ML102560381
| ML102560381 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 09/01/2010 |
| From: | Whaley P University of Texas at Austin |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML102560381 (10) | |
Text
Deparuncnt of Mechanical Engineering THE UNIVERSITY OF TEXAS AT AUSTIN S.Nuclear EngineeringTeaching Laboratory -Austin, Texas 78758 512-232-5370 " FAX 512-471-4589 htrp.'//www.me.utexas.edul-netl/
September 1, 2010 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 Ref: (1) Letter of March 28'2008 (ML080920755) Docket 50-602 (2) Letter of March 4, 2010 (ML101250168) Docket 50-602 Madame or Sir:
On March 10, 2010, a proposal was submitted for a change to the University of Texas at Austin Facility License R-129. The proposed change would have permitted authorization of byproduct material in new categories, related to the reactor operations or reactor-based research. On further consideration, the proposal is herein modified to identify specific isotopes and form. Excerpts of sections of the current license are provided below, followed by the revised form with the changes inserted at 2.B (2) (a) (vi) and 2.B (3) (a) (viii) for your consideration.
Current License:
2.B(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; (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.
2B(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 califomium-252 encapsulated in stainless steel; (iv) 10 kilocuries of cobalt-60 in the form of sealed stainless steel pins; (v) 500 mCi of Cobalt 60 in the form of sealed sources (vi) 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; (vii) byproduct material which is to be irradiated in the reactor within 31 days of receipt; (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) to possess and use, but not separate, such byproduct material in TRIGA fuel elements as may be produced by operation of the facility Change to:
2.B(2) Pursuant to the Act and 10 CFR Part 70, "Domestic Licensing of Special Nuclear Material," in connection with operation of the facility:
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(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 ofplutonium-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; (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.
2B(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) I sealed americium-beryllium neutron source; a 2-curie Page 3
(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) 500 mCi of Cobalt 60 in the form of sealed sources (vi) 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; (vii) byproduct material which is to be irradiated in the reactor within 31 days of receipt; (viii) 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, C1-36, Fe-55, Fe-59, Co-57, Mn-54, Ni-63, Zn-65, Sr-90, Tc-99, Cd-109, Sn-i 13, Sb-125, 1-129, Pm-147, Eu-155, Ti-204, Bi-207, Pb-210, Po-210, Bi-2 10, Ba-133, Th-230, Np-237, and 500 mCi of cobalt-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 1.0 Ci of Am-241; and in liquid form up to 0.1 mCi each of Mn-54, Co-57, Co-60, Zn-65, Sr-85, Sr-90, Y-88, Cd-109, Sn- 113, 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 Page 4
(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.
Justification:
As previously submitted The complete test of the license as amended is attached.
Please contact me by phone (512-232-5373) or email (whaley(2mail.utexas.edu) if you require clarification or further information.
P. Michael Whaley Associate Director Nuclear Engineering Te ching Laboratory The University of Texas at Austin 512-232-5373 I declare under penalty of perjury that the foregoing is true and correct Steven R. Biegalski NETL Director cc: S. Biegalski, Director H. Liljestrand, Reactor Oversight Committee Chair L Tran, Project Manager, NRC C. Montgomery, NRC att: Proposed License Text Page 5
UNITED STATES NUCLEAR REGULATORY COMMISSION 00 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 requirementsof 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 thislicense 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
License No. R- 129 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.
- 2. Facility License No. R-129 is hereby issued to the University of Texas at Austin as follows:
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; Page 2
License No. R-129 liquid sources up to 0.1 mCi of Pu-238, Pu-239, Pu-240, and Pu-241; (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) 500 mCi of Cobalt 60 in the form of sealed sources (vi) 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; (vii) byproduct material which is to be irradiated in the reactor within 31 days of receipt; (viii) 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, Fe-55, Fe-59, Co-57, Mn-54, Ni-63, Zn-65, Sr-90, Tc-99, Cd-109, Sn- 113, Sb-125, 1-129, Pm-147, Eu-155, T1-204, Bi-207, Pb-210, Po-210, Bi-210, Ba-133, Th-230, Np-237, and 500 mCi of cobalt-60, 1.0 mCi each of Cf-252, Cm 244 and Eu-152, 2.0 mCi of Ra-226 Page 3
License No. R- 129
- 5.0 mCi of Na-22, 2.5 Ci of Cs-137, and 1.0 Ci of Am-241; and in liquid form up to 0.1 mCi each of Mn-54, Co-57, Co-60, Zn-65, Sr-85, Sr-90, Y-88, Cd-109, Sn-i 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.
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License No. R-129 FOR THE NUCLEAR REGULATORY COMMISSION Date of Issuance:
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