New York Codes, Rules and Regulations › Title 10 - DEPARTMENT OF HEALTH › Chapter - APPENDICES › Appendix 16-C

Current through Register Vol. 46, No. 28, July 10, 2024
APPENDIX 16-C
ANNUAL LIMITS ON INTAKE (ALI) AND DERIVED AIR
				CONCENTRATIONS (DAC) OF RADIONUCLIDES FOR OCCUPATIONAL EXPOSURE: EFFLUENT
				CONCENTRATIONS: CONCENTRATIONS FOR RELEASE TO SANITARY
				SEWARAGE
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 um, 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. Table 2 provides concentration limits
				for airborne and liquid effluents released to the general environment. Table 3
				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 × 10-2 or 0.06, 6E+2 represents 6 × 10
				2 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 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, W T. 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 W T are listed
				under the definition of weighting factor in section 16.2. 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 W T = 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 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 (ALI ns)
				that contribute to the committed dose equivalent to the organ receiving the
				highest dose does not exceed unity, that is, [SIGMA] (intake (in µCi) of each
				radionuclide/ALI ns) <= 1.0. If there is an external
				deep dose equivalent contribution of Hd, then this sum
				must be less than 1 - (H d/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:
DAC = ALI(in µCi)/(2000 hours per working year × 60
				minutes/hour × 2 × 10 4 ml per minute) = [ALI/2.4 ×
				10 9] µCi/ml,
where 2 × 10 4 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. 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 section 16.6(b). 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 radionuclides. 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 section
				16.7(b). 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 0.50 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 2. For this
				reason, the DAC and airborne effluent limits are not always proportional as was
				the case in Appendix 16-A6 Table 4 of the revision of Part 16 effective
				December 30, 1992.
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 9, 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 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 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
				7. The factor of 7.3 × 10
				7 (ml) includes the following components: the
				factors of 50 and 2 described above and a factor of 7.3 × 10
				5 (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 3 "Releases to Sewers"
The monthly average concentrations for release to sanitary
				sewerage are applicable to the provisions in section 16.8(c). The concentration
				values were derived by taking the most restrictive occupational stochastic oral
				ingestion ALI and dividing by 7.3 × 10 6 (ml). The
				factor of 7.3 × 10 6 (ml) is composed of a factor of
				7.3 × 10 5 (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 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
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
Osmium
Os
76
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
Th
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
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