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RULE §336.2Definitions

  (40) Derived air concentration (DAC)--The concentration of a given radionuclide in air which, if breathed by the "reference man" for a working year of 2,000 hours under conditions of light work (inhalation rate of 1.2 cubic meters of air/hour), results in an intake of one ALI. DAC values are given in Table I, Column 3, of §336.359(d) of this title (relating to Appendix B. Annual Limits on Intake (ALI) and Derived Air Concentrations (DAC) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sanitary Sewerage).

  (41) Derived air concentration-hour (DAC-hour)--The product of the concentration of radioactive material in air (expressed as a fraction or multiple of the derived air concentration for each radionuclide) and the time of exposure to that radionuclide, in hours. A licensee shall take 2,000 DAC-hours to represent one, equivalent to a committed effective dose equivalent of 5 rems (0.05 sievert).

  (42) Discrete source--A radionuclide that has been processed so that its concentration within a material has been purposely increased for use for commercial, medical, or research activities.

  (43) Disposal--With regard to low-level radioactive waste, the isolation or removal of low-level radioactive waste from mankind and mankind's environment without intent to retrieve that low-level radioactive waste later.

  (44) Disposable respirator--A respirator for which maintenance is not intended and that is designed to be discarded after excessive breathing resistance, sorbent exhaustion, physical damage, or end-of-service-life renders it unsuitable for use. Examples of this type of respirator are a disposable half-mask respirator or a disposable escape-only Self-Contained breathing apparatus.

  (45) Distinguishable from background--The detectable concentration of a radionuclide is statistically different from the background concentration of that radionuclide in the vicinity of the site or, in the case of structures, in similar materials using adequate measurement technology, survey, and statistical techniques.

  (46) Diversion--The unauthorized movement of radioactive material subject to §336.357 of this title (relating to Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material) to a location different from the material's authorized destination inside or outside of the site at which the material is used or stored.

  (47) Dose--A generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, total organ dose equivalent, or total effective dose equivalent. For purposes of the rules in this chapter, "radiation dose" is an equivalent term.

  (48) Dose equivalent (HT )--The product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the rem and sievert (Sv ).

  (49) Dose limits--The permissible upper bounds of radiation doses established in accordance with the rules in this chapter. For purposes of the rules in this chapter, "limits" is an equivalent term.

  (50) Dosimetry processor--An individual or organization that processes and evaluates individual monitoring devices in order to determine the radiation dose delivered to the monitoring devices.

  (51) Effective dose equivalent (HE )--The sum of the products of the dose equivalent to each organ or tissue (HT ) and the weighting factor (wT ) applicable to each of the body organs or tissues that are irradiated.

  (52) Embryo/fetus--The developing human organism from conception until the time of birth.

  (53) Entrance or access point--Any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed radioactive materials. This includes portals of sufficient size to permit human access, irrespective of their intended use.

  (54) Environmental Radiation and Perpetual Care Account--An account in the general revenue fund established for the purposes specified in the Texas Health and Safety Code, §401.306.

  (55) Escorted access--Accompaniment while in a security zone by an approved individual who maintains continuous direct visual surveillance at all times over an individual who is not approved for unescorted access.

  (56) Exposure--Being exposed to ionizing radiation or to radioactive material.

  (57) Exposure rate--The exposure per unit of time.

  (58) External dose--That portion of the dose equivalent received from any source of radiation outside the body.

  (59) Extremity--Hand, elbow, arm below the elbow, foot, knee, and leg below the knee. The arm above the elbow and the leg above the knee are considered part of the whole body.

  (60) Federal facility waste--Low-level radioactive waste that is the responsibility of the federal government under the Low-Level Radioactive Waste Policy Act, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (42 United States Code, §2021b - 2021j). Excluded from this definition is low-level radioactive waste that is classified as greater than Class C in §336.362 of this title (relating to Appendix E. Classification and Characteristics of Low-Level Radioactive Waste).

  (61) Federal facility waste disposal facility--A low-level radioactive waste land disposal facility for the disposal of federal facility waste licensed under Subchapters H and J of this chapter (relating to Licensing Requirements for Near-Surface Land Disposal of Low-Level Radioactive Waste, and Federal Facility Waste Disposal Facility).

  (62) Filtering facepiece (dust mask)--A negative pressure particulate respirator with a filter as an integral part of the facepiece or with the entire facepiece composed of the filtering medium, not equipped with elastomeric sealing surfaces and adjustable straps.

  (63) Fingerprint Orders--Orders issued by the Nuclear Regulatory Commission or the legally binding requirements issued by Agreement States that require fingerprints and criminal history records checks for individuals with unescorted access to category 1 and category 2 quantities of radioactive material or safeguards information-modified handling.

  (64) Fit factor--A quantitative estimate of the fit of a particular respirator to a specific individual, and typically estimates the ratio of the concentration of a substance in ambient air to its concentration inside the respirator when worn.

  (65) Fit test--The use of a protocol to qualitatively or quantitatively evaluate the fit of a respirator on an individual.

  (66) General license--An authorization granted by an agency under its rules which is effective without the filing of an application with that agency or the issuance of a licensing document to the particular person.

  (67) Generally applicable environmental radiation standards--Standards issued by the EPA under the authority of the Atomic Energy Act of 1954, as amended through October 4, 1996, that impose limits on radiation exposures or levels, or concentrations or quantities of radioactive material, in the general environment outside the boundaries of locations under the control of persons possessing or using radioactive material.

  (68) Gray (Gy)--See §336.3 of this title (relating to Units of Radiation Exposure and Dose).

  (69) Hazardous waste--Hazardous waste as defined in §335.1 of this title (relating to Definitions).

  (70) Helmet--A rigid respiratory inlet covering that also provides head protection against impact and penetration.

  (71) High radiation area--An area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 0.1 rem (1 millisievert) in one hour at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.

  (72) Hood--A respiratory inlet covering that completely covers the head and neck and may also cover portions of the shoulders and torso.

  (73) Host state--A party state in which a compact facility is located or is being developed. The state of Texas is the host state under the Texas Low-Level Radioactive Waste Disposal Compact, §2.01, established under Texas Health and Safety Code, §403.006.

  (74) Individual--Any human being.

  (75) Individual monitoring--The assessment of:

    (A) dose equivalent by the use of individual monitoring devices;

    (B) committed effective dose equivalent by bioassay or by determination of the time-weighted air concentrations to which an individual has been exposed, that is, derived air concentration-hour; or

    (C) dose equivalent by the use of survey data.

  (76) Individual monitoring devices--Devices designed to be worn by a single individual for the assessment of dose equivalent such as film badges, thermoluminescence dosimeters, pocket ionization chambers, and personal ("lapel") air sampling devices.

  (77) Inhalation class--See "Class."

  (78) Inspection--An official examination and/or observation including, but not limited to, records, tests, surveys, and monitoring to determine compliance with the Texas Radiation Control Act and rules, orders, and license conditions of the commission.

  (79) Internal dose--That portion of the dose equivalent received from radioactive material taken into the body.

  (80) Land disposal facility--The land, buildings and structures, and equipment which are intended to be used for the disposal of low-level radioactive wastes into the subsurface of the land. For purposes of this chapter, a "geologic repository" as defined in 10 Code of Federal Regulations §60.2 as amended through October 27, 1988 (53 FR 43421) (relating to Definitions - high-level radioactive wastes in geologic repositories) is not considered a "land disposal facility."

  (81) Lens dose equivalent (LDE)--The external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm2 ).

  (82) License--See "Specific license."

  (83) Licensed material--Radioactive material received, possessed, used, processed, transferred, or disposed of under a license issued by the commission.

  (84) Licensee--Any person who holds a license issued by the commission in accordance with the Texas Health and Safety Code, Chapter 401 (Radioactive Materials and Other Sources of Radiation) and the rules in this chapter. For purposes of the rules in this chapter, "radioactive material licensee" is an equivalent term. Unless stated otherwise, "licensee" as used in the rules of this chapter means the holder of a "specific license."

  (85) Licensing state--Any state with rules equivalent to the Suggested State Regulations for Control of Radiation relating to, and having an effective program for, the regulatory control of naturally occurring or accelerator-produced radioactive material (NARM) and which has been designated as such by the Conference of Radiation Control Program Directors, Inc.

  (86) Local law enforcement agency (LLEA)--A public or private organization that has been approved by a federal, state, or local government to carry firearms; make arrests; and is authorized and has the capability to provide an armed response in the jurisdiction where the licensed category 1 or category 2 quantity of radioactive material is used, stored, or transported.

  (87) Loose-fitting facepiece--A respiratory inlet covering that is designed to form a partial seal with the face.

  (88) Lost or missing licensed radioactive material--Licensed material whose location is unknown. This definition includes material that has been shipped but has not reached its planned destination and whose location cannot be readily traced in the transportation system.

  (89) Low-level radioactive waste--

    (A) Except as provided by subparagraph (B) of this paragraph, low-level radioactive waste means radioactive material that:

      (i) is discarded or unwanted and is not exempt by a Texas Department of State Health Services rule adopted under the Texas Health and Safety Code, §401.106;

      (ii) is waste, as that term is defined by 10 Code of Federal Regulations (CFR) §61.2; and

      (iii) is subject to:

        (I) concentration limits established under this chapter; and

        (II) disposal criteria established under this chapter.

    (B) Low-level radioactive waste does not include:

      (i) high-level radioactive waste defined by 10 CFR §60.2;

      (ii) spent nuclear fuel as defined by 10 CFR §72.3;

      (iii) transuranic waste as defined in this section;

      (iv) byproduct material as defined by paragraph (20)(B) - (E) of this section;

      (v) naturally occurring radioactive material (NORM) waste; or


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