South Carolina Code of Regulations › Chapter 61 - DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL › Subchapter 61-63 - Radioactive Materials (Title A) › Part III - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 61-63.III.RHA 3.53 - [Appendix B] Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage

Current through Register Vol. 48, No. 6, June 28, 2024
Introduction
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 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 halftimes
				  for 0 of less than 10 days, for W from 10 to 100 days, and for Y greater than 100
				  days. Table 2 provides concentration limits for airborne and liquid effluents
				  released to the general environment. Table 3 provides concentration limits for
				  discharges to sanitary sewer systems.
Note:
The values in Tables 1, 2, and 3 are presented in the computer "E"
				  notation. In this notation a value of 6E-02 represents a value of 6 ×
				  10-2 or 0.06, 6E+" 2 represents 6 ×
				  1O2 or 600, and 6E+" 0 represents 6 ×
				  100 or 6.
Table 1 "Occupational Values"
Note that the columns in Table 1 of this appendix captioned "Oral
				  Ingestion ALI," "Inhalation ALI," and "DAC," are applicable to occupational exposure
				  to radioactive material.
The ALIs in this appendix are the annual intakes of given
				  radionuclide by "Reference Man" which would result in either (1) a committed
				  effective dose equivalent of 5 rems (stochastic ALI) or (2) a committed dose
				  equivalent of 50 rems 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 5
				  rems. 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
				  RHA
				  3.2. 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
				  parts 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 extremities (hands and
				  forearms, feet and lower legs), 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.
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: LLI wall = lower large intestine wall; St. wall = stomach wall; Blad wall
				  = bladder wall; and 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, use of that non-stochastic ALI is considered unduly
				  conservative, the licensee may use the stochastic ALI to determine the committed
				  effective dose equivalent. However, the licensee shall also ensure that the 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 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 (i.e., (intake (in Ci) of each radionuclide/ALIins) 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 being 1.0.
Note that the dose equivalents for extremities (hand and forearms,
				  feet and lower legs), skin, and lens of the are 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: DAC = ALI(in Ci)/(2000 hours per working year × 60
				  minutes/hour × 2 × 10 ml per minute) = [ALI/2.4 × 10] Ci/ml, where
				  2 × 10 ml per minute is the volume of air breathed per minute at work by
				  "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. Derived air concentrations 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 relate to exposure to the single
				  radionuclide named, but also include contributions from the in-growth of any
				  daughter radionuclide produced in the body by the 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 value 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
				  RHA 3.6). When an individual is
				  exposed to radioactive materials which fall under several of the translocation
				  classifications (i.e., Class D, Class W, or Class Y) of the same radionuclide, 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 2 "Effluent Concentrations"
The columns in Table 2 of this appendix captioned "Effluents,"
				  "Air," and "Water," are applicable to the assessment and control of dose to the
				  public, particularly in the implementation of the provisions of
				  RHA 3.14. The concentration values
				  given in Columns 1 and 2 of Table 2 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 0.05 rem (50 millirem or 0.5
				  millisieverts).
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 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 2. For this reason, the DAC and
				  airborne effluent limits are not always proportional as was the case in Appendix A
				  of Part III of the July 1990 edition of Radioactive Materials Regulation 61-63,
				  Title A.
The air concentration values listed in Table 2, 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
				  × 10, 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 5-rem annual occupational dose limit to the 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 (external dose) is
				  limiting, the occupational DAC in Table 1, 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 ×
				  10. The factor of 7.3 × 10 (ml) includes the following components: the factors
				  of 50 and 2 described above and a factor of 7.3 × 10 (ml) which is the annual
				  water intake of "Reference Man."
Note 2 of this appendix 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
				  sewerage) require demonstrating that the most limiting radionuclides in successive
				  classes are absent. The limit for the unknown mixture is defined when the presence
				  of the 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 3 "Releases to Sewers"
The monthly average concentrations for release to sanitary sewers
				  are applicable to the provisions in
				  RHA 3.29. The concentration values
				  were derived by taking the most restrictive occupational stochastic oral ingestion
				  ALI and dividing by 7.3 × 10(ml). The factor of 7.3 × 10(ml) is composed
				  of a factor of 7.3 × 10(ml), the annual water intake by "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 0.5 rem.
List of Elements
Name
Symbol
Atomic No.
Actinium ................................
Ac
89
Aluminium ...............................
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
Krypton .................................
Kr
36
Lanthanum ...............................
La
57
Lead ....................................
Pb
82
Lutetium ................................
Lu
71
Magnesium ...............................
Mg
12
Manganese ...............................
Mn
25
Mendelevium .............................
Md
101
Mercury .................................
Hg
80
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
Thullium ................................
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
RHA 3.53 [Appendix B] Annual Limits on Intake (ALIs) and Derived
				  Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent
				  Concentrations; Concentrations for Release to Sewerage.
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