[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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