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<br /> <br />PART 43 <br />• LICENSING OF URANIUM RECOVERY FACILITIES <br />43.1 Scope and Purpose <br />(a) (1) This part provides for the specific licensing of the receipt, <br />possession, use, or disposal of radioactive material in uranium <br />recovery facilities and other operations which accept for <br />disposal byproduct material (second definition). No person shall <br />engage in such activities except as authorized in a specific <br />license issued pursuant to this part unless otherwise provided <br />for in Part 41 of these rules. <br />(2) This part provides for the implementation of certain Memoranda of <br />Understanding between the Texas Department of Health and other <br />state agencies. <br />(b) In addition to the requirements of this part, all licensees, unless <br />otherwise specified, are subject to the requirements of Parts 11, 12, <br />13, 21, 22, and 41 of these rules. <br />43.2 Definitions <br />• As used in this part, the following definitions apply: <br />"Aquifer" means a geologic formation, group of formations, or part of a <br />formation capable of yielding a significant amount of groundwater to <br />wells or springs. Any saturated zone created by uranium or thorium <br />recovery operations would not be considered an aquifer unless the zone <br />is or potentially is: <br />(1) hydraulically interconnected to a natural aquifer; <br />(2) capable of discharge to. surface water; or <br />(3) reasonably accessible because of migration beyond the vertical <br />projection of the boundary of the land transferred for long-term <br />government ownership and care in accordance with 43.95. <br />"Byproduct material" means: <br />(1) any radioactive material (except special nuclear material) <br />yielded in or made radioactive by exposure to the radiation <br />incident to the process of producing or utilizing special nuclear <br />material; and <br />(2) the tailings or wastes produced by or resulting from the <br />extraction or concentration of uranium or thorium from any ore <br />processed primarily for its source material content, including <br />• discrete surface wastes resulting from uranium solution extrac- <br />tion processes, and other tailings having similar radiological <br />characteristics. <br />43 - 1 (April 1990) <br />