CA Health & Safety Code § 114985 (2021)
2021 California Code|Health and Safety Code - HSC|DIVISION 104 - ENVIRONMENTAL HEALTH|PART 9 - RADIATION|CHAPTER 8 - Radiation Control Law|ARTICLE 1 - General|Section 114985.

114985.  As used in this chapter:(a)  “Secretary” means the Secretary of the Resources Agency. (b)  “Ionizing radiation” means gamma rays and X-rays; alpha and beta particles, high-speed electrons, neutrons, protons, and other nuclear particles; but not sound or radio waves, or visible, infrared, or ultraviolet light. (c)  “Person” means any individual, corporation, partnership, limited liability company, firm, association, trust, estate, public or private institution, group, agency, political subdivision of this state, any other state or political subdivision or agency thereof, and any legal successor, representative, agent, or agency of the foregoing, other than the United States Nuclear Regulatory Commission, the United States Department of Energy, or any successor thereto, and other than federal government agencies licensed by the United States Nuclear Regulatory Commission, under prime contract to the United States Department of Energy, or any successor thereto. (d)  “Byproduct material” means any radioactive material, except special nuclear material, yielded in, or made radioactive by exposure to the radiation incident to, the process of producing or utilizing special nuclear material. (e)  “Source material” means (1) uranium, thorium, or any other material which the department declares by rule to be source material after the United States Nuclear Regulatory Commission, or any successor thereto, has determined the material to be such; or (2) ores containing one or more of the foregoing materials, in such concentration as the department declares by rule to be source material after the United States Nuclear Regulatory Commission, or any successor thereto, has determined the material in such concentration to be source material. (f)  “Special nuclear material” means (1) plutonium, uranium 233, uranium enriched in the isotope 233 or in the isotope 235, and any other material which the department declares by rule to be special nuclear material after the United States Nuclear Regulatory Commission, or any successor thereto, has determined the material to be such, but does not include source material; or (2) any material artificially enriched by any of the foregoing, but does not include source material. (g)  “General license” means a license, pursuant to regulations promulgated by the department, effective without the filing of an application, to transfer, acquire, own, possess or use quantities of, or devices or equipment utilizing, byproduct, source, or special nuclear materials or other radioactive material occurring naturally or produced artificially. (h)  “Specific license” means a license, issued after application, to use, manufacture, produce, transfer, receive, acquire, own, or possess quantities of, or devices or equipment utilizing, byproduct, source, or special nuclear materials or other radioactive material occurring naturally or produced artificially. (i)  “Registration” means the reporting of possession of a source of radiation and the furnishing of information with respect thereto, in accordance with subdivision (b) of Section 115060. (j)  “Department” means the State Department of Health Services. (k)  “Director” means the State Director of Health Services. ( l)  “Federal research and development activity” means any activity of the Secretary of Energy conducted at any research facility owned or operated by the United States Department of Energy. (m)  “Low-level waste” means radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or the byproduct material defined in Section 11(e)(2) of the Atomic Energy Act of 1954 (42 U.S.C. Sec. 2014 (e)(2)). For purposes of this subdivision, the following definitions shall apply: (1)  “High-level radioactive waste” means either of the following: (A)  The highly radioactive material resulting from the reprocessing of spent nuclear fuel, including liquid waste produced directly in reprocessing and any solid material derived from this liquid waste that contains fission products in sufficient concentrations. (B)  Other highly radioactive material that the Nuclear Regulatory Commission, consistent with existing law, determines by rule requires permanent isolation. (2)  “Spent nuclear fuel” means fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. (3)  “Transuranic waste” means any waste containing more than 100 nanocuries of alpha emitting transuranic nuclides with half-life greater than five years per gram of waste material. (n)  “Mammogram” means an X-ray image of the human breast. (o)  “Mammography” means the procedure for creating a mammogram. (p)  “Mammography quality assurance” means the detection of a change in X-ray and ancillary equipment that adversely affects the quality of films and the glandular radiation dose, and the correction of this change. (q)  “Mammogram certification” means a certification, issued by the department after registration, that the equipment dedicated to or used for mammography meets the standards prescribed pursuant to this chapter. (Added by Stats. 1995, Ch. 415, Sec. 6. Effective January 1, 1996.)