Tenn. Comp. R. & Regs. 0400-20-04-.04 - DEFINITIONS

(1) As used in these rules, these terms have the definitions set forth below. (For additional definitions used only in Chapters 0400-20-05, 0400-20-06, 0400-20-07, 0400-20-08 and 0400-20-09, see Rules 0400-02-05-.32, 0400-20-06-.03, 0400-20-07-.05, 0400-20-08-.03 and 0400-20-09-.03.)

(a)

1. "A₁" means the maximum activity of special form radioactive material permitted in a Type A package. This value is either listed in Table A-1 of Schedule 10-6 in Rule 0400-20-10-.38, or may be derived in accordance with the procedures prescribed in Schedule 10-6 in Rule 0400-20-10-.38.

2. "A₂" means the maximum activity of radioactive material, other than special form material, LSA, and SCO material, permitted in a Type A package. This value is either listed in Table A-1 of Schedule 10-6 in Rule 0400-20-10-.38, or may be derived in accordance with the procedure prescribed in Schedule 10-6 in Rule 0400-20-10-.38.

(b) "Accelerator-produced radioactive material" means any material made radioactive by a particle accelerator.

(c) "Agreement State" means any state with which the U.S. Nuclear Regulatory Commission has entered into an effective agreement under Section 274 b. of the Atomic Energy Act of 1954, as amended.

(d) "Alert" means a classification for events that are in progress, may occur, or have occurred that could lead to a release of radioactive material(s) but that the release is not expected to require a response by an offsite response organization to protect persons offsite.

(e) "Authorized nuclear pharmacist". Defined in Rule 0400-20-07-.05.

(f) "Authorized user". Defined in Rule 0400-20-07-.05.

(g) "Barrier" means attenuating materials used to reduce radiation exposure.

1. "Primary". Barrier sufficient to attenuate the useful beam to the required degree at a distance no greater than 8 centimeters beyond the barrier.

2. "Secondary". Barrier sufficient to attenuate scattered and leakage radiation to the 1 It is reasonable to assume that individuals will not occupy the area within 8 centimeters of the barrier continuously.

(h) "Calibration" means the determination of:

1. The response or reading of an instrument relative to a series of known radiation values over the range of the instrument, or

2. The strength of a source of radiation relative to a standard.

(i) "Carrier" means a person engaged in the transportation of passengers or property by land or water as a common, contract, or private carrier, or by civil aircraft.

(j) "Certificate holder" means a person who has been issued a certificate of compliance or other package approval by the U.S. Nuclear Regulatory Commission (U.S. NRC or NRC).

(k) "Certificate of Compliance" (CoC) means the certificate issued by the U.S. NRC under 10 CFR 71 subpart D which approves the design of a package for the transportation of radioactive material.

(l) "Close reflection by water" means immediate contact by water of sufficient thickness for maximum reflection of neutrons.

(m) "Commencement of construction" means taking any action defined as "construction" or any other activity at the site of a facility subject to the rules in this Division 0400-20 that has a reasonable nexus to radiological health and safety.

(n) "Consignment" means each shipment of a package or groups of packages or load of radioactive material offered by a shipper for transport.

(o) "Consortium" means an association of medical use licensees and a PET radionuclide production facility in the same geographical area that jointly own or share in the operation and maintenance cost of the PET radionuclide production facility that produces PET radionuclides for use in producing radioactive drugs within the consortium for noncommercial distributions among its associated members for medical use. The PET radionuclide production facility within the consortium must be located at an educational institution or a Federal facility or a medical facility.

(p) "Construction" means the installation of foundations, or in-place assembly, erection, fabrication, or testing for any structure, system, or component of a facility or activity subject to the rules in this Division 0400-20 that are related to radiological safety or security. The term "construction" does not include:

1. Changes for temporary use of the land for public recreational purposes;

2. Site exploration, including necessary borings to determine foundation conditions or other preconstruction monitoring to establish background information related to the suitability of the site, the environmental impacts of construction or operation, or the protection of environmental values;

3. Preparation of the site for construction of the facility, including clearing of the site, grading, installation of drainage, erosion and other environmental mitigation measures, and construction of temporary roads and borrow areas;

4. Erection of fences and other access control measures that are not related to the safe use of, or security of, radiological materials.

5. Excavation;

6. Erection of support buildings (e.g. construction equipment storage sheds, warehouse and shop facilities, utilities, concrete mixing plants, docking and unloading facilities, and office buildings) for use in connection with the construction of the facility;

7. Building of service facilities (e.g. paved roads, parking lots, railroad spurs, exterior utility and lighting systems, potable water systems, sanitary sewerage treatment facilities, and transmission lines);

8. Procurement or fabrication of components or portions of the proposed facility occurring at other than the final, in-place location at the facility; or

9. Taking any other action that has no reasonable nexus to radiological health and safety.

(q) "Containment system" means the assembly of components of the packaging intended to retain the radioactive material during transport.

(r) "Contamination", for purposes of packaging and transportation of radioactive material, means the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm² (1x10^-5 µCi/cm²) for beta and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm² (1x10^-6 µCi/cm²) for all other alpha emitters.

1. "Fixed contamination" means contamination that cannot be removed from a surface during normal conditions of transport.

2. "Non-fixed contamination" means contamination that can be removed from a surface during normal conditions of transport.

(s) "Conveyance" means:

1. For transport by public highway or rail: any transport vehicle or large freight container;

2. For transport by water: any vessel, or any hold, compartment, or defined deck area of a vessel including any transport vehicle on board the vessel; and

3. For transport by aircraft: any aircraft.

(t) "Critical group" means the group of individuals reasonably expected to receive the greatest exposure to residual radioactivity for any applicable set of circumstances.

(u) "Criticality safety index" (CSI) means the dimensionless number (rounded up to the next tenth) assigned to and placed on the label of a fissile material package, to designate the degree of control of accumulation of packages, overpacks, or freight containers containing fissile material during transportation. Determination of the criticality safety index is described in paragraphs (10) and (11) of Rule 0400-20-10-.30 and 10 CFR 71.59. The criticality safety index for an overpack, freight container, consignment, or conveyance containing fissile material packages is the arithmetic sum of the criticality safety indices of all the fissile material packages contained within the overpack, freight container, consignment, or conveyance.

(v) "Curie". Defined in Rule 0400-20-05-.34.

(w) "Cyclotron" means a particle accelerator in which the charged particles travel in an outward spiral or circular path. A cyclotron accelerates charged particles and is commonly used for production of short half-life radionuclides for medical or veterinary use.

(x) "Decommission" means:

1. To remove a facility or site safely from service and reduce residual radioactivity to a level that permits:

(i) Release of the property for unrestricted use and termination of the license; or

(ii) Release of the property under restricted conditions and the termination of the license.

2. For purposes of Rule 0400-20-05-.12, decommission also means reclaiming the property on which the facility or site is located to a condition or state such that the property no longer presents a public health or safety hazard or threat to the environment.

(y) "Deuterium" means, for the purposes of subparagraph (6)(c) and paragraph (10) of Rule 0400-20-10-.30, deuterium and any deuterium compounds, including heavy water, in which the ratio of deuterium atoms to hydrogen atoms exceeds 1:5000.

(z) "Discrete source" means 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.

(aa) "Disposal facility" means a land disposal site that is used for the isolation of radioactive waste from the biosphere.

(bb) "Distinguishable from background" means that 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.

(cc) Reserved.

(dd) "Dose". Defined in Rule 0400-20-05-.32.

(ee) "DOT" and "U.S. DOT" means the United States Department of Transportation. U.S. DOT regulations are found in Code of Federal Regulations Title 49 Transportation.

(ff) "Emergency procedures" means the written pre-planned steps to be taken in the event of actual or suspected exposure of individuals to excessive radiation. This procedure should include the names and telephone numbers of individuals to be contacted as well as directives for processing the film badge or other personnel-monitoring device.

(gg) "Exclusive use" (or "sole use" or "full load") means the sole use by a single consignor of a conveyance for which all initial, intermediate, and final loading and unloading are carried out in accordance with the direction of the consignor or consignee. The consignor and the carrier shall ensure that personnel having radiological training and resources appropriate for safe handling of the consignment perform any loading or unloading. The consignor shall issue specific written instructions for maintenance of exclusive use shipment controls and include them with the shipping paper information provided to the carrier by the consignor.

(hh) "Exposure"2 means a measure of the ionization produced in air by X or gamma radiation. It is the sum of the electrical charges on all of the ions of one sign produced in air, when all electrons liberated by photons in a volume element of air are completely stopped in air, divided by the mass of the air in the volume element. The special unit of exposure is the roentgen.

(ii) "Fissile material" means the radionuclides plutonium-239, plutonium-241, uranium-233, uranium-235 or any combination of these radionuclides. Fissile material means the fissile nuclides themselves, not material containing fissile nuclides. Unirradiated natural uranium and depleted uranium, and natural uranium or depleted uranium, that has been irradiated in thermal reactors only, are not included in this definition. Certain exclusions from fissile material controls are provided in subparagraph (6)(c) of Rule 0400-20-10-.30.

(jj) "Fissile material package". See "Package"

(kk) "Former AEC or NRC licensed facilities" means nuclear reactors, nuclear fuel processing plants, uranium enrichment plants, or critical mass experimental facilities where U.S. Atomic Energy Commission (AEC) or NRC licenses have been terminated.

(ll) "Generator" means a person whose activities with radioactive material are such that waste is generated that is distinctly separate and/or distinct from materials received.

(mm) "Graphite" means, for the purposes of subparagraph (6)(c) and paragraph (10) of Rule 0400-20-10-.30, graphite with a boron equivalent content less than 5 parts per million and density greater than 1.5 grams per cubic centimeter.

(nn) "Indian Tribe" means an Indian or Alaska native Tribe, band, nation, pueblo, village, or community that the Secretary of the Interior acknowledges to exist as an Indian Tribe pursuant to the Federally Recognized Indian Tribe List Act of 1994, 25 U.S.C. 1530.

(oo) "Human use" (or "medical use") means the intentional internal or external administration of radiation or radioactive materials to individuals under the supervision of an authorized user.

(pp) "Interlock" means a device for precluding access to any area of radiation hazard by automatically eliminating the hazard upon entry by personnel or parts of their body.

(qq) "Licensed material" means radioactive, by-product, source, or special nuclear material received, possessed, used, or transferred under a general or specific license issued by the Division pursuant to the rules in this chapter, or issued by the U.S. NRC or an Agreement State pursuant to equivalent regulations.

(rr) "Licensing State" means any state with regulations equivalent to the Suggested State Regulations for Control of Radiation relating to, and an effective program for, the regulatory control of NARM.

(ss) "Low specific activity (LSA) material" means radioactive material with limited specific activity which is nonfissile or is excepted under subparagraph (6)(c) of Rule 0400-2010-.30, and which satisfies the descriptions and limits set forth in parts 1, 2, and 3 of this subparagraph. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. The LSA material must be in one of three groups:

1. LSA-I

(i) Uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing only naturally occurring radionuclides that are intended to be processed for the use of these radionuclides; or

(ii) Natural uranium, depleted uranium, natural thorium, or their compounds or mixtures, provided they are unirradiated and in solid or liquid form; or

(iii) Radioactive material other than fissile material for which the A₂ value is unlimited; or

(iv) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 30 times the value for exempt material activity concentration determined in accordance with Schedule 10-6 in Rule 0400-20-10-.38.

2. LSA-II

(i) Water with tritium concentration up to 20 Ci/liter (0.8 terabecquerel/liter); or

(ii) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 1 E-4 A₂/gram for solids and gases or 1 E-5 A₂/gram for liquids.

3. LSA-III. Solids (e.g., consolidated wastes, activated materials), excluding powders, that satisfy the requirements of the U.S. NRC regulations 10 CFR 71.77, in which:

(i) The radioactive material is distributed throughout a solid or a collection of solid objects or is essentially uniformly distributed in a solid compact binding agent (such as concrete, bitumen, ceramic, etc.); and

(ii) The radioactive material is relatively insoluble, or it is intrinsically contained in a relatively insoluble material, so that even under loss of packaging, the loss of radioactive material per package by leaching, when placed in water for seven days, would not exceed 0.1 A₂; and

(iii) The estimated average specific activity of the solid, excluding any shielding material, does not exceed 2 E-3 A₂/gram.

(tt) "Low toxicity alpha emitters" means natural uranium, depleted uranium, natural thorium; uranium-235, uranium-238, thorium-232, thorium-228, or thorium-230 when contained in ores or physical or chemical concentrates or tailings; or alpha emitters with a half-life of less than 10 days.

(uu) "Major processors" means persons processing or handling radioactive materials exceeding Type X quantities 3 as unsealed sources or material.

(vv) "Maximum normal operating pressure" means the maximum gauge pressure that would develop in the containment system in a period of one year under the heat condition specified in 10 CFR 71.71(c)(1), in the absence of venting, external cooling by an ancillary system, or operational controls during transport.

(ww) "NARM" means any naturally occurring or accelerator-produced radioactive material. It does not include by product, source or special nuclear material.

(xx) "Natural radioactivity" means radioactivity of naturally occurring nuclides.

(yy) "Natural thorium" means thorium with the naturally occurring distribution of thorium isotopes (essentially 100 weight percent thorium-232).

(zz) "Normal form radioactive material" means radioactive material that has not been demonstrated to qualify as special form radioactive material.

(aaa) "Operating procedures" means detailed written instructions including, but not limited to, the normal operation of equipment and movable shielding, closing of interlock circuits, manipulation of controls, radiation monitoring procedures for personnel and areas, testing of interlocks and record keeping requirements.

(bbb) "Optimum interspersed hydrogenous moderation" means the presence of hydrogenous material between packages to such an extent that the maximum nuclear reactivity results.

(ccc) "Ore refineries" means all non-exempt processors of a radioactive material ore.

(ddd) "Package" means the packaging together with its radioactive contents as presented for transport.

1. "Fissile material package" or "Type AF package", "Type BF package", Type B(U)F package" or "Type B(M)F package" means a fissile material packaging together with its fissile material contents.

2. "Type A package" means a Type A packaging together with its radioactive contents. A Type A package is defined and must comply with the U.S. DOT regulations in 49 CFR 173.

3. "Type B package" means a Type B packaging together with its radioactive contents. On approval, a Type B package design is designated by NRC as B(U) unless the package has a maximum normal operating pressure of more than 700 kPa (100 lbs/in²) gauge or a pressure relief device that would allow the release of radioactive material to the environment under the tests specified in 10 CFR 71.73 (hypothetical accident conditions), in which case it will receive a designation B(M). B(U) refers to the need for unilateral approval of international shipments; B(M) refers to the need for multilateral approval of international shipments. There is no distinction made in how packages with these designations may be used in domestic transportation. To determine their distinction for international transportation, see U.S. DOT regulations in 49 CFR 173. A Type B package approved before September 6, 1983, was designated only as Type B. Limitations on its use are specified in 10 CFR 71.19.

(eee) "Packaging" means the assembly of components necessary to ensure compliance with the packaging requirements of this chapter. It may consist of one or more receptacles absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing mechanical shocks. The vehicle, tie-down system, and auxiliary equipment may be designated as part of the packaging.

(fff) "Particle accelerator" means any device used to impact kinetic energy to electrically charged particles including but not limited to electrons, protons, deuterons, and helium ions. For the purpose of these rules, "accelerator" includes equipment designed for and used only for the production of x-rays of 0.9 MeV or greater and equipment capable of discharging nuclear particles into a medium external to the accelerating device. For purposes of this definition, "accelerator" is an equivalent term.

(ggg) "Physician" means an individual licensed by the State to dispense drugs in the practice of medicine.

(hhh) "Qualified individual". Defined in Rule 0400-20-06-.03.

(iii) "Qualified expert" means, for purposes of subparagraph (2)(g) and (m) of Rule 0400 20-09-.21, a person:

1. Who is certified by the American Board of Radiology in Therapeutic Radiological Physics, Radiological Physics, Roentgen-Ray and Gamma-Ray Physics or X-Ray and Radium Physics; or

2. Who has the following 4 minimum training and experience:

(i) A Master's or Doctor's degree in physics biophysics radiological physics, or health physics;

(ii) One year of full-time training in therapeutic radiological physics; and

(iii) One year of full-time experience in a therapy facility including personal calibration and spot check of at least one teletherapy unit.

(jjj) "Rad" is defined in subparagraph (1)(b) of Rule 0400-20-05-.33.

(kkk) "Radiation machine" means any device capable of producing radiation except devices that produce radiation through utilization of a radioactive material.

(lll) "Radioactive material" means any material, solid, liquid or gas, which emits radiation spontaneously.

(mmm) "Radiological Safety Officer" means an individual who has the knowledge and responsibility to apply appropriate radiation protection rules and has been assigned such responsibility by the licensee or registrant.

(nnn) "Rem" is defined in subparagraph (1)(c) of Rule 0400-20-05-.33.

(ooo) "Research and development" means theoretical analysis, exploration or experimentation; or extension of investigative findings and theories of a scientific or technical nature into practical application for experimental and demonstration purposes. Research and development includes the experimental production and testing of models, devices, equipment, materials and processes. Research and development does not include the internal or external administration of radiation or radioactive material to individuals.

(ppp) "Residual radioactivity" means radioactivity in structures, materials, soils, groundwater, subsurface materials and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of Chapter 0400-20-05.

(qqq) "Roentgen" (R) means the special unit of exposure. One roentgen equals 2.58 x 10^-4 coulombs per kilogram of air.

(rrr) "Sealed source" is defined in Rule 0400-20-07-.05.

(sss) "Site area emergency" means a classification for events that are in progress, may occur, or have occurred that could lead to a significant release of radioactive material 4 Licensees or certified registrants that utilize persons who do not meet these criteria for minimum training and experience may request a variance excepting them from the requirements of using qualified experts. The request should include:

(ttt) "Source of radiation" means material that emits radiation spontaneously, or apparatus that produces, or may produce when the associated controls are operated, one or more forms of radiation.

(uuu) "Special form radioactive material" means radioactive material that satisfies the following conditions:

1. It either is a single solid piece or is contained in a sealed capsule that can be opened only by destroying the capsule;

2. The piece or capsule has at least one dimension not less than 5 millimeters (0.2 inch); and

3. It satisfies the requirements specified by the U.S. Nuclear Regulatory Commission in 10 CFR 71.75. A special form encapsulation designed in accordance with the U.S. NRC requirements of 10 CFR 71.4 in effect on June 30, 1983 (see 10 CFR 71, revised as of January 1, 1983), and constructed before July 1, 1985; a special form encapsulation designed in accordance with U.S. NRC requirements of 10 CFR 71.4 in effect on March 31, 1996, (see 10 CFR 71, revised as of January 1, 1996), and constructed before April 1, 1998; and special form material that was successfully tested before September 10, 2015, in accordance with the requirements of 10 CFR 71.75(d) in effect before September 10, 2015, may continue to be used. Any other special form encapsulation shall meet the specifications of this definition.

(vvv) "Special nuclear material in quantities not sufficient to form a critical mass" means:

1. Uranium enriched in the isotope U-235 in quantities not exceeding 350 grams of contained U-235;

2. Uranium-233 in quantities not exceeding 200 grams;

3. Plutonium in quantities not exceeding 200 grams; or

4. Any combination of them in accordance with the following formula. For each kind of special nuclear material, determine the ratio between the quantity of that special nuclear material and the quantity specified above for the same kind of special nuclear material. The sum of such ratios for all kinds of special nuclear material in combination shall not exceed 1 (i.e., unity). For example, the following quantities in combination would not exceed the limitation and are within the formula, as follows:

Click to view Image

(www) "Specific activity" means the radioactivity of a radionuclide per unit mass of that nuclide. The specific activity of a material in which the radionuclide is essentially uniformly distributed is the radioactivity per unit mass of the material.

(xxx) "Spent nuclear fuel" or "Spent fuel" means fuel that has been withdrawn from a nuclear reactor following irradiation, has undergone at least one year's decay since being used as a source of energy in a power reactor, and has not been chemically separated into its constituent elements by reprocessing. Spent fuel includes the special nuclear material, byproduct material, source material, and other radioactive materials associated with fuel assemblies.

(yyy) Reserved.

(zzz) "State" means a state of the United States, the District of Columbia, the Commonwealth of Puerto Rico, the Virgin Islands, Guam, American Samoa, and the Commonwealth of the Northern Mariana Islands.

(aaaa) "Surface contaminated object" (SCO) means a solid object that is not itself classed as radioactive material but that has radioactive material distributed on any of its surfaces. SCO must be in one of two groups with surface activity not exceeding the following limits:

1. SCO-I: A solid object on which:

(i) The removable (non-fixed) contamination on the accessible surface averaged over 300 cm² (or the area of the surface if less than 300 cm²) does not exceed 1 E-4 microcurie (4 becquerels) per square centimeter (cm²) for beta and gamma and low toxicity alpha emitters or 1 E-5 microcuries (0.4 becquerel) per cm² for all other alpha emitters;

(ii) The fixed contamination on the accessible surface averaged over 300 cm² (or the area of the surface if less than 300 cm²) does not exceed 1 microcurie (4 E+4 becquerels) per square centimeter (cm²) for beta and gamma and low toxicity alpha emitters or 0.1 microcurie (4 E+3 becquerels) per cm²for all other alpha emitters; and

(iii) The removable (nonfixed) contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm² (or the area of the surface if less than 300 cm²) does not exceed 1 microcurie (4 E+4 becquerels) per square centimeter (cm²) beta and gamma and low toxicity alpha emitters or 0.1 microcurie (4 E+3 becquerels) per cm²for all other alpha emitters.

2. SCO-II: A solid object on which the limits for SCO-I are exceeded and on which:

(i) The removable contamination on the accessible surface averaged over 300 cm²(or the area of the surface if less than 300 cm²) does not exceed 1 E-2 microcurie (400 becquerels) per square centimeter (cm²) for beta and gamma and low toxicity alpha emitters or 1 E-3 microcurie (40 becquerels) per cm²for all other alpha emitters;

(ii) The fixed contamination on the accessible surface averaged over 300 cm² (or the area of the surface if less than 300 cm²) does not exceed 20 2 microcuries (8 E+5 becquerels) per square centimeter (cm) for beta and gamma and low toxicity alpha emitters or 2 microcuries (8 E+4 becquerels) per cm²for all other alpha emitters; and

(iii) The removable (nonfixed) contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm² (or the area of the surface if less than 300 cm²) does not exceed 20 microcuries (8 E+5 becquerels) per square centimeter (cm²) for beta and gamma and low toxicity alpha emitters or 2 microcuries (8 E+4 becquerels) per cm² for all other alpha emitters.

(bbbb) "Therapeutic-type protective tube housing" means:

1. For x-ray therapy apparatus not capable of operating at 500 kVp or above, the following definition applies. An x-ray tube housing so constructed that the leakage radiation at a distance of one meter from the target does not exceed 1 roentgen in an hour when the tube is operated at its maximum rated continuous current for the maximum rated tube potential.

2. For x-ray therapy apparatus capable of operating at 500 kVp or above, the following definition applies. An x-ray tube housing so constructed that the leakage radiation at a distance of one meter from the target does not exceed 0.1 percent of the useful beam exposure rate at 1-meter from the target, for any of its operating conditions.

3. In either case, small areas of reduced protection are acceptable providing the average radiation exposure over any area of 100 square centimeters at one meter distance from the target does not exceed the values given above. However, no linear dimension of the area used to obtain the average shall exceed 20 centimeters.

4. See part (1)(a)15. of Rule 0400-20-06-.05 for leakage requirements for contact therapy apparatus.

(cccc) "These regulations" or "these rules" or "State Regulations for Protection Against Radiation" means Division 0400-20.

(dddd) "Transport index" (TI) means the dimensionless number (rounded up to the next tenth) placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. The transport index is the number determined by multiplying the maximum radiation level in millirem per hour at one meter (3.3 feet) from the external surface of the package by 100 (equivalent to multiplying the maximum radiation level in millisievert (mSv) per hour at one meter (3.3 feet) by 100). The transport index is determined as follows:

1. For non-fissile material packages, the number determined by multiplying the maximum radiation level in millisievert (mSv) per hour at one meter (3.3 ft) from the external surface of the package by 100 (equivalent to the maximum radiation level in millirem per hour at 1-meter (3.3 ft)); or

2. For fissile material packages, the number determined by multiplying the maximum radiation level in millisievert per hour at one meter (3.3 ft) from the external surface of the package by 100 (equivalent to the maximum radiation level in millirem per hour at 1-meter (3.3 ft)), or, for criticality control purposes, the number obtained as described in 10 CFR 71.59, whichever is larger.

(eeee) "Tribal official" means the highest-ranking individual that represents Tribal leadership, such as the chief, president, or Tribal council leadership.

(ffff) "Type A quantity" means a quantity of radioactive material, the aggregate radioactivity of which does not exceed A₁ for special form radioactive material or A₂ for normal form radioactive material, where A₁ and A₂ are given in Table A-1, Schedule 10-6, Rule 0400-20-10-.37, or may be determined by procedures described in Schedule 10-6, Rule 0400-20-10-.38.

(gggg) "Type B quantity" means a quantity of radioactive material greater than a Type A quantity.

(hhhh) "Unirradiated uranium" means uranium containing not more than 2 E+3 Bq of plutonium per gram of uranium-235, not more than 9 E+6 Bq of fission products per gram of uranium-235, and not more than 5 E-3 g of uranium-236 per gram of uranium-235.

(iiii) "Units of radioactivity". Defined in Rule 0400-20-05-.34.

(jjjj) "Unrefined and unprocessed ore" means ore in its natural form prior to any processing, such as grinding, roasting, beneficiating or refining. Processing does not include sieving or encapsulation of ore or preparation of samples for laboratory analysis.

(kkkk) Uranium - natural, depleted, enriched.

1. "Natural uranium" means uranium (which may be chemically separated) with the naturally occurring distribution of uranium isotopes (about 0.711 weight percent uranium-235, and the remainder by weight essentially uranium-238).

2. "Depleted uranium" means uranium containing less uranium-235 than the naturally occurring distribution of uranium isotopes.

3. "Enriched uranium" means uranium containing more uranium-235 than the naturally occurring distribution of uranium isotopes.

(llll) "Useful beam" (or "primary beam") means that part of the radiation that passes through a window, aperture, cone or other collimating device.

(mmmm) "Waste" means those low-level radioactive wastes containing source, special nuclear, or byproduct material that are acceptable for disposal at a land disposal facility. For the purposes of this definition, low-level waste is radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel or byproduct material as defined in Rule 0400-20-05-.32.

(nnnn) "Waste handler" means a person who holds radioactive wastes for disposal and/or who actually disposes of radioactive wastes for other persons.

(oooo) "Waste processor" means a waste handler who performs a physical and/or chemical activity on a material containing or contaminated with radioactive material.

(pppp) "Worker" means an individual engaging in work under a license or registration issued by the Division and controlled by a licensee or registrant, but does not include the licensee or registrant.

Notes

Tenn. Comp. R. & Regs. 0400-20-04-.04

Original rule filed February 22, 2012; effective May 22, 2012. Repeal and new rule filed March 3, 2015; effective June 1, 2015. Amendment filed June 14, 2017; effective September 12, 2017. Amendments filed September 1, 2021; effective 11/30/2021.

Authority: T.C.A. §§ 4-5-201, et seq.; 68-202-101, et seq.; and 68-202-201, et seq.

It is reasonable to assume that individuals will not occupy the area within 8 centimeters of the barrier continuously.

When not underlined the term "exposure" has a more general meaning in these rules.

Type X quantities are defined in Tables RHS 2-1, RHS 2-2 and RHS 2-3 as contained in Chapter 0400-20-05. For purposes of Rule 0400-20-04-.04, where there is involved a combination of radioactive materials licensed, the method of deriving a Type X quantity is as specified in Rule 0400-20-05-.162(1)(b).

Licensees or certified registrants that utilize persons who do not meet these criteria for minimum training and experience may request a variance excepting them from the requirements of using qualified experts. The request should include:

1. The name of the proposed individual,

2. A description of his or her training and experience including information similar to that specified in Rule 0400-20-04-.04,

3. Reports of at least one calibration and spot-check program based on measurements personally made by the proposed individual within the last 10 years, and

4. Written endorsement of the technical qualifications of the proposed individual from personal knowledge by a physicist certified by the American Board of Radiology in one of the specialties listed in Rule 0400-20-04-.04. The variance request should be addressed to the Division of Radiological Health at the address given in Rule 0400-20-04-.07.