Wis. Admin. Code DHS § , DHS 110-199, ch. DHS 157, app E

Current through October 28, 2024
Appendix E

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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Wis. Admin. Code Department of Health Services, DHS 110-199, ch. DHS 157, app E

Amended by, Register January 2018 No. 745, eff. 2/1/2018