12 CRR-NY 38.18NY-CRR

STATE COMPILATION OF CODES, RULES AND REGULATIONS OF THE STATE OF NEW YORK
TITLE 12. DEPARTMENT OF LABOR
CHAPTER I. INDUSTRIAL BOARD OF APPEALS
SUBCHAPTER A. THE INDUSTRIAL CODE
PART 38. IONIZING RADIATION PROTECTION
12 CRR-NY 38.18
12 CRR-NY 38.18
38.18 Occupational dose limits.
(a) Occupational dose limits for adults.
(1) Except for planned special exposures pursuant to subdivision (f) of this section, no person shall transfer, receive, possess or use any radiation source so as to cause any individual adult to receive an occupational dose from all sources of radiation that exceeds any of the following limits:
(i) an annual limit, which is the more limiting of:
(a) a total effective dose equivalent equal to 0.05 Sv (5 rem); or
(b) the sum of the deep dose equivalent and the committed dose equivalent to any individual organ or tissue, other than the lens of the eye, equal to 0.50 Sv (50 rem);
(ii) annual limits to the lens of the eye, to the skin, and to the extremities which are:
(a) an eye dose equivalent of 0.15 Sv (15 rem); and
(b) a shallow dose equivalent of 0.50 Sv (50 rem) to the skin or to any extremity.
(2) Doses received in excess of the annual limits, including doses received during accidents, emergencies, and planned special exposures must be subtracted from the limits for planned special exposures that the individual may receive during the current year and during the individual's lifetime. (See paragraph [f][5] of this section.)
(3) The assigned deep dose equivalent and shallow dose equivalent shall be for the portion of the body receiving the highest exposure. If an individual's monitoring device was not in the region of highest potential exposure, or the results of individual monitoring are unavailable, the deep dose equivalent, eye dose equivalent and shallow dose equivalent may be assessed from surveys or other radiation measurements for the purpose of demonstrating compliance with the occupational dose limits.
(4) Derived air concentration (DAC) and annual limit on intake (ALI) values are presented in Appendix A-13 of section 38.41 of this Part (rule), and may be used to determine the individual's dose and to demonstrate compliance with the occupational dose limits.
(5) Notwithstanding the annual dose limits, the licensee shall limit the soluble uranium intake by an individual to 10 milligrams in a week. (See footnote 3 of Appendix A-13 of section 38.41 of this Part [rule].)
(6) The 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. (See subdivision [e]of this section.)
(b) Compliance with requirements for summation of external and internal dose.
(1) Requirements for summation of external and internal doses. If the licensee or registrant is required to monitor pursuant to both subdivisions (a) and (b) of section 38.24 of this Part (rule), the licensee or registrant shall demonstrate compliance with the dose limits by summing external and internal doses. If the licensee or registrant is required to monitor only pursuant to section 38.24(a) or only pursuant to section 38.24(b) of this Part (rule), then summation is not required in order to demonstrate compliance with the dose limits. The licensee or registrant may demonstrate compliance with the requirements for summation of external and internal doses by meeting one of the conditions specified in paragraph (2) of this subdivision, and the conditions in paragraphs (3) and (4) of this subdivision. The dose equivalents for the lens of the eye, the skin, and the extremities are not to be included in the summation, but are subject to separate limits.
(2) Intake by inhalation. 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 one of the following, does not exceed unity:
(i) the sum of the fractions of the inhalation ALI for each radionuclide; or
(ii) the total number of derived air concentrations-hours (DAC-hours) for all radionuclides divided by 2,000; or
(iii) the sum of the calculated committed effective dose equivalents to all significantly irradiated organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit. For purposes of this requirement, 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, H T,50, per unit intake is greater than 10 percent of the maximum weighted value of H50, that is, WTH T,50 per unit intake for any organ or tissue.
(3) Intake by oral ingestion. If the occupationally exposed individual also receives an intake of radionuclides by oral ingestion greater than 10 percent of the applicable oral ALI, the licensee or registrant shall account for this intake and include it in demonstrating compliance with the limits.
(4) Intake through wounds or absorption through skin. The licensee or registrant shall evaluate and 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 accounted for pursuant to this paragraph.
(c) Determination of external dose from airborne radioactive material.
(1) Licensees 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 (see footnotes 1 and 2 of Appendix A-13 of section 38.41 of this Part [rule]).
(2) Airborne radioactivity measurements and DAC values shall 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. The determination of the deep dose equivalent to an individual in these cases shall be based upon measurements using instruments or individual monitoring devices.
(d) Determination of internal exposure.
(1) For purposes of assessing dose used to deter mine compliance with occupational dose equivalent limits, the licensee shall, when required under section 38.24 of this Part (rule), take any of the following measurements as may be necessary for timely and appropriate detection and assessment of intake of radioactivity by individuals:
(i) concentrations of radioactive materials in air in work areas;
(ii) quantities of radionuclides in the body;
(iii) quantities of radionuclides excreted from the body; or
(iv) combinations of these measurements.
(2) Unless respiratory protective equipment is used, as provided in section 38.26 of this Part (rule), or the assessment of intake is based on bioassays, the licensee or registrant shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present.
(3) When specific information on the physical and biochemical properties of the radionuclides taken into the body or the behavior of the material in an individual is known, the licensee or registrant may:
(i) 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; and
(ii) separately assess the contribution of fractional intakes of Class D, W, or Y compounds of a given radionuclide to the committed effective dose equivalent.
(4) If the licensee chooses to assess intakes of Class Y material using the measurements listed in subparagraph (1)(ii) or (iii) of this subdivision, the licensee or registrant may delay the recording and reporting of the assessments for periods up to seven months, unless otherwise required by section 38.29(b)(1) and (2) of this Part (rule). This delay permits the licensee or registrant to make additional measurements basic to the assessments.
(5) If the identity and concentration of each radionuclide in a mixture are known, the fraction of the DAC applicable to the mixture for use in calculating DAC-hours shall be either:
(i) the sum of the ratios of the concentration to the appropriate DAC value, that is, D, W, or Y, from Appendix A-13, for each radionuclide in the mixture; or
(ii) the ratio of the total concentration for all radionuclides in the mixture to the most restrictive DAC value for any radionuclide in the mixture.
(6) If the identity of each radionuclide in a mixture is known, but the concentration of one or more of the radionuclides in the mixture is not known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture.
(7) When a mixture of radionuclides in air exists, a licensee may disregard certain radionuclides in the mixture if:
(i) the licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in subdivision (a) of this section and in complying with the monitoring requirements in section 38.24(b) of this Part (rule);
(ii) the concentration of any radionuclide disregarded is less than 10 percent of its DAC; and
(iii) the sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent.
(8) When determining the committed effective dose equivalent, the following information may be considered:
(i) in order to calculate the committed effective dose equivalent, the licensee or registrant may assume that the inhalation of one ALI, or an exposure of 2,000 DAC-hours, results in a committed effective dose equivalent of 0.05 Sv (5 rem) for radionuclides that have their ALIs or DACs based on the committed effective dose equivalent;
(ii) for an ALI and associated DAC which are based upon the nonstochastic organ dose limit of 0.50 Sv (50 rem), the intake of radionuclides that would result in a committed effective dose equivalent of 0.05 Sv (5 rem), that is, the stochastic ALI, is listed in parentheses in Appendix A-13. The licensee or registrant may, as a simplifying assumption, use the stochastic ALIs to determine committed effective dose equivalent. However, if the licensee or registrant uses the stochastic ALIs, the licensee or registrant shall also demonstrate that the limit in clause (a)(1)(i)(b) of this section is met.
(e) Determination of prior occupational dose.
(1) For each individual who may enter the licensee's or registrant's restricted area and is likely to receive, in a year, an occupational dose requiring monitoring pursuant to section 38.24 of this Part (rule), the licensee or registrant shall:
(i) determine the occupational radiation dose received during the current year; and
(ii) request in writing the records of lifetime cumulative occupational radiation dose.
(2) Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant shall determine:
(i) the internal and external doses received by the individual from all previous planned special exposures; and
(ii) all doses in excess of the limits received during the individual's lifetime, including doses received during accidents and emergencies.
(3) In complying with the requirements of paragraph (1) of this subdivision, a licensee or registrant may:
(i) accept, as a record of the occupational dose that the individual received during the current year, a written signed statement from the individual, or from the individual's most recent employer for work involving radiation exposure, that discloses the nature and the amount of any occupational dose that the individual received during the current year;
(ii) accept, as the record of lifetime cumulative radiation dose, a completed and up-to- date department form for cumulative occupational radiation exposure history, or equivalent, signed by the individual and countersigned by an appropriate official of the most recent employer for work involving radiation exposure, or the individual' s current employer, if the individual is not employed by the licensee or registrant; and
(iii) obtain reports of the individual's dose equivalent from the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant, by telephone, telegram, facsimile, or letter. The licensee or registrant shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established.
(4) The licensee or registrant shall record the exposure history, required by paragraph (1) of this subdivision, on the department form for cumulative occupational radiation exposure history, or other clear and legible record and shall include all the information required on that form.
(i) The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure. For each period for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing the form or record. For any period for which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on the form or record indicating the periods of time for which data are not available.
(ii) Licensees or registrants are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents, or intakes of radionuclides, which were assessed under the regulations in effect before the effective date of these regulations. Occupational exposure histories obtained and recorded on the department form for cumulative occupational radiation exposure history before the effective date of these regulations would not have included effective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.
(5) If the licensee or registrant is unable to obtain complete records of an individual's current and previously accumulated occupational dose, the licensee or registrant shall:
(i) when establishing administrative controls under paragraph (a)(6) of this section for the current year, assume that the allowable dose limit for the individual is reduced by 12.5 mSv (1.25 rem) for each quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposure; and
(ii) not authorize the individual to receive any planned special exposures.
(6) The licensee or registrant shall retain the records on the department form for cumulative occupational radiation exposure history or equivalent, until the commissioner terminates each pertinent license or registration. The licensee or registrant shall retain records used in preparing this form or equivalent for three years after the record is made.
(f) Planned special exposures.
A licensee or registrant may authorize an adult worker to receive doses which are in addition to, and which are accounted for separately from, the doses received under the limits specified in subdivision (a) of this section provided that each of the following conditions is satisfied:
(1) The licensee or registrant authorizes the planned special exposure only in an exceptional situation when alternatives that might avoid the higher exposure are unavailable or impractical.
(2) The licensee or registrant, and the employer if the employer is not the licensee or registrant, specifically authorizes the planned special exposure, in writing, before the exposure occurs.
(3) Before a planned special exposure, the licensee or registrant ensures that each worker involved is:
(i) informed of the purpose of the planned operation;
(ii) informed of the estimated doses and associated potential risks and specific radiation levels or other conditions that might be involved in performing the task; and
(iii) instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present.
(4) Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant ascertains prior doses as required by paragraph (e)(2) of this section.
(5) Subject to paragraph (a)(2) of this section, the licensee or registrant shall not authorize a planned special exposure that would cause an individual to receive a dose from all planned special exposures that would exceed:
(i) the numerical values of any of the dose limits in paragraph (a)(1) of this section in any year; and
(ii) five times the annual dose limits in paragraph (a)(1) of this section during the individual's lifetime.
(6) The licensee or registrant maintains records of the conduct of a planned special exposure in accordance with section 38.28(e) of this Part and submits a written report in accordance with section 38.29(d).
(7) The licensee or registrant records the best estimate of the dose resulting from the planned special exposure in the individual's record and informs the individual, in writing, of the dose within 30 days from the date of the planned special exposure. The dose from planned special exposures shall not be considered in controlling future occupational dose of the individual pursuant to paragraph (a)(1) of this section but shall be included in evaluations required by paragraphs (4) and (5) of this subdivision.
(g) Occupational dose limits for minors.
The annual occupational dose limits for minors are 10 percent of the annual occupational dose limits specified for adult workers in subdivision (a) of this section.
(h) Dose to an embryo/fetus.
(1) The licensee or registrant shall ensure that the dose to an embryo/fetus during the entire pregnancy, which results from occupational exposure of a declared pregnant woman, does not exceed 5 mSv (0.5 rem). (See section 38.28[f]of this Part for recordkeeping requirements.)
(2) The licensee or registrant shall review past exposure history and adjust working conditions so as to avoid a monthly total effective dose equivalent of more than 50 mrem to the embryo/fetus of a declared pregnant woman.
(3) The dose to an embryo/fetus shall be taken as the sum of:
(i) the deep dose equivalent to the declared pregnant woman during the entire pregnancy period; and
(ii) the dose to the embryo/fetus from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman during the entire pregnancy period.
(4) If by the time the woman declares pregnancy to the licensee or registrant, the dose to the embryo/fetus exceeded 4.5 mSv (0.45 rem), the licensee or registrant shall be deemed to be in compliance with paragraph (1) of this subdivision if the additional dose to the embryo/fetus does not exceed 0.50 mSv (0.05 rem) during the remainder of the pregnancy.
12 CRR-NY 38.18
Current through March 15, 2022
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