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Radiation Safety Guide


 
Radiation Safety Guide

APPENDIX B

Appendix B is an abridged version of the Appendix B to "10 CFR Part 20" For the Table 1, 2 or 3 values for any radioisotopes which are not listed in this Appendix, contact the Office of Environmental Health and Safety.

Table 1: ANNUAL LIMITS ON INTAKE (ALIs) AND DERIVED AIR CONCENTRATIONS (DACs) OF RADIONUCLIDES FOR OCCUPATIONAL EXPOSURE
For each radionuclide, Table 1 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 mm 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 of less than 10 days for D, 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 1, columns 2 and 3.

Table 2: EFFLUENT CONCENTRATIONS
Table 2 provides concentrations limits for airborne and liquid effluents released to the general environment.

Table 3: CONCENTRATIONS FOR RELEASE TO SEWERAGE
Table 3 provides concentration limits for discharges to sanitary sewer systems.

Page B.2, which comes directly from Appendix B to "10 CFR Part 20", provides additional information about the derivation and use of Tables 1, 2, and 3.


FOOTNOTES:

1. "Submersion" means that values given are for submersion in a hemispherical semi-infinite cloud of a 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 Authorized User 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 Section 8.3.3 and 10 CFR 20.1203)

3. For soluble mixtures of U-238 and U-235 in air, chemical toxicity may be the limiting factor (see 10 CFR 20.1201(e) for more details.)

NOTE:

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 listed in this Appendix or in Appendix B to 10 CFR 20.1001-20.2401 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::

CA..........CB..........CC
------ + ------ + ------ < 1
DACA.....DACB......DACC

 

       
       
     

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