Tenn. Comp. R. & Regs. 0400-20-05-.161
RHS 8-30
ANNUAL LIMITS ON INTAKE (ALI) AND DERIVED AIR CONCENTRATIONS (DAC) OF RADIONUCLIDES FOR OCCUPATIONAL EXPOSURE; EFFLUENT CONCENTRATIONS; CONCENTRATIONS FOR RELEASE TO SANITARY SEWERAGE
Introduction
For each radionuclide, Table I indicates the chemical form which is to be used for selecting the appropriate ALI or DAC value. The ALIs and DACs for inhalation are given for an aerosol with an activity median aerodynamic diameter (AMAD) of 1 µm, micron, and for three classes (D,W,Y) of radioactive material, which refer to their retention (approximately days, weeks, or years) in the pulmonary region of the lung. This classification applies to a range of clearance half-times for D if less than 10 days, for W from 10 to 100 days, and for Y greater than 100 days. The class (D, W, or Y) given in the column headed "Class" applies only to the inhalation ALIs and DACs given in Table I, columns 2 and 3. Table II provides concentration limits for airborne and liquid effluents released to the general environment. Table III provides concentration limits for discharges to sanitary sewerage systems.
Note:
The values in Tables I, II, and III are presented in the computer "E" notation. In this notation a value of 6E-02 represents a value of 6 x 10-2 or 0.06, 6E+2 represents 6 x 102 or 600, and 6E+0 represents 6 x 100 or 6.
Table I "Occupational Values"
Note that the columns in Table I of this schedule captioned, "Oral Ingestion ALI," "Inhalation," "ALI," and "DAC," are applicable to occupational exposure to radioactive material.
The ALIs in this schedule are the annual intakes of a given radionuclide by the reference man, which would result in either a committed effective dose equivalent (CEDE) of 0.05 Sv (5 rem), stochastic ALI, or a committed dose equivalent of 0.5 Sv (50 rem) to an organ or tissue, non-stochastic ALI. The stochastic ALIs were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of 0.05 Sv (5 rem). The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor, wT. This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue, T, to the total risk of stochastic effects when the whole body is irradiated uniformly. The values of wT are listed under the definition of weighting factor in Rule 0400-20-05-.32. The non-stochastic ALIs were derived to avoid non-stochastic effects, such as prompt damage to tissue or reduction in organ function.
A value of wT=0.06 is applicable to each of the five organs or tissues in the "remainder" category receiving the highest dose equivalents, and the dose equivalents of all other remaining tissues may be disregarded. The following portions of the GI tract-stomach, small intestine, upper large intestine, and lower large intestine-are to be treated as four separate organs.
Note that the dose equivalents for an extremity, skin, and lens of the eye are not considered in computing the CEDE but are subject to limits that must be met separately.
When an ALI is defined by the stochastic dose limit, this value alone is given. When an ALI is determined by the non-stochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the ALI for the stochastic limit is shown in parentheses. Abbreviated organ or tissue designations are used:
| 1. | LLI wall=lower large intestine wall; |
| 2. | St wall=stomach wall; |
| 3. | Blad wall=bladder wall; and |
| 4. | Bone surf=bone surface. |
The use of the ALIs listed first, the more limiting of the stochastic and non-stochastic ALIs, will ensure that non-stochastic effects are avoided and that the risk of stochastic effects is limited to an acceptably low value. If, in a particular situation involving a radionuclide for which the non-stochastic ALI is limiting, the use of that non-stochastic ALI is considered unduly conservative, the licensee or registrant may use the stochastic ALI to determine the committed effective dose equivalent. However, the licensee or registrant shall also ensure that the 0.5 Sv (50 rem) dose equivalent limit for any organ or tissue is not exceeded by the sum of the external deep dose equivalent plus the internal committed dose equivalent to that organ, not the effective dose. For the case where there is no external dose contribution, this would be demonstrated if the sum of the fractions of the nonstochastic ALIs (ALIns) that contribute to the committed dose equivalent to the organ receiving the highest dose does not exceed unity, that is, £ (intake [in µCi] of each radionuclide/ALIns) <=1.0. If there is an external deep dose equivalent contribution of Hd, then this sum must be less than 1 - (Hd/50), instead of <=1.0.
Note that the dose equivalents for an extremity, skin, and lens of the eye are not considered in computing the committed effective dose equivalent but are subject to limits that must be met separately.
The derived air concentration (DAC) values are derived limits intended to control chronic occupational
exposures. The relationship between the DAC and the ALI is given by:
where 2 x 104 ml is the volume of air breathed per minute at work by the reference man under working conditions of light work.
The DAC values relate to one of two modes of exposure: either external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials. DACs based upon submersion are for immersion in a semi-infinite cloud of uniform concentration and apply to each radionuclide separately.
The ALI and DAC values include contributions to exposure by the single radionuclide named and any ingrowth of daughter radionuclides produced in the body by decay of the parent. However, intakes that include both the parent and daughter radionuclides should be treated by the general method appropriate for mixtures.
The values of ALI and DAC do not apply directly when the individual both ingests and inhales a radionuclide, when the individual is exposed to a mixture of radionuclides by either inhalation or ingestion or both, or when the individual is exposed to both internal and external irradiation. See Rule 0400-20-05-.51. When an individual is exposed to radioactive materials, which fall under several of the translocation classifications of the same radionuclide (such as Class D, Class W, or Class Y), the exposure may be evaluated as if it were a mixture of different radionuclides.
It should be noted that the classification of a compound as Class D, W, or Y is based on the chemical form of the compound and does not take into account the radiological half-life of different radioisotopes. For this reason, values are given for Class D, W, and Y compounds, even for very short-lived radionuclides.
Table II "Effluent Concentrations"
The columns in Table II of this schedule captioned "Air" and "Water" are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of Rule 0400-20-05-.61. The concentration values given in Columns 1 and 2 of Table II are equivalent to the radionuclide concentrations, which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.5 mSv (0.05 rem).
Consideration of non-stochastic limits has not been included in deriving the air and water effluent concentration limits because non-stochastic effects are presumed not to occur at or below the dose levels established for individual members of the public. For radionuclides, where the non-stochastic limit was governing in deriving the occupational DAC, the stochastic ALI was used in deriving the corresponding airborne effluent limit in Table II. For this reason, the DAC and airborne effluent limits are not always proportional, as was the case in the previous Schedule RHS 8-1.
The air concentration values listed in Table II, Column 1 were derived by one of two methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation ALI was divided by 2.4 x 109, relating the inhalation ALI to the DAC, as explained above, and then divided by a factor of 300. The factor of 300 includes the following components: a factor of 50 to relate the 0.05 Sv (5 rem) annual occupational dose limit to the 1mSv (0.1 rem) limit for members of the public; a factor of 3 to adjust for the difference in exposure time and the inhalation rate for a worker and that for members of the public; and a factor of 2 to adjust the occupational values, derived for adults, so that they are applicable to other age groups.
For those radionuclides for which submersion, that is external dose, is limiting, the occupational DAC in Table I, Column 3 was divided by 219. The factor of 219 is composed of a factor of 50, as described above, and a factor of 4.38 relating occupational exposure for 2,000 hours per year to full-time exposure (8,760 hours per year). Note that an additional factor of 2 for age considerations is not warranted in the submersion case.
The water concentrations were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 107. The factor of 7.3 x 107 (ml) includes the following components: the factors of 50 and 2 described above and a factor of 7.3 x 105 (ml), which is the annual water intake of the reference man.
Note 2 of this schedule provides groupings of radionuclides, which are applicable to unknown mixtures of radionuclides. These groupings, including occupational inhalation ALIs and DACs, air and water effluent concentrations and releases to sewer, require demonstrating that the most limiting radionuclides in successive classes are absent. The limit for the unknown mixture is defined when the presence of one of the listed radionuclides cannot be definitely excluded as being present, either from knowledge of the radionuclide composition of the source or from actual measurements.
Table III "Releases to Sewers"
The monthly average concentrations for release to sanitary sewerage are applicable to the provisions in Rule 0400-20-05-.122. The concentration values were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 106 (ml). The factor of 7.3 x 106 (ml) is composed of a factor of 7.3 x 105 (ml), the annual water intake by a reference man, and a factor of 10, such that the concentrations, if the sewage released by the licensee were the only source of water ingested by a reference man during a year, would result in a committed effective dose equivalent of 5 mSv (0.5 rem).
LIST OF ELEMENTS
| . | . | Atomic |
| Name | Symbol | Number |
| Actinium | Ac | 89 |
| Aluminum | Al | 13 |
| Americium | Am | 95 |
| Antimony | Sb | 51 |
| Argon | Ar | 18 |
| Arsenic | As | 33 |
| Astatine | At | 85 |
| Barium | Ba | 56 |
| Berkelium | Bk | 97 |
| Beryllium | Be | 4 |
| Bismuth | Bi | 83 |
| Bromine | Br | 35 |
| Cadmium | Cd | 48 |
| Calcium | Ca | 20 |
| Californium | Cf | 98 |
| Carbon | C | 6 |
| Cerium | Ce | 58 |
| Cesium | Cs | 55 |
| Chlorine | Cl | 17 |
| Chromium | Cr | 24 |
| Cobalt | Co | 27 |
| Copper | Cu | 29 |
| Curium | Cm | 96 |
| Dysprosium | Dy | 66 |
| Einsteinium | Es | 99 |
| Erbium | Er | 68 |
| Europium | Eu | 63 |
| Fermium | Fm | 100 |
| Fluorine | F | 9 |
| Francium | Fr | 87 |
| Gadolinium | Gd | 64 |
| Gallium | Ga | 31 |
| Germanium | Ge | 32 |
| Gold | Au | 79 |
| Hafnium | Hf | 72 |
| Holmium | Ho | 67 |
| Hydrogen | H | 1 |
| Indium | In | 49 |
| Iodine | I | 53 |
| Iridium | Ir | 77 |
| Iron | Fe | 26 |
| Mercury | Hg | 80 |
| Krypton | Kr | 36 |
| Lanthanum | La | 57 |
| Lead | Pb | 82 |
| Lutetium | Lu | 71 |
| Magnesium | Mg | 12 |
| Manganese | Mn | 25 |
| Mendelevium | Md | 101 |
| Molybdenum | Mo | 42 |
| Neodymium | Nd | 60 |
| Neptunium | Np | 93 |
| Nickel | Ni | 28 |
| Niobium | Nb | 41 |
| Nitrogen | N | 7 |
| Osmium | Os | 76 |
| Oxygen | O | 8 |
| Palladium | Pd | 46 |
| Phosphorus | P | 15 |
| Platinum | Pt | 78 |
| Plutonium | Pu | 94 |
| Polonium | Po | 84 |
| Potassium | K | 19 |
| Praseodymium | Pr | 59 |
| Promethium | Pm | 61 |
| Protactinium | Pa | 91 |
| Radium | Ra | 88 |
| Radon | Rn | 86 |
| Rhenium | Re | 75 |
| Rhodium | Rh | 45 |
| Rubidium | Rb | 37 |
| Ruthenium | Ru | 44 |
| Samarium | Sm | 62 |
| Scandium | Sc | 21 |
| Selenium | Se | 34 |
| Silicon | Si | 14 |
| Silver | Ag | 47 |
| Sodium | Na | 11 |
| Strontium | Sr | 38 |
| Sulfur | S | 16 |
| Tantalum | Ta | 73 |
| Technetium | Tc | 43 |
| Tellurium | Te | 52 |
| Terbium | Tb | 65 |
| Thallium | Tl | 81 |
| Thorium | Th | 90 |
| Thulium | Tm | 69 |
| Tin | Sn | 50 |
| Titanium | Ti | 22 |
| Tungsten | W | 74 |
| Uranium | U | 92 |
| Vanadium | V | 23 |
| Xenon | Xe | 54 |
| Ytterbium | Yb | 70 |
| Yttrium | Y | 39 |
| Zinc | Zn | 30 |
| Zirconium | Zr | 40 |
ENDNOTES:
1"Submersion" means that values given are for submersion in a hemispherical semi-infinite cloud of airborne material.
2 These radionuclides have radiological half-lives of less than 2 hours. The total effective dose equivalent received during operations with these radionuclides might include a significant contribution from external exposure. The DAC values for all radionuclides, other than those designated Class "Submersion," are based upon the committed effective dose equivalent due to the intake of the radionuclide into the body and do not include potentially significant contributions to dose equivalent from external exposures. The licensee may substitute 1E-7 µCi/ml for the listed DAC to account for the submersion dose prospectively, but should use individual monitoring devices or other radiation measuring instruments that measure external exposure to demonstrate compliance with the limits. (See Rule 0400-20-05-.52.)
3 For soluble mixtures of U-238, U-234, and U-235 in air, chemical toxicity may be the limiting factor (see paragraph (5) of Rule 0400-20-05-.50) . If the percent by weight (enrichment) of U-235 is not greater than 5, the concentration value for a 40-hour workweek is 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the product of the average concentration and time of exposure during a 40-hour workweek shall not exceed 8E-3 (SA) µCi-hr/ml, where SA is the specific activity of the uranium inhaled. The specific activity for natural uranium is 6.77E-7 curies per gram U. The specific activity for other mixtures of U-238, U-235, and U-234, if not known, shall be:
SA=3.6E-7 curies/gram U U-depleted
SA=[0.4 + 0.38 (enrichment) + 0.0034 (enrichment)2] E-6, enrichment=> 0. 72 where enrichment is the percentage by weight of U-235, expressed as percent.
NOTE:
1. If the identity of each radionuclide in a mixture is known but the concentration of one or more of the radionuclides in the mixture is not known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture.
2. If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in this schedule are not present in the mixture, the inhalation ALI, DAC, and effluent and sewage concentrations for the mixture are the lowest values specified in this schedule for any radionuclide that is not known to be absent from the mixture; or
3. If a mixture of radionuclides consists of uranium and its daughters in ore dust (10 µm AMAD particle distribution assumed) prior to chemical separation of the uranium from the ore, the following values may be used for the DAC of the mixture: 6E-11 µCi of gross alpha activity from uranium-238, uranium-234, thorium-230, and radium-226 per milliliter of air; 3E-11 µCi of natural uranium per milliliter of air; or 45 micrograms of natural uranium per cubic meter of air.
4. If the identity and concentration of each radionuclide in a mixture are known, the limiting values should be derived as follows: determine, for each radionuclide in the mixture, the ratio between the concentration present in the mixture and the concentration otherwise established in Schedule RHS 8-30 for the specific radionuclide when not in a mixture. The sum of such ratios for all of the radionuclides in the mixture may not exceed "1" (i.e., "unity").
Example: If radionuclides "A," "B," and "C" are present in concentrations Ca, Cb, and CC, and if the applicable DACs are DACa, DACb, and DACC, respectively, then the concentrations shall be limited so that the following relationship exists:
SCHEDULE RHS 8-31 QUANTITIES a OF LICENSED MATERIAL REQUIRING LABELING
| Radionuclide | Quantity(µCi)*a |
| Hydrogen-3 | 1,000 |
| Beryllium-7 | 1,000 |
| Beryllium-10 | 1 |
| Carbon-11 | 1,000 |
| Carbon-14 | 1,000 |
| Fluorine-18 | 1,000 |
| Sodium-22 | 10 |
| Sodium-24 | 100 |
| Magnesium-28 | 100 |
| Aluminum-26 | 10 |
| Silicon-31 | 1,000 |
| Silicon-32 | 1 |
| Phosphorus-32 | 10 |
| Phosphorus-33 | 100 |
| Sulfur-35 | 100 |
| Chlorine-36 | 10 |
| Chlorine-38 | 1,000 |
| Chlorine-39 | 1,000 |
| Argon-39 | 1,000 |
| Argon-41 | 1,000 |
| Potassium-40 | 100 |
| Potassium-42 | 1,000 |
| Potassium-43 | 1,000 |
| Potassium-44 | 1,000 |
| Potassium-45 | 1,000 |
| Calcium-41 | 100 |
| Calcium-45 | 100 |
| Calcium-47 | 100 |
| Scandium-43 | 1,000 |
| Scandium-44m | 100 |
| Scandium-44 | 100 |
| Scandium-46 | 10 |
| Scandium-47 | 100 |
| Scandium-48 | 100 |
| Scandium-49 | 1,000 |
| Titanium-44 | 1 |
| Titanium-45 | 1,000 |
| Vanadium-47 | 1,000 |
| Vanadium-48 | 100 |
| Vanadium-49 | 1,000 |
| Chromium-48 | 1,000 |
| Chromium-49 | 1,000 |
| Chromium-51 | 1,000 |
| Manganese-51 | 1,000 |
| Manganese-52m | 1,000 |
| Manganese-52 | 100 |
| Manganese-53 | 1,000 |
| Manganese-54 | 100 |
| Manganese-56 | 1,000 |
| Radionuclide | Quantity(µCi)*a |
| Iron-52 | 100 |
| Iron-55 | 100 |
| Iron-59 | 10 |
| Iron-60 | 1 |
| Cobalt-55 | 100 |
| Cobalt-56 | 10 |
| Cobalt-57 | 100 |
| Cobalt-58m | 1,000 |
| Cobalt-58 | 100 |
| Cobalt-60m | 1,000 |
| Cobalt-60 | 1 |
| Cobalt-61 | 1,000 |
| Cobalt-62m | 100 |
| Nickel-56 | 100 |
| Nickel-57 | 100 |
| Nickel-59 | 100 |
| Nickel-63 | 100 |
| Nickel-65 | 1,000 |
| Nickel-66 | 10 |
| Copper-60 | 1,000 |
| Copper-61 | 1,000 |
| Copper-64 | 1,000 |
| Copper-67 | 1,000 |
| Zinc-62 | 100 |
| Zinc-63 | 1,000 |
| Zinc-65 | 10 |
| Zinc-69m | 100 |
| Zinc-69 | 1,000 |
| Zinc-71m | 1,000 |
| Zinc-72 | 100 |
| Gallium-65 | 1,000 |
| Gallium-66 | 100 |
| Gallium-67 | 1,000 |
| Gallium-68 | 1,000 |
| Gallium-70 | 1,000 |
| Gallium-72 | 100 |
| Gallium-73 | 1,000 |
| Germanium-66 | 1,000 |
| Germanium-67 | 1,000 |
| Germanium-68 | 10 |
| Germanium-69 | 1,000 |
| Germanium-71 | 1,000 |
| Germanium-75 | 1,000 |
| Germanium-77 | 1,000 |
| Germanium-78 | 1,000 |
| Arsenic-69 | 1,000 |
| Arsenic-70 | 1,000 |
| Arsenic-71 | 100 |
| Arsenic-72 | 100 |
| Arsenic-73 | 100 |
| Arsenic-74 | 100 |
*a To Convert µCi to KBq, multiply the µCi value by 37.
| Radionuclide | Quantity(µCi)*a |
| Arsenic-76 | 100 |
| Arsenic-77 | 100 |
| Arsenic-78 | 1,000 |
| Selenium-70 | 1,000 |
| Selenium-73m | 1,000 |
| Selenium-73 | 100 |
| Selenium-75 | 100 |
| Selenium-79 | 100 |
| Selenium-81m | 1,000 |
| Selenium-81 | 1,000 |
| Selenium-83 | 1,000 |
| Bromine-74m | 1,000 |
| Bromine-74 | 1,000 |
| Bromine-75 | 1,000 |
| Bromine-76 | 100 |
| Bromine-77 | 1,000 |
| Bromine-80m | 1,000 |
| Bromine-80 | 1,000 |
| Bromine-82 | 100 |
| Bromine-83 | 1,000 |
| Bromine-84 | 1,000 |
| Krypton-74 | 1,000 |
| Krypton-76 | 1,000 |
| Krypton-77 | 1,000 |
| Krypton-79 | 1,000 |
| Krypton-81 | 1,000 |
| Krypton-83m | 1,000 |
| Krypton-85m | 1,000 |
| Krypton-85 | 1,000 |
| Krypton-87 | 1,000 |
| Krypton-88 | 1,000 |
| Rubidium-79 | 1,000 |
| Rubidium-81m | 1,000 |
| Rubidium-81 | 1,000 |
| Rubidium-82m | 1,000 |
| Rubidium-83 | 100 |
| Rubidium-84 | 100 |
| Rubidium-86 | 100 |
| Rubidium-87 | 100 |
| Rubidium-88 | 1,000 |
| Rubidium-89 | 1,000 |
| Strontium-80 | 100 |
| Strontium-81 | 1,000 |
| Strontium-83 | 100 |
| Strontium-85m | 1,000 |
| Strontium-85 | 100 |
| Strontium-87m | 1,000 |
| Strontium-89 | 10 |
| Strontium-90 | 0.1 |
| Strontium-91 | 100 |
| Strontium-92 | 100 |
| Yttrium-86m | 1,000 |
| Yttrium-86 | 100 |
| Yttrium-87 | 100 |
| Yttrium-88 | 10 |
| Yttrium-90m | 1,000 |
| Radionuclide | Quantity(µCi)*a |
| Yttrium-90 | 10 |
| Yttrium-91m | 1,000 |
| Yttrium-91 | 10 |
| Yttrium-92 | 100 |
| Yttrium-93 | 100 |
| Yttrium-94 | 1,000 |
| Yttrium-95 | 1,000 |
| Zirconium-86 | 100 |
| Zirconium-88 | 10 |
| Zirconium-89 | 100 |
| Zirconium-93 | 1 |
| Zirconium-95 | 10 |
| Zirconium-97 | 100 |
| Niobium-88 | 1,000 |
| Niobium-89m (66 min) | 1,000 |
| Niobium-89 | . |
| (122 min) | 1,000 |
| Niobium-90 | 100 |
| Niobium-93m | 10 |
| Niobium-94 | 1 |
| Niobium-95m | 100 |
| Niobium-95 | 100 |
| Niobium-96 | 100 |
| Niobium-97 | 1,000 |
| Niobium-98 | 1,000 |
| Molybdenum-90 | 100 |
| Molybdenum -93m | 100 |
| Molybdenum-93 | 10 |
| Molybdenum-99 | 100 |
| Molybdenum-101 | 1,000 |
| Technetium-93m | 1,000 |
| Technetium-93 | 1,000 |
| Technetium-94m | 1,000 |
| Technetium-94 | 1,000 |
| Technetium-96m | 1,000 |
| Technetium-96 | 100 |
| Technetium-97m | 100 |
| Technetium-97 | 1,000 |
| Technetium-98 | 10 |
| Technetium-99m | 1,000 |
| Technetium-99 | 100 |
| Technetium-101 | 1,000 |
| Technetium-104 | 1,000 |
| Ruthenium-94 | 1,000 |
| Ruthenium-97 | 1,000 |
| Ruthenium-103 | 100 |
| Ruthenium-105 | 1,000 |
| Ruthenium-106 | 1 |
| Rhodium-99m | 1,000 |
| Rhodium-99 | 100 |
| Rhodium-100 | 100 |
| Rhodium-101m | 1,000 |
| Rhodium -101 | 10 |
| Rhodium-102m | 10 |
| Rhodium-102 | 10 |
| Rhodium-103m | 1,000 |
| Rhodium-105 | 100 |
| Rhodium-106m | 1,000 |
| Rhodium-107 | 1,000 |
| Palladium-100 | 100 |
| Palladium-101 | 1,000 |
| Palladium-103 | 100 |
| Palladium-107 | 10 |
| Palladium-109 | 100 |
| Silver-102 | 1,000 |
| Silver-103 | 1,000 |
| Silver-104m | 1,000 |
| Silver-104 | 1,000 |
| Silver-105 | 100 |
| Silver-106m | 100 |
| Silver-106 | 1,000 |
| Silver-108m | 1 |
| Silver-110m | 10 |
| Silver-111 | 100 |
| Silver-112 | 100 |
| Silver-115 | 1,000 |
| Cadmium-104 | 1,000 |
| Cadmium-107 | 1,000 |
| Cadmium-109 | 1 |
| Cadmium-113m | 0.1 |
| Cadmium-113 | 100 |
| Cadmium-115m | 10 |
| Cadmium-115 | 100 |
| Cadmium-117m | 1,000 |
| Cadmium-117 | 1,000 |
| Indium-109 | 1,000 |
| Indium-110m | . |
| (69.1m) | 1,000 |
| Indium-110 | . |
| (4.9h) | 1,000 |
| Indium-111 | 100 |
| Indium-112 | 1,000 |
| Indium-113m | 1,000 |
| Indium-114m | 10 |
| Indium-115m | 1,000 |
| Indium-115 | 100 |
| Indium-116m | 1,000 |
| Indium-117m | 1,000 |
| Indium-117 | 1,000 |
| Indium-119m | 1,000 |
| Tin-110 | 100 |
| Tin-111 | 1,000 |
| Tin-113 | 100 |
| Tin-117m | 100 |
| Tin-119m | 100 |
| Tin-121m | 100 |
| Tin-121 | 1,000 |
| Tin-123m | 1,000 |
| Tin-123 | 10 |
| Tin-125 | 10 |
| Tin-126 | 10 |
| Radionuclide | Quantity(µCi)*a |
| Tin-127 | 1,000 |
| Tin-128 | 1,000 |
| Antimony-115 | 1,000 |
| Antimony-116m | 1,000 |
| Antimony-116 | 1,000 |
| Antimony-117 | 1,000 |
| Antimony-118m | 1,000 |
| Antimony-119 | 1,000 |
| Antimony-120 (16m) | 1,000 |
| Antimony-120 (5.76d) | 100 |
| Antimony-122 | 100 |
| Antimony-124m | 1,000 |
| Antimony-124 | 10 |
| Antimony-125 | 100 |
| Antimony-126m | 1,000 |
| Antimony-130 | 1,000 |
| Antimony-131 | 1,000 |
| Tellurium-116 | 1,000 |
| Tellurium-121m | 10 |
| Tellurium-121 | 100 |
| Tellurium-123m | 10 |
| Tellurium-123 | 100 |
| Tellurium-125m | 10 |
| Antimony-126 | 100 |
| Antimony-127 | 100 |
| Tellurium-127m | 10 |
| Tellurium-127 | 1,000 |
| Antimony-128 (10.4 m) | 1,000 |
| Antimony-128 (9.01 h) | 100 |
| Antimony-129 | 100 |
| Tellurium-129m | 10 |
| Tellurium-129 | 1,000 |
| Tellurium-131m | 10 |
| Tellurium-131 | 100 |
| Tellurium-132 | 10 |
| Tellurium-133m | 100 |
| Tellurium-133 | 1,000 |
| Tellurium-134 | 1,000 |
| Iodine-120m | 1,000 |
| Iodine-120 | 100 |
| Iodine-121 | 1,000 |
| Iodine-123 | 100 |
| Iodine-124 | 10 |
| Iodine-125 | 1 |
| Iodine-126 | 1 |
| Iodine-128 | 1,000 |
| Iodine-129 | 1 |
| Iodine-130 | 10 |
| Iodine-131 | 1 |
| Iodine-132m | 100 |
| Iodine-132 | 100 |
| Iodine-133 | 10 |
| Iodine-134 | 1,000 |
| Iodine-135 | 100 |
| Xenon-120 | 1,000 |
| Xenon-121 | 1,000 |
| Xenon-122 | 1,000 |
| Xenon-123 | 1,000 |
| Xenon-125 | 1,000 |
| Xenon-127 | 1,000 |
| Xenon-129m | 1,000 |
| Xenon-131m | 1,000 |
| Xenon-133m | 1,000 |
| Xenon-133 | 1,000 |
| Xenon-135m | 1,000 |
| Xenon-135 | 1,000 |
| Xenon-138 | 1,000 |
| Cesium-125 | 1,000 |
| Cesium-127 | 1,000 |
| Cesium-129 | 1,000 |
| Cesium-130 | 1,000 |
| Cesium-131 | 1,000 |
| Cesium-132 | 100 |
| Cesium-134m | 1,000 |
| Cesium-134 | 10 |
| Cesium-135m | 1,000 |
| Cesium-135 | 100 |
| Cesium-136 | 10 |
| Cesium-137 | 10 |
| Cesium-138 | 1,000 |
| Barium-126 | 1,000 |
| Barium-128 | 100 |
| Barium-131m | 1,000 |
| Barium-131 | 100 |
| Barium-133m | 100 |
| Barium-133 | 100 |
| Barium-135m | 100 |
| Barium-139 | 1,000 |
| Barium-140 | 100 |
| Barium-141 | 1,000 |
| Barium-142 | 1,000 |
| Lanthanum-131 | 1,000 |
| Lanthanum-132 | 100 |
| Lanthanum-135 | 1,000 |
| Lanthanum-137 | 10 |
| Lanthanum-138 | 100 |
| Lanthanum-140 | 100 |
| Lanthanum-141 | 100 |
| Lanthanum-142 | 1,000 |
| Lanthanum-143 | 1,000 |
| Cerium-134 | 100 |
| Cerium-135 | 100 |
| Cerium-137m | 100 |
| Cerium-137 | 1,000 |
| Cerium-139 | 100 |
| Cerium-141 | 100 |
| Cerium-143 | 100 |
| Cerium-144 | 1 |
| Praseodymium-136 | 1,000 |
| Praseodymium-137 | 1,000 |
| Radionuclide | Quantity(µCi)*a |
| Praseodymium-138m | 1,000 |
| Praseodymium-139 | 1,000 |
| Praseodymium-142m | 1,000 |
| Praseodymium-142 | 100 |
| Praseodymium-143 | 100 |
| Praseodymium-144 | 1,000 |
| Praseodymium-145 | 100 |
| Praseodymium-147 | 1,000 |
| Neodymium-136 | 1,000 |
| Neodymium-138 | 100 |
| Neodymium-139m | 1,000 |
| Neodymium-139 | 1,000 |
| Neodymium-141 | 1,000 |
| Neodymium-147 | 100 |
| Neodymium-149 | 1,000 |
| Neodymium-151 | 1,000 |
| Promethium-141 | 1,000 |
| Promethium-143 | 100 |
| Promethium-144 | 10 |
| Promethium-145 | 10 |
| Promethium-146 | 1 |
| Promethium-147 | 10 |
| Promethium-148m | 10 |
| Promethium-148 | 10 |
| Promethium-149 | 100 |
| Promethium-150 | 1,000 |
| Promethium-151 | 100 |
| Samarium-141m | 1,000 |
| Samarium-141 | 1,000 |
| Samarium-142 | 1,000 |
| Samarium-145 | 100 |
| Samarium-146 | 1 |
| Samarium-147 | 100 |
| Samarium-151 | 10 |
| Samarium-153 | 100 |
| Samarium-155 | 1,000 |
| Samarium-156 | 1,000 |
| Europium-145 | 100 |
| Europium-146 | 100 |
| Europium-147 | 100 |
| Europium-148 | 10 |
| Europium-149 | 100 |
| Europium-150 (12.62h) | 100 |
| Europium-150 (34.2y) | 1 |
| Europium-152m | 100 |
| Europium-152 | 1 |
| Europium-154 | 1 |
| Europium-155 | 10 |
| Europium-156 | 100 |
| Europium- 157 | 100 |
| Europium-158 | 1,000 |
| Gadolinium-145 | 1,000 |
| Gadolinium-146 | 10 |
| Gadolinium-147 | 100 |
| Gadolinium-148 | 0.001 |
| Gadolinium-149 | 100 |
| Gadolinium-151 | 10 |
| Gadolinium-152 | 100 |
| Gadolinium-153 | 10 |
| Gadolinium-159 | 100 |
| Terbium-147 | 1,000 |
| Terbium-149 | 100 |
| Terbium- 150 | 1,000 |
| Terbium-151 | 100 |
| Terbium-153 | 1,000 |
| Terbium-154 | 100 |
| Terbium-155 | 1,000 |
| Terbium-156m (5.0 h) | 1,000 |
| Terbium-156m (24.4h) | 1,000 |
| Terbium-156 | 100 |
| Terbium-157 | 10 |
| Terbium-158 | 1 |
| Terbium-160 | 10 |
| Terbium-161 | 100 |
| Dysprosium-155 | 1,000 |
| Dysprosium-157 | 1,000 |
| Dysprosium-159 | 100 |
| Dysprosium-165 | 1,000 |
| Dysprosium-166 | 100 |
| Holmium-155 | 1,000 |
| Holmium-157 | 1,000 |
| Holmium-159 | 1,000 |
| Holmium-161 | 1,000 |
| Holmium-162m | 1,000 |
| Holmium-162 | 1,000 |
| Holmium-164m | 1,000 |
| Holmium-164 | 1,000 |
| Holmium-166m | 1 |
| Holmium-166 | 100 |
| Holmium-167 | 1,000 |
| Erbium-161 | 1,000 |
| Erbium-165 | 1,000 |
| Erbium-169 | 100 |
| Erbium-171 | 100 |
| Erbium-172 | 100 |
| Thulium-162 | 1,000 |
| Thulium-166 | 100 |
| Thulium-167 | 100 |
| Thulium-170 | 10 |
| Thulium-171 | 10 |
| Thulium-172 | 100 |
| Thulium-173 | 100 |
| Thulium-175 | 1,000 |
| Ytterbium-162 | 1,000 |
| Ytterbium-166 | 100 |
| Ytterbium-167 | 1,000 |
| Ytterbium-169 | 100 |
| Ytterbium-175 | 100 |
| Ytterbium-177 | 1,000 |
| Ytterbium-178 | 1,000 |
| Lutetium-169 | 100 |
| Lutetium-170 | 100 |
| Radionuclide | Quantity(µCi)*a |
| Lutetium-171 | 100 |
| Lutetium-172 | 100 |
| Lutetium-173 | 10 |
| Lutetium-174m | 10 |
| Lutetium-174 | 10 |
| Lutetium-176m | 1,000 |
| Lutetium-176 | 100 |
| Lutetium-177m | 10 |
| Lutetium-177 | 100 |
| Lutetium-178m | 1,000 |
| Lutetium-178 | 1,000 |
| Lutetium-179 | 1,000 |
| Hafnium-170 | 100 |
| Hafnium-172 | 1 |
| Hafnium-173 | 1,000 |
| Hafnium-175 | 100 |
| Hafnium-177m | 1,000 |
| Hafnium-178m | 0.1 |
| Hafnium-179m | 10 |
| Hafnium-180m | 1,000 |
| Hafnium-181 | 10 |
| Hafnium-182m | 1,000 |
| Hafnium-182 | 0.1 |
| Hafnium-183 | 1,000 |
| Hafnium-184 | 100 |
| Tantalum-172 | 1,000 |
| Tantalum-173 | 1,000 |
| Tantalum-174 | 1,000 |
| Tantalum-175 | 1,000 |
| Tantalum-176 | 100 |
| Tantalum-177 | 1,000 |
| Tantalum-178 | 1,000 |
| Tantalum-179 | 100 |
| Tantalum-180m | 1,000 |
| Tantalum-180 | 100 |
| Tantalum-182m | 1,000 |
| Tantalum-182 | 10 |
| Tantalum-183 | 100 |
| Tantalum-184 | 100 |
| Tantalum-185 | 1,000 |
| Tantalum-186 | 1,000 |
| Tungsten-176 | 1,000 |
| Tungsten-177 | 1,000 |
| Tungsten-178 | 1,000 |
| Tungsten-179 | 1,000 |
| Tungsten-181 | 1,000 |
| Tungsten-185 | 100 |
| Tungsten-187 | 100 |
| Tungsten-188 | 10 |
| Rhenium-177 | 1,000 |
| Rhenium-178 | 1,000 |
| Rhenium-181 | 1,000 |
| Rhenium-182 (12.7h) | 1,000 |
| Rhenium-182 (64.0 h) | 100 |
| Rhenium-184m | 10 |
| Rhenium-184 | 100 |
| Rhenium-186m | 10 |
| Rhenium-186 | 100 |
| Rhenium-187 | 1,000 |
| Rhenium-188m | 1,000 |
| Rhenium-188 | 100 |
| Rhenium-189 | 100 |
| Osmium-180 | 1,000 |
| Osmium-181 | 1,000 |
| Osmium-182 | 100 |
| Osmium-185 | 100 |
| Osmium-189m | 1,000 |
| Osmium-191m | 1,000 |
| Osmium-191 | 100 |
| Osmium-193 | 100 |
| Osmium-194 | 1 |
| Iridium-182 | 1,000 |
| Iridium-184 | 1,000 |
| Iridium-185 | 1,000 |
| Iridium-186 | 100 |
| Iridium-187 | 1,000 |
| Iridium-188 | 100 |
| Iridium-189 | 100 |
| Iridium-190m | 1,000 |
| Iridium-190 | 100 |
| Iridium-192m (1.4m) | 10 |
| Iridium-192 (73.8d) | 1 |
| Iridium-194m | 10 |
| Iridium-194 | 100 |
| Iridium-195m | 1,000 |
| Iridium-195 | 1,000 |
| Platinum-186 | 1,000 |
| Platinum-188 | 100 |
| Platinum -189 | 1,000 |
| Platinum-191 | 100 |
| Platinum-193m | 100 |
| Platinum-193 | 1,000 |
| Platinum-195m | 100 |
| Platinum-197m | 1,000 |
| Platinum-197 | 100 |
| Platinum-199 | 1,000 |
| Platinum-200 | 100 |
| Gold-193 | 1,000 |
| Gold-194 | 100 |
| Gold-195 | 10 |
| Gold-198m | 100 |
| Gold-198 | 100 |
| Gold-199 | 100 |
| Gold-200m | 100 |
| Gold-200 | 1,000 |
| Gold-201 | 1,000 |
| Mercury-193m | 100 |
| Mercury-193 | 1,000 |
| Mercury-194 | 1 |
| Mercury-195m | 100 |
| Mercury-195 | 1,000 |
| Mercury-197m | 100 |
| Radionuclide | Quantity(µCi)*a |
| Mercury-197 | 1,000 |
| Mercury-199m | 1,000 |
| Mercury-203 | 100 |
| Thallium-194m | 1,000 |
| Thallium-194 | 1,000 |
| Thallium-195 | 1,000 |
| Thallium-197 | 1,000 |
| Thallium-198m | 1,000 |
| Thallium-198 | 1,000 |
| Thallium-199 | 1,000 |
| Thallium-200 | 1,000 |
| Thallium-201 | 1,000 |
| Thallium-202 | 100 |
| Thallium-204 | 100 |
| Lead-195m | 1,000 |
| Lead-198 | 1,000 |
| Lead-199 | 1,000 |
| Lead-200 | 100 |
| Lead-201 | 1,000 |
| Lead-202m | 1,000 |
| Lead-202 | 10 |
| Lead-203 | 1,000 |
| Lead-205 | 100 |
| Lead-209 | 1,000 |
| Lead-210 | 0.01 |
| Lead-211 | 100 |
| Lead-212 | 1 |
| Lead-214 | 100 |
| Bismuth-200 | 1,000 |
| Bismuth-201 | 1,000 |
| Bismuth-202 | 1,000 |
| Bismuth-203 | 100 |
| Bismuth-205 | 100 |
| Bismuth-206 | 100 |
| Bismuth-207 | 10 |
| Bismuth-210m | 0.1 |
| Bismuth-210 | 1 |
| Bismuth-212 | 10 |
| Bismuth-213 | 10 |
| Bismuth-214 | 100 |
| Polonium-203 | 1,000 |
| Polonium-205 | 1,000 |
| Polonium-207 | 1,000 |
| Polonium-210 | 0.1 |
| Astatine-207 | 100 |
| Astatine-211 | 10 |
| Radon-220 | 1 |
| Radon-222 | 1 |
| Francium-222 | 100 |
| Francium-223 | 100 |
| Radium-223 | 0.1 |
| Radium-224 | 0.1 |
| Radium-225 | 0.1 |
| Radium-226 | 0.1 |
| Radium-227 | 1,000 |
| Radium-228 | 0.1 |
| Actinium-224 | 1 |
| Actinium-225 | 0.01 |
| Actinium-226 | 0.1 |
| Actinium-227 | 0.001 |
| Actinium-228 | 1 |
| Thorium-226 | 10 |
| Thorium-227 | 0.01 |
| Thorium-228 | 0.001 |
| Thorium-229 | 0.001 |
| Thorium-230 | 0.001 |
| Thorium-231 | 100 |
| Thorium-232 | 100 |
| Thorium-234 | 10 |
| Thorium-natural | 100 |
| Protactinium-227 | 10 |
| Protactinium-228 | 1 |
| Protactinium-230 | 0.1 |
| Protactinium-231 | 0.001 |
| Protactinium-232 | 1 |
| Protactinium-233 | 100 |
| Protactinium-234 | 100 |
| Uranium-230 | 0.01 |
| Uranium-231 | 100 |
| Uranium-232 | 0.001 |
| Uranium-233 | 0.001 |
| Uranium-234 | 0.001 |
| Uranium-235 | 0.001 |
| Uranium-236 | 0.001 |
| Uranium-237 | 100 |
| Uranium-238 | 100 |
| Uranium-239 | 1,000 |
| Uranium-240 | 100 |
| Uranium-natural | 100 |
| Neptunium-232 | 100 |
| Neptunium-233 | 1,000 |
| Neptunium-234 | 100 |
| Neptunium-235 | 100 |
| Neptunium-236 (1.15E+5) | 0.001 |
| Neptunium-236 (22.5h) | 1 |
| Neptunium-237 | 0.001 |
| Neptunium-238 | 10 |
| Neptunium-239 | 100 |
| Neptunium-240 | 1,000 |
| Plutonium-234 | 10 |
| Plutonium-235 | 1,000 |
| Plutonium-236 | 0.001 |
| Plutonium-237 | 100 |
| Plutonium-238 | 0.001 |
| Plutonium-239 | 0.001 |
| Plutonium-240 | 0.001 |
| Plutonium-241 | 0.01 |
| Plutonium-242 | 0.001 |
| Plutonium-243 | 1,000 |
| Any alpha-emitting radionuclide not listed above or mixtures of alpha emitters of unknown composition | 0.001 |
| Radionuclide | Quantity(µCi)*a |
| Plutonium-244 | 0.001 |
| Plutonium-245 | 100 |
| Americium-237 | 1,000 |
| Americium-238 | 100 |
| Americium-239 | 1,000 |
| Americium-240 | 100 |
| Americium-241 | 0.001 |
| Americium-242m | 0.001 |
| Americium-242 | 10 |
| Americium-243 | 0.001 |
| Americium-244m | 100 |
| Americium-244 | 10 |
| Americium-245 | 1,000 |
| Americium-246m | 1,000 |
| Americium-246 | 1,000 |
| Curium-238 | 100 |
| Curium-240 | 0.1 |
| Curium-241 | 1 |
| Curium-242 | 0.01 |
| Curium-243 | 0.001 |
| Curium-244 | 0.001 |
| Curium-245 | 0.001 |
| Curium-246 | 0.001 |
| Curium-247 | 0.001 |
| Curium-248 | 0.001 |
| Curium-249 | 1,000 |
| Berkelium-245 | 100 |
| Berkelium-246 | 100 |
| Berkelium-247 | 0.001 |
| Berkelium-249 | 0.1 |
| Berkelium-250 | 10 |
| Californium-244 | 100 |
| Californium-246 | 1 |
| Californium-248 | 0.01 |
| Californium-249 | 0.001 |
| Californium-250 | 0.001 |
| Californium-251 | 0.001 |
| Californium-252 | 0.001 |
| Californium-253 | 0.1 |
| Californium-254 | 0.001 |
| Einsteinium-250 | 100 |
| Einsteinium-250 | 100 |
| Einsteinium-251 | 100 |
| Einsteinium-253 | 0.1 |
| Einsteinium-254m | 1 |
| Einsteinium-254 | 0.01 |
| Fermium-252 | 1 |
| Fermium-253 | 1 |
| Fermium-254 | 10 |
| Fermium-255 | 1 |
| Fermium-257 | 0.01 |
| Mendelevium-257 | 10 |
| Mendelevium-258 | 0.01 |
| Any radionuclide other than alpha emitting radionuclides not listed above, or mixtures of beta emitters of unknown composition | 0.01 |
a The quantities listed above were derived by taking 1/10 of the most restrictive ALI listed in Table 1 Columns 1 and 2 of Schedule RHS 8-30 of this chapter, rounding to the nearest factor of 10, and arbitrarily constraining the values listed between 0.001 and 1,000 µCi (37 Bq and 37 MBq). Values of 100 µCi (3.7 MBq) have been assigned for radionuclides having a radioactive half-life in excess of 109 years, except rhenium, 1,000 µCi (37 MBq), to take into account their low specific activity.
NOTE: For purposes of Rules 0400-20-02-.111, 0400-20-05-.114, and 0400-20-05-.140, where there is involved a combination of radionuclides in known amounts, the limit for the combination shall be derived as follows: determine, for each radionuclide in the combination, the ratio between the quantity present in the combination and the limit otherwise established for the specific radionuclide when not in combination. The sum of such ratios for all radionuclides in the combination may not exceed "1" -- that is, unity.
*a To Convert µCi to KBq, multiply the µCi value by 37.
SCHEDULE RHS 8-32 ASSIGNED PROTECTION FACTORS FOR RESPIRATORS a
| Operating Modec | Assigned Protection Factors | |
| I. Air-Purifying Respirators [Particulateonly]c: | . | . |
| Filtering facepiece disposabled | Negative Pressure | (d) |
| Facepiece, halfe | Negative Pressure | 10 |
| Facepiece, full | Negative Pressure | 100 |
| Facepiece, half | Powered air-purifying respirators | 50 |
| Facepiece, full | Powered air-purifying respirators | 1000 |
| Helmet/hood | Powered air-purifying respirators | 1000 |
| Facepiece, loose-fitting | Powered air-purifying respirators | 25 |
| II. Atmosphere-Supplying Respirators | ||
| [Particulate, gases and vaporsf]: | ||
| 1. Air-line respirator: | . | . |
| Facepiece, half | Demand | 10 |
| Facepiece, half | Continuous Flow | 50 |
| Facepiece, half | Pressure Demand | 50 |
| Facepiece, full | Demand | 100 |
| Facepiece, full | Continuous Flow | 1000 |
| Facepiece, full | Pressure Demand | 1000 |
| Helmet/hood | Continuous Flow | 1000 |
| Facepiece, loose-fitting | Continuous Flow | 25 |
| Suit | Continuous Flow | (g) |
| 2. Self-contained breathing | . | . |
| apparatus (SCBA): | . | . |
| Facepiece, full | Demand | h100 |
| Facepiece, full | Pressure Demand | i10,000 |
| Facepiece, full | Demand, Recirculating | h100 |
| Facepiece, full | Positive Pressure Recirculating | i10,000 |
| Any combination of air-purifying and atmosphere-supplying respirators | Assigned protection factor for type and mode of operation as listed above | |
a These assigned protection factors apply only in a respiratory protection program that meets the requirements of this chapter. They are applicable only to airborne radiological hazards and may not be appropriate to circumstances when chemical or other respiratory hazards exist instead of, or in addition to, radioactive hazards. Selection and use of respirators for such circumstances must also comply with U. S. Department of Labor regulations. Radioactive contaminants for which the concentration values in Table 1, Column 3 of schedule RHS 8-32 in this rule are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under these circumstances, limitations on occupancy may have to be governed by external dose limits.
b Air purifying respirators with APF <100 shall be equipped with particulate filters that are at least 95 percent efficient. Air purifying respirators with APF=100 shall be equipped with particulate filters that are at least 99 percent efficient. Air purifying respirators with APFs >100 shall be equipped with particulate filters that are at least 99.97 percent efficient.
c The licensee may apply to the Division for the use of an APF greater than 1 for sorbent cartridges as protection against airborne radioactive gases and vapors (e.g., radioiodine).
d Licensees may permit individuals to use this type of respirator who have not been medically screened or fit tested on the device provided that no credit be taken for their use in estimating intake or dose. It is also recognized that it is difficult to perform an effective positive or negative pressure pre-use user seal check on this type of device. All other respiratory protection program requirements listed in Rule 0400-20-05-.92 apply. An assigned protection factor has not been assigned for these devices. However, an APF equal to 10 may be used if the licensee can demonstrate a fit factor of at least 100 by use of a validated or evaluated, qualitative or quantitative fit test.
e Under-chin type only. No distinction is made in this Schedule between elastomeric half-masks with replaceable cartridges and those designed with the filter medium as an integral part of the facepiece (e.g., disposable or reusable disposable). Both types are acceptable so long as the seal area of the latter contains some substantial type of seal-enhancing material such as rubber or plastic, the two or more suspension straps are adjustable, the filter medium is at least 95 percent efficient and all other requirements of this chapter are met.
f The assigned protection factors for gases and vapors are not applicable to radioactive contaminants that present an absorption or submersion hazard. For tritium oxide vapor, approximately one-third of the intake occurs by absorption through the skin so that an overall protection factor of 3 is appropriate when atmosphere-supplying respirators are used to protect against tritium oxide. Exposure to radioactive noble gases is not considered a significant respiratory hazard, and protective actions for these contaminants should be based on external (submersion) dose considerations.
g No NIOSH approval schedule is currently available for atmosphere supplying suits. This equipment may be used in an acceptable respiratory protection program as long as all the other minimum program requirements, with the exception of fit testing, are met (i.e., Rule 0400-20-05-.92) .
h The licensee should implement institutional controls to assure that these devices are not used in areas immediately dangerous to life or health (IDLH).
i This type of respirator may be used as an emergency device in unknown concentrations for protection against inhalation hazards. External radiation hazards and other limitations to permitted exposure such as skin absorption shall be taken into account in these circumstances. This device may not be used by any individual who experiences perceptible outward leakage of breathing gas while wearing the device.
SCHEDULE RHS 8-33
REQUIREMENTS FOR TRANSFER OF LOW-LEVEL RADIOACTIVE WASTE
FOR DISPOSAL AT LAND DISPOSAL FACILITIES AND MANIFESTS
I. Manifest.
A waste generator, collector, or processor who transports, or offers for transportation, low-level radioactive waste intended for ultimate disposal at a licensed low-level radioactive waste land disposal facility shall prepare a manifest. The manifest shall contain the information requested on applicable NRC Forms 540 (Uniform Low-Level Radioactive Waste Manifest (Shipping Paper)) and 541 (Uniform Low-Level Radioactive Waste Manifest (Container and Waste Description)) and, if necessary, on an applicable NRC Form 542 (Uniform Low-Level Radioactive Waste Manifest (Manifest Index and Regional Compact Tabulation)). NRC Forms 540 and 540A shall be completed and shall physically accompany the pertinent low-level waste shipment. Upon agreement between shipper and consignee, NRC Forms 541 and 541A and 542 and 542A may be completed, transmitted and stored in electronic media with the capability for producing legible, accurate and complete records of the respective forms. Licensees are not required to comply with the manifesting requirements of this rule when they ship:
1. LLW for processing and expect its return (i.e., for storage under their license) prior to disposal at a licensed land disposal facility;
2. LLW that is being returned to the licensee who is the "waste generator" or "generator," as defined in this rule; or
3. Radioactively contaminated material to a "'waste processor" that becomes the processor's "residual waste."
For guidance in completing these forms, refer to the instructions that accompany the forms. Copies of manifests required by this appendix may be legible carbon copies, photocopies or computer printouts that reproduce the data in the format of the uniform manifest.
NRC Forms 540, 540A, 541, 541A, 542 and 542A and the accompanying instructions, in hard copy, may be obtained from the Information and Records Management Branch, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 415-7232.
This appendix includes information requirements of the Department of Transportation, as codified in 49 CFR part 172. Information on hazardous, medical, or other waste, required to meet Environmental Protection Agency regulations, as codified in 40 CFR parts 259, 261 or elsewhere, is not addressed in this rule and must be provided on the required EPA forms. However, the required EPA forms shall accompany the Uniform Low-Level Radioactive Waste Manifest required by this chapter.
As used in this appendix, the following definitions apply:
1. "Chelating agent" has the same meaning as that given in Rule 0400-20-11-.03.
2. "Chemical description" means a description of the principal chemical characteristics of a low-level radioactive waste.
3. "Computer-readable medium" means that the regulatory agency's computer can transfer the information from the medium into its memory.
4. "Consignee" means the designated receiver of the shipment of low-level radioactive waste.
5. "Decontamination facility" means a facility operating under a license issued by the Division, the U.S. Nuclear Regulatory Commission, or another Agreement State, whose principal purpose is decontamination of equipment or materials to accomplish recycle, reuse or other waste management objectives and, for purposes of this rule, is not considered to be a consignee for LLW shipments.
6. "Disposal container" means a container principally used to confine low-level radioactive waste during disposal operations at a land disposal facility (also see "high integrity container"). Note that for some shipments, the disposal container may be the transport package.
7. "EPA identification number" means the number received by a transporter following application to the Administrator of EPA as required by 40 CFR 263.
8. "Generator" means a licensee operating under a license issued by the Division, the U.S. Nuclear Regulatory Commission, or another Agreement State who:
a. Is a waste generator as defined in this rule, or
b. Is the licensee to whom waste can be attributed within the context of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (e.g., waste generated as a result of decontamination or recycle activities).
9. "High integrity container" (HIC) means a container commonly designed to meet the structural stability requirements of paragraph (7) of Rule 0400-20-11-.17 and to meet Department of Transportation requirements for a Type A package.
10. "Land disposal facility" has the same meaning as that given in Rule 0400-20-11-.03.
11. "NRC Forms 540, 540A, 541, 541A, 542 and 542A" means official NRC Forms referenced in this appendix. Licensees need not use originals of these NRC Forms as long as any substitute forms are equivalent to the original documentation in respect to content, clarity, size and location of information. Upon agreement between the shipper and consignee, NRC Forms 541 (and 541A) and NRC Forms 542 (and 542A) may be completed, transmitted and stored in electronic media. The electronic media shall have the capability for producing legible, accurate and complete records in the format of the uniform manifest.
12. "Package" means the assembly of components necessary to ensure compliance with the packaging requirements of U.S. DOT regulations, together with its radioactive contents, as presented for transport.
13. "Physical description" means the items called for on NRC Form 541 to describe a low-level radioactive waste.
14. "Residual waste" means low-level radioactive waste resulting from processing or decontamination activities that cannot be easily separated into distinct batches attributable to specific waste generators. This waste is attributable to the processor or decontamination facility, as applicable.
15. "Shipper" means the licensed entity (i.e., the waste generator, waste collector, or waste processor) who offers low-level radioactive waste for transportation, typically consigning this type of waste to a licensed waste collector, waste processor, or land disposal facility operator.
16. "Shipping paper" means NRC Form 540 and, if required, NRC Form 540A which includes the information required by U.S. DOT in 49 CFR 172.
17. "Source material" has the same meaning as that given in Rule 0400-20-05-.32.
18. "Special nuclear material" has the same meaning as that given in T.C.A. §68-202-202(1).
19. "Uniform Low-Level Radioactive Waste Manifest" (or "uniform manifest") means the combination of NRC Forms 540, 541 and, if necessary, 542 and their respective continuation sheets as needed, or equivalent.
20. "Waste collector" means an entity, operating under a license issued by the Division, the U.S. NRC or another Agreement State, whose principal purpose is to collect and consolidate waste generated by others and to transfer this waste, without processing or repackaging the collected waste, to another licensed waste collector, licensed waste processor or licensed land disposal facility.
21. "Waste description" means the physical, chemical and radiological description of a low-level radioactive waste as called for on NRC Form 541.
22. "Waste generator" means an entity, operating under a license issued by the Division, the U.S. NRC or another Agreement State, who:
a. Possesses any material or component that contains radioactivity or is radioactively contaminated for which the licensee foresees no further use, and:
b. Transfers this material or component to a licensed land disposal facility or to a licensed waste collector or processor for handling or treatment before disposal. A licensee performing processing or decontamination services may be a "waste generator" if the transfer of low-level radioactive waste from its facility is defined as "residual waste."
23. "Waste processor" means an entity, operating under a license issued by the Division, the U.S. NRC or another Agreement State, whose principal purpose is to process, repackage or otherwise treat low-level radioactive material or waste generated by others before eventual transfer of waste to a licensed low-level radioactive waste land disposal facility.
24. "Waste type" means a waste within a disposal container having a unique physical description (i.e., a specific waste descriptor code or description; or a waste sorbed on or solidified in a specifically defined media).
Information Requirements
A. General Information
The shipper of the radioactive waste shall provide the following information on the uniform manifest:
1. The name, facility address and telephone number of the licensee shipping the waste.
2. An explicit declaration indicating whether the shipper is acting as a waste generator, collector, processor, or a combination of these identifiers for the purposes of the manifested shipment; and
3. The name, address and telephone number, or the name and U.S. EPA hazardous waste identification number for the carrier transporting the waste to the land disposal facility.
B. Shipment Information
The shipper of the radioactive waste shall provide the following information regarding the waste shipment on the uniform manifest:
1. The date of the waste shipment;
2. The total number of packages/disposal containers;
3. The total disposal volume and disposal weight in the shipments;
4. The total radionuclide activity in the shipment;
5. The activity of each of the radionuclides H-3, C-14, Tc-99, and I-129 contained in the shipment; and
6. The total masses of U-233, U-235, and plutonium in special nuclear material, and the total mass of uranium and thorium in source material.
C. Disposal Container and Waste Information.
The shipper of the radioactive waste shall provide the following information on the uniform manifest regarding the waste and each disposal container of waste in the shipment:
1. An alphabetic or numeric identification that uniquely identifies each disposal container in the shipment;
2. A physical description of the disposal container, including the manufacturer and model of any high integrity container;
3. The volume displaced by the disposal container;
4. The gross weight of the disposal container, including the waste;
5. For waste consigned to a disposal facility, the maximum radiation level at the surface of each disposal container;
6. A physical and chemical description of the waste;
7. The total weight percentage of chelating agent for any waste containing more than 0.1 percent chelating agent by weight, plus the identity of the principal chelating agent;
8. The approximate volume of waste within a container;
9. The sorbing or solidification media, if any, and the identity of the solidification media vendor and brand name;
10. The identities and activities of individual radionuclides contained in each container, the masses of U-233, U-235 and plutonium in special nuclear material, and the masses of uranium and thorium in source material. For discrete waste types (i.e., activated materials, contaminated equipment, mechanical filters, sealed source/devices and wastes in solidification/stabilization media), the identities and activities of individual radionuclides associated with or contained on these waste types within a disposal container shall be reported;
11. The total radioactivity within each container; and
12. For wastes consigned to a disposal facility, the classification of the waste under paragraph (6) of Rule 0400-20-11-.17. Waste not meeting the structural stability requirements of subparagraph (7)(b) of Rule 0400-20-11-.17 shall be identified.
D. Uncontainerized Waste Information.
The shipper of the radioactive waste shall provide the following information on the uniform manifest regarding a waste shipment delivered without a disposal container:
1. The approximate volume and weight of the waste;
2. A physical and chemical description of the waste;
3. The total weight percentage of chelating agent if the chelating agent exceeds 0.1% by weight, plus the identity of the principal chelating agent;
4. For waste consigned to a disposal facility, the classification of the waste under paragraph (6) of Rule 0400-20-11-.17. Waste not meeting the structural stability requirements of subparagraph (7)(b) of Rule 0400-20-11-.17 shall be identified;
5. The identities and activities of individual radionuclides contained in the waste, the masses of U-233, U-235 and plutonium in special nuclear material, and the masses of uranium and thorium in source material; and
6. For wastes consigned to a disposal facility, the maximum radiation levels at the surface of the waste.
E. Multi-Generator Disposal Container Information.
This section applies to disposal containers enclosing mixtures of waste originating from different generators. (Note: The origin of the LLW resulting from a processor's activities may be attributable to one or more "generators" (including "waste generators") as defined in this rule). It also applies to mixtures of wastes shipped in an uncontainerized form, for which portions of the mixture within the shipment originate from different generators.
1. For homogeneous mixtures of waste, such as incinerator ash, provide the waste description applicable to the mixture and the volume of the waste attributed to each generator.
2. For heterogeneous mixtures of waste, such as the combined products from a large compactor, identify each generator contributing waste to the disposal container and, for discrete waste types (i.e., activated materials, contaminated equipment, mechanical filters, sealed source/devices and wastes in solidification/stabilization media), the identities and activities of individual radionuclides contained on these waste types within the disposal container. For each generator, provide the following:
a. The volume of waste within the disposal container;
b. A physical and chemical description of the waste, including the solidification agent, if any;
c. The total weight percentage of chelating agents for any disposal container containing more than 0.1 percent chelating agent by weight, plus the identity of the principal chelating agent;
d. The sorbing or solidification media, if any, and the identity of the solidification media vendor and brand name if the media is claimed to meet stability requirements in subparagraph (7)(b) of Rule 0400-20-11-.17; and
e. Radionuclide identities and activities contained in the waste, the masses of U-233, U-235 and plutonium in special nuclear material, and the masses of uranium and thorium in source material if contained in the waste.
II. Certification.
An authorized representative of the waste generator, processor, or collector shall certify by signing and dating the shipment manifest that the transported materials are properly classified, described, packaged, marked and labeled and are in proper condition for transportation according to the applicable regulations of the U.S. Department of Transportation, the U.S. Nuclear Regulatory Commission and the Division of Radiological Health. A collector, in signing the certification, is certifying that nothing has been done to the collected waste that would invalidate the waste generator's certification.
III. Control and Tracking.
A. Any licensee who transfers radioactive waste to a land disposal facility or a licensed waste collector shall comply with the requirements in paragraphs A.1 through 9 of this section. Any licensee who transfers waste to a licensed waste processor for waste treatment or repackaging shall comply with the requirements of paragraphs A.4 through 9 of this section. A licensee shall:
1. Prepare all waste so that the waste is classified according to paragraph (6) of Rule 0400-20-11-.17 and meets the waste characteristics requirements in paragraph (7) of Rule 0400-20-11-.17;
2. Label each disposal container (or transport package if potential radiation hazards preclude labeling of the individual disposal container) of waste to identify whether it is Class A waste, Class B waste, Class C waste or greater than Class C waste, in accordance with paragraph (6) of Rule 0400-20-11-.17;
3. Conduct a quality assurance program to assure compliance with paragraphs (6) and (7) of Rule 0400-20-11-.17 (the program shall include management evaluation of audits);
4. Prepare the NRC Uniform Low-Level Radioactive Waste Manifest as required by this appendix;
5. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either:
a. Receipt of the manifest precedes the LLW shipment, or
b. The manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee.
c. Using both a. and b. is also acceptable;
6. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in part 5 of this subparagraph;
7. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;
8. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by Chapter 0400-20-10; and
9. For any shipments or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with Section III.E. of this Schedule.
B. Any waste collector licensee who handles only prepackaged waste shall:
1. Acknowledge receipt of the waste from the shipper within one week of receipt by returning a signed copy of NRC Form 540;
2. Prepare a new manifest to reflect consolidated shipments that meet the requirements of this appendix. The waste collector shall ensure that, for each container of waste in the shipment, the manifest identifies the generator of that container of waste;
3. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either:
a. Receipt of the manifest precedes the LLW shipment, or
b. The manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee.
c. Using both a. and b. is also acceptable;
4. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in part 3 of this subparagraph;
5. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;
6. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by Chapter 0400-20-10;
7. For any shipments or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with Section III.E. of this Schedule; and
8. Notify the shipper and the Director, Division of Radiological Health, when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.
C. Any licensed waste processor who treats or repackages waste shall:
1. Acknowledge receipt of the waste from the shipper within 1 week of receipt by returning a signed copy of NRC Form 540;
2. Prepare a new manifest that meets the requirements of this appendix. Preparation of the new manifest reflects that the processor is responsible for meeting these requirements. For each container of waste in the shipment, the manifest shall identify the waste generators, the preprocessed waste volume and the other information required in Section I.E. of this Schedule;
3. Prepare all waste so that the waste is classified according to paragraph (6) of Rule 0400-20-11-.17 and meets the waste characteristics requirements in paragraph (7) of Rule 0400-20-11-.17;
4. Label each package of waste to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with paragraphs (6) and (8) of Rule 0400-20-11-.17;
5. Conduct a quality assurance program to assure compliance with paragraphs (6) and (7) of Rule 0400-20-11-.17 (the program shall include management evaluation of audits);
6. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either:
a. Receipt of the manifest precedes the LLW shipment, or
b. The manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee.
c. Using both a. and b. is also acceptable;
7. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in Subsection III.C.6 of this Schedule;
8. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;
9. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by Chapter 0400-20-10;
10. For any shipment or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with Section III.E. of this Schedule; and
11. Notify the shipper and the Director, Division of Radiological Health, when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.
D. The land disposal facility operator shall:
1. Acknowledge receipt of the waste within 1 week of receipt by returning, as a minimum, a signed copy of NRC Form 540 to the shipper. The shipper to be notified is the licensee who last possessed the waste and transferred the waste to the operator. If any discrepancy exists between materials listed on the Uniform Low-Level Radioactive Waste Manifest and materials received, copies or electronic transfer of the affected forms must be returned indicating the discrepancy;
2. Maintain copies of all completed manifests and electronically store the information required by paragraph (1) of Rule 0400-20-11-.19 until the Division terminates the license; and
3. Notify the shipper and the Director, Division of Radiological Health, when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.
E. Any shipment or part of a shipment for which acknowledgement is not received within the times set forth in this section shall:
1. Be investigated by the shipper if the shipper has not received notification or receipt within 20 days after transfer; and
2. Be traced and reported. The investigation shall include tracing the shipment and filing a report with the Director, Division of Radiological Health, at the address given in Rule 0400-20-04-.07. Each licensee who conducts a trace investigation shall file a written report with the Division within 2 weeks of completion of the investigation.
Tenn. Comp. R. & Regs. 0400-20-05-.161
Authority: T.C.A. §§ 68-202-101 et seq., 68-202-201 et seq. and 4-5-201 et seq.