Wisconsin Administrative Code › Department of Health Services › DHS 110-199 - Health › Chapter DHS 157 - Radiation Protection › Appendix E

Current through June 24, 2024
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 m(micron), and for the D, W and Y classes of
				  radioactive material, which refer to their retention 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 D, W or Y class given in the column headed "Class" applies only to
				  the inhalation ALIs and DACs given in Table I, column 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.
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
				  1O-2 or 600, and 6E+0 represents 6 x
				  100 or 6.
Table I "Occupational Values"
Note that the columns in Table I 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 0.05 Sv (5 rem), stochastic ALI,
				  or (2) 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 s.
				  DHS
				  157.03. The non-stochastic ALIs were derived to avoid
				  non-stochastic effects, such as prompt damage to tissue or reduction in organ
				  function.
Note: A description of the reference man is contained in the
				  International Commission on Radiological Protection report, ICRP Publication
				  23,
Reference Man: Anatomical Physiological and Metabolic
				  Characteristics
, Pergamon Press, Oxford (1975). The publication
				  may be ordered from the web-site
http://www.icrp.org/publications.asp
.
A value of wT = 0.06 is applicable to
				  each of the 5 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 4 separate organs. 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.
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 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 that contribute to the committed
				  dose equivalent to the organ receiving the highest dose does not exceed unity,
				  that is, intake 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.
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(mCi) /(2000 hours per working year x 60 minutes/
				  hour x 2 x 104 ml per minute) = [ALI/2.4 x
				  109] mCi/ml,
where 2 x 104 ml is the volume of
				  air breathed per minute at work by reference man under working conditions of
				  light work.
The DAC values relate to 1 of 2 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 in-growth 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 s.
				  DHS
				  157.22(2). When an individual is
				  exposed to radioactive materials that 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 radionuclides. 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 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 s.
				  DHS
				  157.23(2). 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
.
The air concentration values listed in Table II, Column 1
				  were derived by one of 2 methods. For those radionuclides for which the
				  stochastic limit is governing, the occupational stochastic inhalation ALI was
				  divided by 2.4 x 109 ml, 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 1 mSv (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 of a
				  8,760 hour full-time exposure 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 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 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 s.
				  DHS
				  157.30(3). 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 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).
Name
Symbol
Atomic Number
Actinium
Ac
89
Aluminum
A
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
Tv
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
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