DHS 157.22(1)(c)2.c.c. If a protective apron is worn, the individual monitoring device shall be located at the neck, which is, collar. If a second monitoring device is used, for the same purpose, it shall be located under the protective apron at the waist. The estimated effective dose equivalent (HE) when wearing 2 monitoring devices, one located outside and one under a protective apron, shall be calculated using the following formula: HE (estimate) = 1.5 HW + 0.04 HN where HW = badge reading from the waist badge under the apron and HN = badge reading from the neck badge worn outside the apron. DHS 157.22(1)(d)(d) Derived air concentration and annual limit on intake values are specified in Table I of ch. DHS 157 Appendix E and may be used to determine the individual’s dose and to demonstrate compliance with the occupational dose limits. DHS 157.22 NoteNote: See s. DHS 157.31 (7) for instructions about recording the exposure levels. DHS 157.22(1)(e)(e) In addition to the annual dose limits, a licensee or registrant shall limit the soluble uranium intake by an individual to 10 milligrams in a week in consideration of chemical toxicity. DHS 157.22 NoteNote: See footnote c/ of ch. DHS 157 Appendix E for the calculation method for determining DAC for soluble mixtures of uranium. DHS 157.22(1)(f)(f) A licensee or registrant shall reduce the dose that an individual may be allowed to receive in the current year by the amount of occupational dose received while employed by any other person during the current year. DHS 157.22 NoteNote: See sub. (5) for instruction on determining occupational dose.
DHS 157.22(2)(2) Compliance with requirements for summation of external and internal doses. DHS 157.22(2)(a)(a) If a licensee or registrant is required to monitor under both s. DHS 157.25 (2) (a) and (b), a licensee or registrant shall demonstrate compliance with the dose limits by summing external and internal doses. If a licensee or registrant is required to monitor only under s. DHS 157.25 (2) (a) or (b), then summation is not required to demonstrate compliance with the dose limits. A licensee or registrant may demonstrate compliance with the requirements for summation of external and internal doses by meeting one of the conditions in par. (b) and the conditions of pars. (c) and (d). The dose equivalents for the lens of the eye, the skin and the extremities are not included in the summation, but are subject to separate limits. DHS 157.22(2)(b)(b) If the only intake of radionuclides is by inhalation, the total effective dose equivalent limit is not exceeded if the sum of the deep dose equivalent divided by the total effective dose equivalent limit, and any one of the following, does not exceed unity: DHS 157.22(2)(b)1.1. The sum of the fractions of the inhalation ALI for each radionuclide. DHS 157.22(2)(b)2.2. The total number of derived air concentration-hours for all radionuclides divided by 2,000. DHS 157.22(2)(b)3.3. The sum of the calculated committed effective dose equivalents to all significantly irradiated organs or tissues calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit. For purposes of this subdivision, an organ or tissue is deemed to be significantly irradiated if, for that organ or tissue, the product of the weighting factors, wT, and the committed dose equivalent, HT,50, per unit intake is greater than 10% of the maximum weighted value of HT,50, that is, wTHT,50, per unit intake for any organ or tissue. DHS 157.22(2)(c)(c) If the occupationally exposed individual also receives an intake of radionuclides by oral ingestion greater than 10% of the applicable oral ALI, a licensee or registrant shall account for this intake and include it in demonstrating compliance with the limits. DHS 157.22(2)(d)(d) A licensee or registrant shall evaluate and, to the extent practical, account for intakes through wounds or skin absorption. The intake through intact skin has been included in the calculation of DAC for hydrogen-3 and does not need to be evaluated or taken into account. DHS 157.22(3)(3) Determination of external doses from airborne radioactive material. DHS 157.22(3)(a)(a) A licensee or registrant shall, when determining the dose from airborne radioactive material, include the contribution to the deep dose equivalent, eye dose equivalent, and shallow dose equivalent from external exposure to the radioactive cloud. DHS 157.22 NoteNote: See Appendix E, footnotes a/ and b/ for methods used for calculating dose from exposure to a radioactive cloud for materials that have a half-life of less than 2 hours.
DHS 157.22(3)(b)(b) Airborne radioactivity measurements and DAC values may not be used as the primary means to assess the deep dose equivalent when the airborne radioactive material includes radionuclides other than noble gases or if the cloud of airborne radioactive material is not relatively uniform in its distribution of radioactive material in the cloud. The determination of the deep dose equivalent to an individual shall be based upon measurements using instruments or individual monitoring devices. DHS 157.22(4)(a)(a) For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, a licensee or registrant shall, when required under s. DHS 157.25 (2), take suitable and timely measurements of all of the following: DHS 157.22(4)(b)(b) Unless respiratory protective equipment is used, as provided in s. DHS 157.27 (3), or the assessment of intake is based on bioassays, a licensee or registrant shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present. DHS 157.22(4)(c)(c) When the physical and biochemical properties of the radionuclides taken into the body or the behavior of the material in an individual is known, a licensee or registrant may do any of the following: DHS 157.22(4)(c)1.1. Use that information to calculate the committed effective dose equivalent, and, if used, the licensee or registrant shall document that information in the individual’s record. DHS 157.22(4)(c)2.2. Upon prior approval of the department, adjust the DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive material, for example, aerosol size distribution or density.