[Federal Register Volume 61, Number 209 (Monday, October 28, 1996)]
[Notices]
[Pages 55672-55673]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-27561]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-262]
Environmental Assessment and Finding of No Significant Impact
Regarding Termination of Facility License No. R-109 Brigham Young
University L-77 Research Reactor
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an Order terminating Facility License No. R-109 for the
Brigham Young University (BYU or the licensee) L-77 Research Reactor
located on the licensee's campus in Provo, Utah in accordance with the
application dated June 28, 1990, as supplemented on July 2, 1991; March
9, 1992; April 15, 1994; and May 30, October 9, and December 7, 1995.
Environmental Assessment
Identification of Proposed Action
By application dated June 28, 1990, as supplemented on July 2,
1991, and March 9, 1992, the licensee requested authorization to
dismantle the BYU L-77 Research Reactor, and dispose of its component
parts in accordance with the proposed decommissioning plan. The July 2,
1991, submittal also requested authorization to terminate Facility
License No. R-109. Following an ``Order Approving Decommissioning Plan
and Authorizing Decommissioning,'' dated July 23, 1992 (57 FR 33979),
the licensee completed the dismantlement and submitted a final survey
report dated April 15, 1994, as supplemented on May 30, October 9, and
December 7, 1995. Representatives of the Oak Ridge Institute for
Science and Education (ORISE), under contract to NRC, conducted a
survey of the facility on April 10 and 11, 1996. The survey is
documented in an ORISE report, ``Radiological Survey for the Brigham
Young University L-77 Research Reactor Provo, Utah,'' dated June 1996.
NRC Region IV staff, in a memorandum dated July 15, 1996, found that
the ORISE report findings support the data developed in the licensee
final survey report.
The Need for the Proposed Action
In order to release the facility for unrestricted access and use,
Facility License No. R-109 must be terminated.
Environmental Impact of License Termination
The licensee indicates that the residual contamination and dose
exposures comply with the criteria of Regulatory Guide 1.86, Table 1,
which establishes acceptable residual surface contamination levels, and
the exposure limit, established by the NRC staff, of less than 5 micro-
R/hr above background at 1 meter. The NRC verified these measurements.
The NRC finds that, since these criteria have been met, there is no
significant impact on the environment, and the facility can be released
for unrestricted use.
Alternative to the Proposed Action
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 and would deny release of
the site for unrestricted use and require continuance of the facility
license. The environmental impacts of the proposed action and the
alternative action are similar. Since the contaminated and activated
reactor and component parts have been dismantled and disposed of in
accordance with NRC regulations and guidelines, there is no alternative
with less of an environmental impact than the termination of Facility
License No. R-109.
Agencies and Persons Consulted
Personnel from the Oak Ridge Institute of Science and Education (an
NRC contractor) conducted the confirmatory survey for the BYU L-77
Research Reactor. The staff consulted with the Utah State official
regarding the environmental impact of the proposed action. The State
official had no comments.
Finding of No Significant Impact
The NRC has determined not to prepare an Environmental Impact
Statement for the proposed action. On the basis of the foregoing
Environmental Assessment, the NRC has concluded that the issuance of
the Order will not have a significant effect on the quality of the
human environment.
For further details with respect to this proposed action, see the
application for termination of Facility License No. R-109, dated June
28, 1990, as supplemented. These documents are available for public
inspection at the Commission's Public Document Room,
[[Page 55673]]
2120 L Street, N.W., Washington, D.C. 20037.
Dated at Rockville, Maryland this 21st day of October 1996.
For the Nuclear Regulatory Commission.
Seymour H. Weiss,
Director, Non-Power Reactors and Decommissioning Project Directorate,
Division of Reactor Program Management, Office of Nuclear Reactor
Regulation.
[FR Doc. 96-27561 Filed 10-25-96; 8:45 am]
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