ML13024A041
| ML13024A041 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 01/09/2013 |
| From: | Biegalski S University of Texas at Austin |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13024A041 (5) | |
Text
Deparrment of Mechanical Engineering S*"*9 THE UNIVERSITY OF TEXAS AT AUSTIN
/ NuclearEngineering Tkaching Laboratory Austin, Texas 78758
\ AU512-232-5370" FAX-512-471-4589 .http://uwwwmne.utexas.edu/-netl/
January 9, 2013 Nuclear Regulatory Commission Attn: Document Control Desk Washington D.C., 20555-0001
Subject:
Requested Change to Facility Operating License for the University of Texas at Austin Docket 50-602 Ref : (1) Letter of March 4, 2010 (ML101250168)
(2) Letter of September 1, 2010 (ML102560381)
(3) Letter of December 18, 2012 (ML12363A040)
Madame or Sir:
A change to the University of Texas TRIGA Facility Operating License has been proposed to permit authorization of byproduct material supporting reactor operations or reactor-based research (see Ref.).
The Technical Specifications 2B(3)(a)(v) as approved specifies a 500 mCi cobalt 60 source. It was intended to capture authorization of this source in (viii) developed to identify other sealed sources.
However, section (v) the specification was not deleted in proposal, inadvertently and incorrectly increasing the authorized cobalt 60 sealed source inventory. This communication corrects that error, deleting 2B(3)(a)(v) as specification for a 500 mCi source and retaining the specified source in section 2B(3)(a)(vii). Note that the section is renumbered to reflect the deletion of item (v) form the original. In addition, it is proposed to revise "cobalt 60" to "Co-60" to make the specification consistent in context of specification for other isotopes.
The complete text of the license as amended is attached. Please contact me by phone (512-232-5373) or email (whaleyv(mail.utexas.edu) if you require clarification or further information.
P. Michael Whaley Associate Director, Nuclear Engineering Teaching Laboratory The University of Texas at Austin I declare under penalty of perjury that the foregoing is true and correct Steven R. Biegalski NETL Director cc: H. Liljestrand, Reactor Oversight Committee Chair; P. Torres, Project Manager, NRC;
- 0. E. Font, Relicense Project Manager att: Proposed License Text
UNITED STATES 9 NUCLEAR REGULATORY COMMISSION Washington, D.C. 20555 FACILITY OPERATING LICENSE DOCKET NO. 50-602 UNIVERSITY OF TEXAS AT AUSTIN Amendment No. 7 License No. R-129 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for license, filed by University of Texas at Austin, on November 9, 1984, as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. Construction of the facility was completed in substantial conformity with Construction Permit No. CPRR-123, of June 4, 1985, the provisions of the Act, and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance (i) that the activities authorized by this license can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commission's regulations; E. The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the regulations of the Commission; F. The licensee is a nonprofit educational institution and will use the facility for conducting educational activities, and has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. The issuance of this license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of the byproduct and special nuclear materials as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and 70, including Sections 30.33, 70.23 and 70.31.
License No. R-129
A. The license applies to the TRIGA Mark II nuclear reactor (the facility) owned by the University of Texas at Austin (the licensee). The facility is located on the licensee's site in Austin, Texas, and is described in the licensee's application for license of November 9, 1984, as supplemented.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the University of Texas at Austin:
(1) Pursuant to Section 104c of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Austin, Texas, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, "Domestic Licensing of Special Nuclear Material," in connection with operation of the facility:
(a) to receive, possess and use:
(i) up to 9.5 kilograms of contained uranium-235 enriched to less than 20 percent in the isotope uranium-235 in the form of TRIGA reactor fuel; (ii) up to 20 grams of contained uranium-235 of any enrichment in the form of fission chambers; (iii) up to 1.0 gram of uranium-233, 1.0 gram of contained uranium-235 of any enrichment, 1.0 gram of plutonium-240, 1.0 gram of plutonium-239, and 1.0 gram of plutonium-241 in the form of foils; (iv) 1.0 gram of plutonium-239, and 10 grams of contained uranium-235 of any enrichment in the form of reference materials; (v) 150 grams of plutonium as mixed oxide pellets contained in stainless steel pins for experimental purposes; (vi) special nuclear material in reactor-based experiments, calibration of radiation detectors, and reference sources for reactor based analytic techniques including:
sealed sources up to 0.1 mCi of Pu-239, Pu-240, Pu-241 and up to 85 mCi of Pu-238; liquid sources up to 0.1 mCi of Pu-238, Pu-239, Pu-240, and Pu-241; Page 2
License No. R-129 (b) to receive, possess, and use, but not separate, any amount of special nuclear material produced by the operation of other facilities, contained in TRIGA fuel transferred from other facilities, and (c) to possess, use, but not separate, such special nuclear material as may be produced by the operation of the facility.
(3) Pursuant to the Act and 10 CFR Part 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," in connection with operation of the facility:
(a) to receive, possess, and use:
(i) a 6-curie sealed polonium-beryllium neutron source; (ii) a 2-curie sealed americium-beryllium neutron source; (iii) 1200 micrograms of californium-252 encapsulated in stainless steel; (iv) 10 kilocuries of cobalt-60 in the form of sealed stainless steel pins; (v) up to 0.1 curie of byproduct material, atomic number 3-83, in the form of reactor components transferred from Facility Operating License No. R-92; (vi) byproduct material which is to be irradiated in the reactor within 31 days of receipt; (vii) byproduct used in reactor-based experiments, calibration of radiation detectors, and reference sources for use in reactor based analytic techniques including:
sealed sources up to:
0.1 mCi each of C-14, CI-36, Cr-51, Fe-55, Fe-59, Co-57, Mn-54, Ni-63, Zn-65, Sr-85, Y-88, Sr-90, Tc-99, Cd-109, Sn-I13, Sb-125, 1-129, Pm-147, Eu-155, TI-204, Bi-207, Pb-210, Po-210, Bi-210, Ba-133, Th-230, Np-237, and
- 500 mCi of Co-60,
- 1.0 mCi each of Cf-252, Cm 244 and Eu-152,
- 2.0 mCi of Ra-226
- 5.0 mCi of Na-22,
- 2.5 Ci of Cs-137, and Page 3
License No. R-129 1.0 Ci of Am-241; and in liquid form up to 0.1 mCi each of Mn-54, Cr-51, Co-57, Co-60, Zn-65, Sr-85, Sr-90, Y-88, Cd-109, Sn-1 13, Ba-133, Cs-137, Ce-139, Ce-141, Pm-147, Eu-152, Eu-154, Eu-155, Hg-203, Bi-207, Po-209, Np-237, Am-241, Cm-244 and 0.5 mCi of Pb-210 (b) to receive, possess, and use, but not separate, any amount of byproduct material produced by the operation of other facilities, contained in TRIGA fuel transferred from other facilities; (c) to possess and use any byproduct material produced by operation of the reactor except for byproduct material in TRIGA fuel elements; and (d) (d) to possess and use, but not separate, such byproduct material in TRIGA fuel elements as may be produced by operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in Parts 20, 30, 50, 51, 55, 70, and 73 of 10 CFR Chapter I, to all applicable provisions of the Act, and to the rules, regulations, and orders of the Commission now or hereafter in effect and to the additional conditions specified below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state power levels not in excess of 1100 kilowatts (thermal) and in the pulse mode with reactivity insertions not to exceed 2.2 percent 4k/k.
(2) Technical Specifications The Technical Specifications contained in Appendix A are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Security Plan The licensee shall fully implement and maintain in effect all provisions of the physical security plan approved by the Commission and all amendments and changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The approved plan, which is exempt from public disclosure pursuant to the provisions of 10 CFR 2.790(d), is entitled "Physical Security Plan for the UT
[University of Texas] TRIGA Mark II Reactor Facility," Revision 1, dated August 1990.
D. This license is effective as of the date of issuance and shall expire twenty years from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Date of Issuance:
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