ML23065A303
| ML23065A303 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 04/11/2023 |
| From: | Cindy Montgomery Office of Nuclear Reactor Regulation |
| To: | Charlton W University of Texas at Austin |
| Cruz H | |
| References | |
| EPID L-2022-NFA-0007 | |
| Download: ML23065A303 (1) | |
Text
April 11, 2023 Dr. William Charlton, Director Nuclear Engineering Teaching Laboratory The University of Texas at Austin Pickle Research Campus, Building 159 10100 Burnet Road Austin, TX 78758
SUBJECT:
UNIVERSITY OF TEXAS AT AUSTIN - ISSUANCE OF AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NO. R-129, FOR THE UNIVERSITY OF TEXAS AT AUSTIN TRIGA MARK II NUCLEAR REACTOR REGARDING CHANGES TO LICENSE CONDITIONS 2.B.(2)(a)(iii) AND (iv) REVISING THE SPECIFIC PLUTONIUM ISOTOPES ALLOWED (EPID NO. L-2022-NFA-0007)
Dear Dr. Charlton:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 8 to University of Texas at Austin for the University of Texas at Austin TRIGA Mark II nuclear reactor. This amendment modifies License Conditions 2.B.(2)(a)(iii) and (iv) in response to the application dated September 9, 2022 (Agencywide Documents Access and Management System Accession No. ML22269A479). This license amendment request proposes to make changes to License Conditions 2.B.(2)(a)(iii) and (iv), combining (iii) and (iv), renumbering (v) as (iv), renumbering (vi) as (v), and deleting (vi), permitting plutonium, uranium-233, and uranium-235 to be in the form of reference materials or foils, and removing the specificity of plutonium isotopes. This amendment does not modify the possession limits for plutonium, uranium-233, or uranium-235.
W. Charlton 2 A copy of the NRC staffs safety evaluation is also enclosed. If you have any questions, please contact me at (301) 415-3398, or by email to Cindy.Montgomery@nrc.gov.
Sincerely, Signed by Montgomery, Cynthia on 04/11/23 Cindy Montgomery, Project Manager Non-Power Production and Utilization Facility Licensing Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-602 License No. R-129
Enclosures:
- 1. Amendment No. 8 to Facility Operating License No. R-129
- 2. Safety Evaluation cc w/enclosures: See next page
University of Texas-Austin Docket No. 50-602 cc:
Bureau of Radiation Control Test, Research and Training State of Texas Reactor Newsletter 1100 West 49th Street Attention: Amber Johnson Austin, TX 78756 Dept of Materials Science and Engineering University of Maryland Jay Hartzell, President 4418 Stadium Drive The University of Texas at Austin College Park, MD 20742-2115 Office of the President 110 Inner Campus Drive, G3400 John G Ekerdt, PhD Austin, TX 78712-3400 The University of Texas at Austin Chemical Engineering Sharon Wood, Executive Vice President 200 E. Dean Keeton St, C0400 and Provost Austin, TX 78712-1589 The University of Texas at Austin 110 Inner Campus Drive, G1000 Dr. Richard Neptune, Dept. Chair Austin, TX 78712-3400 Walker Department of Mechanical Engineering DeAnn Walker, Director 204 E. Dean Keeton St., ETC 5.200 Office of the Governor (C2200)
Office of Budget and Policy Austin, TX 78712-1591 P.O. Box 12428 Austin, TX 78711 Roger T. Bonnecaze, Dean The Cockrell School of Engineering Paul Whaley, Associate Director 301 E. Dean Keeton St., ECJ 10th Floor Nuclear Engineering Teaching Laboratory (C2100)
The University of Texas at Austin Austin, TX 78712-2100 10100 Burnet Road, Building 159 Austin, TX 78758 Ashley Forbes, Director Radiation Materials Division, MC 233 Jim Terry, Reactor Supervisor Texas Commission on Environmental Nuclear Engineering Teaching Laboratory Quality The University of Texas at Austin P.O. Box 13087 10100 Burnet Road, Building 159 Austin, TX 78711-3087 Austin, TX 78758
ML23065A303 NRR-058 OFFICE NRR/DANU/UNPL/PM NRR/DANU/UNPL/LA OGC/NLO NRR/DANU/UNPL/BC NAME CMontgomery NParker STurk JBorromeo (HCruz for)
DATE 3/15/2023 3/20/2023 4/10/2023 4/11/2023 OFFICE NRR/DANU/UNPL/PM NAME CMontgomery DATE 4/11/2023 UNIVERSITY OF TEXAS AT AUSTIN DOCKET NO. 50-602 UNIVERSITY OF TEXAS AT AUSTIN TRIGA MARK II NUCLEAR REACTOR AMENDMENT TO FACILITY OPERATING LICENSE NO. R-129 Amendment No. 8 License No. R-129
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for an amendment to Facility Operating License No. R-129, filed by the University of Texas at Austin (the licensee) on September 9, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions, of the Commissions regulations and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105, Notice of proposed action, and publication of a notice of issuance for this amendment is not required by 10 CFR 2.106, Notice of issuance.
Enclosure 1
- 2. Accordingly, the license is amended as described in the Attachment to this license amendment. License Conditions 2.B.(2)(a)(iii), (iv), (v), and (vi) of Facility Operating License No. R-129 is hereby amended to read as follows:
2.B.(2) Pursuant to the Act and 10 CFR Part 70, Domestic Licensing of Special Nuclear Material, in connection with the operation of the facility:
(a) to receive, possess and use:
(iii) up to: 1.0 gram of uranium-233, 40.0 grams of contained uranium-235 of any enrichment, and 4.0 grams of plutonium, in the form of foils or reference materials;"
(iv) but not separate, up to 150 grams of plutonium in the form of mixed oxide pellets contained in stainless steel pins for experimental purposes; and, (v) but not separate, up to 147 grams of plutonium in the form of sealed plutonium-beryllium neutron sources.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Holly D. Digitally signed by Holly D. Cruz for Cruz Date: 2023.04.11 17:00:30 -04'00' Joshua M. Borromeo, Chief Non-Power Production and Utilization Facility Licensing Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to Facility Operating License No. R-129 Date of Issuance: April 11, 2023
ATTACHMENT TO LICENSE AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NO. R-129 TRIGA MARK II NUCLEAR REACTOR DOCKET NO. 50-602 Replace the following page of Facility Operating License No. R-129 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Facility Operating License No. R-129 Remove Insert Attachment
I. The receipt, possession, and use of the byproduct and special nuclear materials as authorized by this license will be in accordance with the Commissions regulations in 10 CFR Parts 30 and 70, including Sections 30.33, 70.23 and 70.31.
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 licensees site in Austin, Texas, and is described in the licensees 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 the operation of the facility:
(a) to receive, possess and use:
(i) but not separate, up to 9.5 kilograms of contained uranium-235 enriched to less than 20 percent 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, 40.0 grams of contained uranium-235 of any enrichment, and 4.0 grams of plutonium, in the form of foils or reference materials; (iv) but not separate, up to 150 grams of plutonium in the form of mixed oxide pellets contained in stainless steel pins for experimental purposes; and, (v) but not separate, up to 147 grams of plutonium in the form of sealed plutonium-beryllium neutron sources.
(b) to receive, possess and use, but not separate, any amount of special nuclear materials 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.
Amendment No. 8 April 11, 2023
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE R-129 UNIVERSITY OF TEXAS AT AUSTIN TRIGA MARK II NUCLEAR REACTOR DOCKET NO. 50-602
1.0 INTRODUCTION
By letter dated September 9, 2022 (Agencywide Documents Access and Management System Accession No. ML22269A479), the University of Texas at Austin (the licensee), applied for an amendment to Facility Operating License No. R-129 for the University of Texas TRIGA Mark II nuclear reactor. The license amendment request (LAR) proposed changes to the facility license License Conditions 2.B.(2)(a)(iii), (iv), (v), and (vi). According to the licensee, a pending research program requires a specific mixed plutonium reference material which is available in the form of a wire. License Condition 2.B.(2)(a)(iii) allows plutonium isotopes 239, 240, and 241 in the form of foils. License Condition 2.B.(2)(a)(iv) allows the plutonium isotope 239 in the form of reference materials. The proposed changes would permit plutonium, uranium-233, and uranium-235 to be in the form of reference materials or foils, and remove the specificity of plutonium isotopes, and combine (iii) and (iv). The licensee has not requested a change in the possession limit for plutonium; however, the licensee has requested the deletion of specific plutonium isotopes and the revision of the allowable material form (either reference materials or foils) of plutonium and uranium.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the LAR and evaluated the proposed changes to License Condition 2.B.(2) based on the following regulations and guidance:
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Section 50.10, License required; limited work authorization, paragraph (b) which states, Requirement for license. Except as provided in § 50.11 of this chapter, no person within the United States shall transfer or receive in interstate commerce, manufacture, produce, transfer, acquire, possess, or use any Enclosure 2
production or utilization facility except as authorized by a license issued by the Commission.
NUREG-1537, Part 1, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content, Appendix 14.1, Format and Content of Technical Specifications for Non-Power Reactors (ML042430055), which provides guidance to applicants and licensees on preparing research reactor license applications and TSs.
NUREG-1537, Part 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria, Chapter 14, Technical Specifications (ML042430048), which provides guidance to the NRC staff for reviewing LARs.
3.0 TECHNICAL EVALUATION
The University of Texas at Austin Nuclear Engineering Teaching Laboratory (NETL) operates a 1.1-megawatt thermal (MWt) TRIGA Mark II nuclear reactor at the Pickle Research Campus in Austin, Texas. The TRIGA design uses U-ZrH1.6 fuel clad with stainless steel in natural water convection cooling mode during operation, with a maximum decay heat that can be removed by natural convection of either water or air. The reactor is located in an open pool of purified, light water that serves as a heat sink during operations at power. The reactor can operate continuously at nominal powers up to 1.1 MWt, or in the pulsing mode with maximum power levels up to about 1,500 MWt (with a trip setpoint of 1,750 MWt) for durations of about 10 milliseconds. The pulsing mode is particularly useful in the study of reactor kinetics and control. The power level of the University of Texas at Austin TRIGA reactor is controlled by a regulating rod, two shim rods, and a transient rod.
The NETL provides nuclear analytic services to researchers, industry, and other research and industrial laboratories for testing and evaluation of materials. The NETL provides public education through tours and demonstrations. The licensee stated in the LAR that a pending research program requires the use of plutonium reference material in the form of wire. The licensee proposed changes to License Conditions 2.B.(2)(a)(iii) and (iv) to combine (iii) and (iv),
renumbering (v) as (iv), renumbering (vi) as (v), and deleting (vi), permit plutonium, uranium-233, and uranium-235 to be in the form of reference materials or foils, and remove the specificity of plutonium isotopes. Although the LAR requests changes to the specific plutonium isotope mixture in certain material forms in License Conditions 2.B.(2)(a)(iii) and (iv), the overall possession limit of 4 grams of plutonium remains unchanged. The licensee proposed combining (iii) and (iv) into a reworded (iii) and the renumbering of (iv) and (v), deleting (vi).
The current License Condition 2.B.(2), states:
(2) Pursuant to the Act and 10 CFR Part 70, Domestic Licensing of Special Nuclear Material, in connection with the operation of the facility:
(a) to receive, possess and use:
(i) but not separate, up to 9.5 kilograms of contained uranium-235 enriched to less than 20 percent 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, 30.0 grams 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) up to: 1.0 gram of plutonium-239, and 10 grams of contained uranium-235 of any enrichment, in the form of reference materials; (v) but not separate, up to 150 grams of plutonium in the form of mixed oxide pellets contained in stainless steel pins for experimental purposes; and, (vi) but not separate, up to 147 grams of plutonium in the form of sealed plutonium-beryllium neutron sources.
The proposed License Condition 2.B.(2) states:
(2) Pursuant to the Act and 10 CFR Part 70, Domestic Licensing of Special Nuclear Material, in connection with the operation of the facility:
(a) to receive, possess and use:
(i) but not separate, up to 9.5 kilograms of contained uranium-235 enriched to less than 20 percent 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, 40.0 grams of contained uranium-235 of any enrichment, and 4.0 grams of plutonium, in the form of foils or reference materials; (iv) but not separate, up to 150 grams of plutonium in the form of mixed oxide pellets contained in stainless steel pins for experimental purposes; and, (v) but not separate, up to 147 grams of plutonium in the form of sealed plutonium-beryllium neutron sources.
The NRC staff evaluated proposed License Conditions 2.B.(2), using the University of Texas at Austin license; the safety analysis report (SAR) in support of the license renewal application, dated December 12, 2011 (ML12156A097); and the guidance in NUREG-1537, Part 1, Chapter 9.5, Possession and Use of Byproduct, Source, and Special Nuclear Material, which states, in part The applicant should specify the types and quantities of radionuclides authorized.
According to the licensees LAR, small quantities of plutonium are currently and routinely used in research programs at the research reactor, and the University of Texas at Austin has a broad scope radioactive materials license which authorizes the University of Texas at Austin to receive
radioactive waste, including special nuclear material (SNM), from NETL. The Radiological Protection Program provides radiological management of the plutonium used in research programs, and the proposed amendment does not require changes to the program. The licensee stated that the proposed amendment does not affect the emergency plan or physical security plan, and requires no changes to the facility, storage and control of SNM, or NETL procedures and practices.
The licensee further stated, and the NRC staff confirmed, that the proposed amendment does not change the SAR, including the analyses of reactivity accidents, loss of coolant accidents, and fission product releases occurring from ruptures to the fuel cladding. The radiological consequences of a radiological release of irradiated material from fueled experiments are limited by the allowable production of radioactive iodine and strontium as described in the technical specifications (TSs). The proposed license amendment does not require any amendments to the TSs.
The licensee stated, and the NRC staff confirmed, that the security classification (Category 1, SNM of low strategic significance) of the facility will not change due to the proposed changes to the license, consistent with 10 CFR Part 73, Physical Protection of Plants and Materials, which treats all plutonium isotopes similarly for security purposes. The possession limits for the combined quantity of plutonium remains unchanged and the licensee provides reasonable assurance that the health and safety of the public will be protected.
The NRC staff reviewed the licensees LAR and SAR, and verified that the proposed amendment would not affect the safety or security of the facility and its operations. Based on the fact that changes to the isotope mixture of plutonium has no impact on radiological management, the facility, storage and control of SNM, and the facilitys procedures, the staff finds the licensees assertion that changing the license to allow any mixture of isotopes of plutonium rather than specific limits on certain isotopes in certain forms will have no impact on the analysis of accidents or potential radiological releases, is acceptable. The NRC staff also finds that the safety basis for finding the license amendment acceptable is consistent with previous amendments.
Based on its review, the NRC staff finds that the proposed revisions to the facility operating license, License Condition 2.B.(2), including the changes to the isotope mixture of plutonium and other proposed revisions, make no significant changes to the license or operation of the reactor. Therefore, the staff finds that the proposed changes are acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.22, Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review, paragraph (b), no environmental assessment or environmental impact statement is required for any action within the category of actions listed in 10 CFR 51.22(c). The Commission has declared these actions to be a categorical exclusion as the action does not individually or cumulatively have a significant effect on the human environment.
The proposed amendment authorizes revision of the operating license to allow any mixture of isotopes of plutonium rather than specific limits on certain isotopes in certain forms, and allows the possession and use of uranium-233 and uranium-235 in the form of reference materials or wires. The issuance of the proposed amendment is subject to the categorical exclusion in
10 CFR 51.22(c)(9) in that it meets each of the criteria specified in 10 CFR 51.22(c)(9), as set forth below:
(i) The amendment or exemption involves no significant hazards consideration
[10 CFR 51.22(c)(9)(i)];
The regulations in, 10 CFR 50.92, Issuance of amendment, paragraph (c) state that a license amendment involves no significant hazards consideration if operation of the facility, in accordance with the proposed amendment, would not (1) Involve a significant increase in the probability or consequences of an accident previously evaluated [10 CFR 50.92(c)(1)];
The amendment would revise the license to combine paragraphs (iii) and (iv),
permit plutonium, uranium-233, and uranium-235 to be in the form of reference materials or foils, and remove the specificity of plutonium isotopes to allow any mixture of isotopes of plutonium rather than require specific limits on certain isotopes in certain forms. Chapter 13, Accident Analysis, of the University of Texas at Austin SAR, as supplemented, for the application for Renewed Facility Operating License No. R-129 (ML12156A097) does not identify any differences in the safety impact of the material form of plutonium. Section 4.2.3, Neutron Moderator and Reflector (Core Structure), of the SAR states that small 0.203 inches (8 millimeters) holes at various positions in the top grid plate permit insertion of wires or foils into the core to obtain flux data. The proposed amendment makes no change in the amount of plutonium isotopes allowed by the license. The proposed amendment does not change the analyses in chapter 13, wherein the licensee previously analyzed a postulated maximum hypothetical accident that bounds all accidents at the facility, including ramp and rapid reactivity insertion events. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated, as stated in the licensees technical evaluation. The University of Texas at Austin SAR analyzes reactivity accidents, loss of reactor coolant, and fission product release from clad rupture, and these accidents are not affected by the proposed change. The licensee states that the consequences of a radiological release of irradiated material from fueled experiments are limited by allowable production of radioiodine and strontium inventory identified in TSs and this change does not require a revision to the SAR or the TSs Further, no changes are being proposed to the reactor design or hardware, or to structures, systems, and components (SSCs) that are relied upon for accident detection, mitigation, or response. In addition, the proposed LAR does not change the licensed power level of the reactor, the amount of SNM or byproduct material authorized to be possessed and used at the facility, or any potential release paths from the facility. Therefore, the NRC staff concludes that there is no significant increase in the probability or consequences of an accident previously evaluated.
(2) Create the possibility of a new or different kind of accident from any accident previously evaluated [10 CFR 50.92(c)(2)]; and The changes to License Conditions 2.B.(2)(a)(iii) and (iv) do not create any new or different accident from any accident previously evaluated. The amendment does not involve any design or hardware changes to SSCs that are relied upon for accident detection, mitigation, or response. In addition, the proposed change would not introduce any new accident scenarios, transient precursors, failure mechanisms, or limiting single failures, and there would be no adverse effect or challenges to any reactor safety-related systems as a result of the proposed amendment. Therefore, this amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) Involve a significant reduction in a margin of safety [10 CFR 50.92(c)(3)].
The changes to License Conditions 2.B.(2)(a)(iii) and (iv) do not authorize any changes in the design, function, or operation of SSCs, or change the authorized steady-state reactor power level. The proposed amendment does not alter how safety limits or limiting safety system settings are determined, change the limiting conditions for operations, or adversely affect the reliability of equipment assumed to mitigate accidents in the facility. In addition, the proposed changes do not adversely affect equipment required to safely shut down the reactor and to maintain it in a safe shutdown condition. Therefore, the NRC staff finds that this amendment does not involve a significant reduction in a margin of safety.
(ii) There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite [10 CFR 51.22(c)(9)(ii)].
The changes to License Conditions 2.B.(2)(a)(iii) and (iv) would not result in a significant change in the types or a significant increase in the amounts of fission products and effluents generated by operation of the reactor. License Condition 2.C(1) of Facility Operating License No. R-129 would continue to limit University of Texas at Austin research reactor operation to a steady-state maximum power level of 1,100 kilowatts (thermal) power and this proposed amendment would not change potential release paths from the facility or the amount of nuclear materials authorized to be possessed and used at the reactor.
The operation of the confinement building and ventilation system, as required by TS 3.3.2, Air Confinement Systems, will continue to control the amounts of effluents that may be released off site and provides reasonable assurance that releases do not exceed limits in 10 CFR Part 20, Standards for Protection against Radiation, Table 2, Appendix B. Therefore, the NRC staff finds that there is no significant change in the types or significant increase in the amounts of any effluents that may be released off site.
(iii) There is no significant increase in individual or cumulative occupational radiation exposure [10 CFR 51.22(c)(9)(iii)].
The changes to License Conditions 2.B.(2)(a)(iii) and (iv) do not significantly affect individual or cumulative occupational radiation exposure. The amendment would not change the amount of nuclear material possessed and used at the reactor, the maximum power level, or postulated accident doses. Occupational
and individual doses would remain below the limits in 10 CFR 20.1201, Occupational dose limits for adults, and 10 CFR 20.1301, Dose limits for individual members of the public. Additionally, existing TS 6.3, Operating Procedures, requires administrative controls for operating procedures that would continue to help ensure the adequacy of personnel radiation protection helping to limit individual or cumulative occupational radiation exposure. Therefore, the NRC staff finds that there is no significant increase in individual or cumulative occupational radiation exposure.
4.1 Summary The proposed license amendment changes the license to combine License Conditions 2.B.(2)(a)(iii) and (iv), permits plutonium, uranium-233, and uranium-235 to be in the form of reference materials or foils, and removes the specificity of plutonium isotopes to allow any mixture of isotopes of plutonium rather than require specific limits on certain isotopes in certain forms. The staff has determined that the amendment involves no significant hazards consideration, there is no significant change in the types or significant increase in the amounts of any effluents that may be released off site, and there is no significant increase in individual or cumulative occupational radiation exposure. Therefore, this amendment meets the eligibility criteria for a categorical exclusion stated in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: C. Montgomery, NRR Date: April 11, 2023