[Federal Register Volume 71, Number 145 (Friday, July 28, 2006)]
[Notices]
[Pages 42882-42884]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-12105]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-128, EA-06-166]


In the Matter of Texas A&M University, (Nuclear Science Center 
TRIGA Research Reactor); Order Modifying Amended Facility Operating 
License No. R-83

I.

    The Texas A&M University (the licensee) is the holder of Amended 
Facility Operating License No. R-83 (the license). The license was 
issued on December 7, 1961, by the U.S. Atomic Energy Commission and 
subsequently renewed on March 30, 1983, by the U.S. Nuclear Regulatory 
Commission (the NRC or the Commission). The license includes 
authorization to operate the Nuclear Science Center TRIGA Research 
Reactor (the facility) at a power level up to 1,000 kilowatts thermal 
and to receive, possess, and use special nuclear material associated 
with the operation. The facility is on the campus of the Texas A&M 
University, in the city of College Station, Brazos County, Texas. The 
mailing address is Nuclear Science Center, Texas Engineering 
Experimental Station, Texas A&M University, 3575 TAMU, College Station, 
Texas 77843-3575.

II.

    On February 25, 1986, the Commission promulgated a rule, Section 
50.64 of Title 10 of the Code of Federal Regulations (10 CFR), limiting 
the use of high-enriched uranium (HEU) fuel in domestic research and 
test reactors (non-power reactors). This regulation requires that if 
Federal Government funding for conversion-related costs is available, 
each licensee of a research and test reactor authorized to use HEU fuel 
shall replace it with low-enriched uranium (LEU) fuel. The Commission's 
stated purpose for these requirements was to reduce, to the maximum 
extent possible, the use of HEU fuel in order to reduce the risk of 
theft and diversion of HEU fuel used at research and test reactors 
(51FR 6514).
    The provisions of 10 CFR 50.64(c)(2)(iii) require the licensee to 
include in its conversion proposal, to the extent required to effect 
conversion, all necessary changes to the license, the facility, and 
licensee procedures.

III.

    On June 13, 2006, the licensee submitted a letter as part of its 
conversion proposal, which indicated that changes to the Uranium-235 
possession limit in its license were needed to support the proposed 
schedule for conversion to LEU fuel. The possession of the LEU fuel is 
required by the licensee at this time to prepare the fuel in bundles in 
order to meet the proposed timely conversion. The LEU fuel contains the 
Uranium-235 isotope at an enrichment of less than 20 percent. The NRC 
staff reviewed the licensee's proposal and the requirements of 10 CFR 
50.64, and has determined that the public health and safety and common 
defense and security require the licensee to receive and possess the 
LEU fuel so that the LEU fuel may be prepared to convert from HEU fuel 
in accordance with the schedules planned by the Department of Energy to 
support U.S. non-proliferation policies. Issuance of this Order will, 
therefore, allow the conversion to proceed in accordance with the 
planned schedule. The NRC staff also determined that there should be a 
prohibition on receiving additional HEU fuel and a reduction in the 
associated authorized possession limit concurrent with the 
effectiveness of the amendment authorizing receipt and possession, but 
not use, of the LEU fuel. The specific conditions needed to reduce the 
HEU fuel possession limit, to amend the facility license to allow 
possession of the LEU fuel, and to be made a part of the license in 
accordance with this Order are:

2.B.(2) Pursuant to the Act and 10 CFR Part 70, ``Domestic Licensing 
of Special Nuclear Material,'' to possess and use up to 12.0 
kilograms of contained Uranium-235 at enrichment equal to or less 
than 70 percent in connection with operation of the reactor.
2.B.(8) Pursuant to the Act and 10 CFR Part 70, ``Domestic Licensing 
of Special Nuclear Material,'' to receive and possess, in addition 
to the amount specified under License Condition 2.B.(2), up to 15.0 
kilograms of contained Uranium-235 at enrichments equal to or less 
than 20 percent.

    The attached safety evaluation provides additional details on the 
NRC staff analyses resulting in the determination to order these 
changes.

IV.

    Accordingly, pursuant to Sections 51, 53, 57, 101, 104, 161b, 161i, 
and 161o of the Atomic Energy Act of 1954, as amended, and to 
Commission regulations in 10 CFR 2.202 and 10 CFR 50.64, it is hereby 
ordered that: 
    Amended Facility Operating License No. R-83 is modified by amending 
the license to include the license conditions as stated in Section III 
of this Order. This Order will be effective 20 days after the date of 
publication of this Order in the Federal Register.

[[Page 42883]]

V.

    Pursuant to the Atomic Energy Act of 1954, as amended, any person 
adversely affected by this Order may submit an answer to this Order, 
and may request a hearing on this Order, within 20 days of the date of 
this Order. The answer may consent to this Order. Any answer or request 
for a hearing shall set forth the matters of fact and law on which the 
licensee, or other person adversely affected, relies and the reasons 
why the Order should not have been issued. Any answer or request for a 
hearing shall be filed (1) by first class mail addressed to the Office 
of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) by 
courier, express mail, and expedited delivery services to the Office of 
the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville 
Pike, Rockville, Maryland 20852, Attention: Rulemaking and 
Adjudications Staff. Because of continuing disruptions in delivery of 
mail to the United States Government Offices, it is requested that 
answers and/or requests for hearing be transmitted to the Secretary of 
the Commission either by e-mail addressed to the Office of the 
Secretary, U.S. Nuclear Regulatory Commission, [email protected]; 
or by facsimile transmission addressed to the Office of the Secretary, 
U.S. Nuclear Regulatory Commission, Washington, DC, Attention: 
Rulemakings and Adjudications Staff at 301-415-1101 (the verification 
number is 301-415-1966). Copies of the request for hearing must also be 
sent to the Director, Office of Nuclear Reactor Regulation and to the 
Assistant General Counsel for Materials Litigation and Enforcement, 
Office of the General Counsel, with both copies addressed to the U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, and the NRC 
requests that a copy also be transmitted either by facsimile 
transmission to 301-415-3725 or by e-mail to [email protected]. If 
a person other than the licensee requests a hearing, he or she shall 
set forth in the request for a hearing with particularity the manner in 
which his or her interest is adversely affected by this Order and shall 
address the criteria set forth in 10 CFR 2.309. If a hearing is 
requested by the licensee or a person whose interest is adversely 
affected, the Commission shall issue an Order designating the time and 
place of any hearing. If a hearing is held, the issue to be considered 
at such hearing shall be whether this Order should be sustained.
    In accordance with 10 CFR 51.10(d) this Order is not subject to 
Section 102(2) of the National Environmental Policy Act, as amended. 
The NRC staff notes, however, that with respect to environmental 
impacts associated with the changes imposed by this Order, as described 
in the safety evaluation attached, the changes would, if imposed by 
other than an Order, meet the definition of a categorical exclusion in 
accordance with 10 CR 51.22(c)(9). Thus, pursuant to either 10 CFR 
51.10(d) or 51.22(c)(9), no environmental assessment nor environmental 
impact statement is required.
    For further information see the June 13, 2006, letter from the 
licensee (Agencywide Documents Access and Management System (ADAMS) 
Accession No. ML061720033), and the NRC staff's safety evaluation 
attached to this Order (ADAMS Accession No. ML061810481), available for 
public inspection at the Commission's Public Document Room (PDR), 
located at One White Flint North, Public File Area O1 F21, 11555 
Rockville Pike (first floor), Rockville, Maryland. Publicly available 
records will be accessible electronically from the ADAMS Public 
Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to 
ADAMS or who have problems in accessing the documents in ADAMS should 
contact the NRC PDR reference staff by telephone at 1-800-397-4209 or 
301-415-4737 or by e-mail to [email protected].

    Dated this 21st day of July 2006.
    For the Nuclear Regulatory Commission.
J.E. Dyer,
Director, Office of Nuclear Reactor Regulation.

Attachment

Safety Evaluation by the Office of Nuclear Reactor Regulation 
Supporting Order on Possession Limit Changes To Allow Conversion From 
High-Enriched to Low-Enriched Uranium Fuel

1.0 Introduction
    By letter dated June 13, 2006, the Texas A&M University (the 
licensee) indicated that changes to the Nuclear Science Center (NSC) 
TRIGA Research Reactor possession limit was needed to allow for the 
timely conversion from the use of high-enriched uranium (HEU) fuel to 
low-enriched uranium (LEU) fuel in accordance with Sec.  50.64 of Title 
10 of the Code of Federal Regulations (10 CFR). This regulation was 
promulgated to reduce the risk of theft and diversion of HEU fuel used 
in non-power reactors. The U.S. Nuclear Regulatory Commission (NRC) 
staff determined as discussed below that the following changes to the 
possession limit license conditions were acceptable. The change to the 
current License Condition 2.B.(2) removes the authority to receive HEU 
fuel and decreases the possession limit of contained Uranium-235 (U-
235) with enrichments up to 70 percent from 17.0 to 12.0 kilograms 
(kgs) to allow the continued possession and use of material at the 
facility. The changes also involve the addition of License Condition 
2.B.(8) to allow receipt and possession, but not use, of up to an 
additional 15 kgs of contained U-235 at enrichments equal to or less 
than 20 percent (LEU fuel).
2.0 Background
    The license currently includes a possession limit of special 
nuclear material to allow for operation of the facility. This limit 
allows for an amount of special nuclear material so that the facility 
can continue to conduct its licensed research reactor activities.
    In its June 13, 2006, letter, the licensee indicated that an 
increase to the possession limit for special nuclear material is 
required to allow for the timely conversion to LEU fuel. The licensee 
indicated that it is working with the U.S. Department of Energy (DOE), 
DOE contractors, and the NRC to convert the NSC TRIGA Research Reactor 
from HEU fuel to LEU fuel in support of non-proliferation policies. The 
licensee's letter stated that in order to avoid prolonged reactor 
shutdown and accomplish the conversion in support of non-proliferation 
goals, a period will exist in which the NSC TRIGA Research Reactor will 
need to possess a quantity of U-235 in excess of the current licensed 
maximum. As additional evidence, the licensee also provided a DOE 
letter dated April 13, 2006. In the April 13, 2006, letter, DOE 
indicated that the project schedule for conversion includes shipping a 
fresh fuel core to replace the fuel currently in the reactor. Further, 
DOE indicated that in order to support the timeliness of this effort as 
planned, the license will need an increase in the special nuclear 
material possession limit to accommodate the fuel inventory at the 
facility during the process.
3.0 Evaluation
    The licensee has not requested any changes to the Technical 
Specifications (TSs) nor security plan. Thus, the additional material 
will be received and possessed under the current terms of the reactor 
license. The NRC staff reviewed the license, TSs, and security plan 
requirements for the facility and finds that the possession of the 
additional

[[Page 42884]]

LEU fuel will not require additional safety or security controls or 
conditions beyond those already in place. The NRC staff also finds that 
this increase in the fuel possession limit is within the normal 
possession limit for research reactors.
    The increased possession limit does not allow operation with the 
fuel other than that already authorized by the license and TSs. This 
change does not authorize conversion to the new LEU fuel planned for 
conversion, i.e., 30 weight percent (Wt%) vice the currently authorized 
9 Wt%. (The authorization for conversion will be the subject of an 
ongoing separate evaluation). Therefore, the radioactive fission 
product inventory will not be increased by the increased fuel 
possession limit and the routine effluent or potential accident release 
levels will not increase beyond those already analyzed and accepted 
under the current license and TSs.
    Further, in accordance with the existing TSs, reactor fuel will be 
stored in a geometrical array where the effective multiplication is 
less than 0.8 for all conditions of moderation. Therefore, the 
potential for accidental criticality is not increased with the 
increased fuel possession limit.
    The increase in the special nuclear material possession limit does 
not impact the security requirements for the facility. In accordance 
with 10 CFR 73.2, the increase possession would be consistent with 
special nuclear material of moderate strategic significance (Category 
II). The licensee's current security plan meets or exceeds the 
requirements for this level of material under 10 CFR 73.67(d).
    The license changes are to allow for conversion in a manner that is 
timely to support the non-proliferation goals of the nation and allow 
continued research and development in accordance with the license and 
regulations. They do not change the security plan requirements which 
are consistent the provisions of 10 CFR 73.67(d) for special nuclear 
material of moderate strategic significance (Category II) in accordance 
with 10 CFR 73.2, because the addition of the LEU fuel is within the 
possession limit for that category of material.
    The inspection program has found that the licensee has routinely 
used such material safely and securely.
    The licensee submitted a proposed license condition in its June 13, 
2006, letter. The NRC staff noted several changes from the proposed 
license condition were needed to allow for possession of the current 
material and allow for receipt, but not use, of the new LEU fuel. 
Specifically, the licensee's authority to receive additional HEU fuel 
is removed from License Condition 2.B.(2), and the amount of material 
possessed under that license condition was reduced from 17.0 to 12.0 
kg. Further, License Condition 2.B.(8) is added to allow for the 
receipt and possession, but not use, of the LEU fuel for conversion. A 
telephone conversation between the project manager and the Associate 
Director of the NSC TRIGA Research Reactor facility on July 6, 2006, 
confirmed that these differences were understood and could be 
implemented consistent with protecting the public health and safety.
    Because the requested increased possession limit may be possessed 
safely and securely under the terms of the existing TSs and security 
plan, the increase in special nuclear material possession limit as 
specified above is acceptable to the NRC staff. Further, the NRC staff 
has determined that the public health and safety and the common defense 
and security require the licensee to receive and possess the LEU fuel 
so that the LEU fuel may be configured into fuel bundles to convert 
from HEU fuel in accordance with the schedule planned by the DOE to 
support U.S. non-proliferation policies.
3.0 Environmental Consideration
    In accordance with 10 CFR 51.10(d), an Order is not subject to 
Section 102 of the National Environmental Policy Act. The NRC staff 
notes, however, that even if these changes were not being imposed by an 
Order, the changes would not require an environmental impact statement 
or environmental assessment. The license changes involve use of a 
facility component located within the restricted area as defined in 10 
CFR part 20 or changes in inspection and surveillance requirements. The 
NRC staff has determined that the changes involve no significant 
increase in the amounts or types of any effluents that may be released 
off site and no significant increase in individual or cumulative 
occupational radiation exposure. Therefore, pursuant to 10 CFR 
51.22(b), no environmental impact statement or environmental assessment 
is required.
4.0 Conclusion
    The NRC staff has concluded, on the basis of the considerations 
discussed above, that (1) The proposal by the licensee for possession 
of LEU fuel is consistent with and in furtherance of the requirements 
of 10 CFR 50.64, (2) there is reasonable assurance that the health and 
safety of the public will not be endangered by the proposed activities; 
and (3) such activities will be conducted in compliance with the 
Commission's regulations and will not be inimical to the common defense 
and security or the health and safety of the public. Accordingly, it is 
concluded that an enforcement order as described above should be issued 
pursuant to 10 CFR 50.64(c)(3).


    Dated: July 21, 2006.
M. Mendonca.
Principal Contributor:
 [FR Doc. E6-12105 Filed 7-27-06; 8:45 am]
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