wiscasset, ME 04578.
Dated at Rockville, Maryland, this 21st day of February 1996.
For the Nuclear Regulatory Commission.
John A. Zwolinski,
Deputy Director, Division of Reactor Projects--I/II, Office of Nuclear
Reactor Regulation.
[FR Doc. 96-4682 Filed 2-28-96; 8:45 am]
BILLING CODE 7590-01-P
