Current through all regulations passed and filed through March 18, 2024
(A) Except in the case of a planned special
exposure pursuant to paragraph (F) of this rule, a licensee or registrant shall
limit the occupational dose received by an individual adult, as follows:
(1) An annual limit, which is the more
limiting of:
(a) The total effective dose
equivalent being equal to 0.05 sievert (five 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 being equal to 0.5 sievert (fifty rem).
(2) The annual limits to the lens of the eye,
to the skin of the whole body, and to the skin of the extremities, which are:
(a) A lens dose equivalent of 0.15 sievert
(fifteen rem), and
(b) A
shallow-dose equivalent of 0.5 sievert (fifty rem) to the skin of the whole
body or to the skin of any extremity.
(3) Doses received in excess of the annual
limits, including doses received during accidents, emergencies, and planned
special exposures, shall be subtracted from the limits for planned special
exposures that the individual may receive during the current calendar year and
during the individual's lifetime in accordance with paragraph (F)(5) of this
rule.
(4) When the external
exposure is determined by measurement with an external personal monitoring
device, the deep-dose equivalent must be used in place of the effective dose
equivalent, unless the effective dose equivalent is determined by a dosimetry
method approved by the director. The assigned deep-dose equivalent must be for
the part of the body receiving the highest exposure.
(a) The assigned shallow-dose equivalent must
be the dose averaged over the contiguous ten square centimeters of skin
receiving the highest exposure. The deep-dose equivalent, lens-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, if the individual monitoring device was not in the region of
highest potential exposure, or the results of individual monitoring are
unavailable; or
(b) When a
protective apron is worn while working with radiation-generating equipment and
monitoring is conducted as specified in paragraph (C)(1) of rule
3701:1-38-14
of the Administrative Code, the effective dose equivalent for external
radiation shall be determined as follows:
(i)
When only one individual monitoring device is used and it is located at the
neck outside the protective apron, the reported deep dose equivalent value
multiplied by 0.3 shall be the effective dose equivalent for external
radiation; or
(ii) When two
individual monitoring devices are worn, one under the protective apron at the
waist and the other outside the protective apron at the neck, the effective
dose equivalent for external radiation shall be assigned the value of the sum
of the deep dose equivalent reported for the individual monitoring device
located at the waist under the protective apron multiplied by 1.5 and the deep
dose equivalent reported for the individual monitoring device located at the
neck outside the protective apron multiplied by 0.04; or
(iii) Through the use of computational
methods endorsed by the "American National Standards Institute", recommended by
the "National Council on Radiation Protection and Measurements", or approved by
the director.
(5) Derived air concentration (DAC) and
annual limit on intake (ALI) values are specified in appendix C to this rule
and may be used by the licensee to determine the individual's dose and to
demonstrate compliance with the occupational dose limits. Appendices A and B
are explanatory supplements to appendix C to this rule. Notwithstanding the
annual dose limits, the licensee shall limit the soluble uranium intake by an
individual to ten milligrams in a week in consideration of chemical toxicity.
(6) In accordance with paragraph
(E) of this rule, 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.
(B) Compliance with requirements
for summation of external and internal doses shall be in accordance with the
following:
(1) If the licensee is required to
monitor under both paragraphs (B)(1) and (B)(2) of rule
3701:1-38-14
of the Administrative Code, the licensee shall demonstrate compliance with the
dose limits by summing external and internal doses. If the licensee is required
to monitor only under paragraph (B)(1) or only under paragraph (B)(2) of rule
3701:1-38-14
of the Administrative Code, then summation is not required to demonstrate
compliance with the dose limits. The licensee may demonstrate compliance with
the requirements for summation of external and internal doses by meeting one of
the conditions specified in paragraph (B)(2) of this rule and the conditions in
paragraphs (B)(3) and (B)(4) of this rule. 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.
(2) 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, plus one of the following does not exceed unity:
(a) The sum of the fractions of the
inhalation ALI for each radionuclide; or
(b) The total number of derived air
concentration-hours, or DAC-hours, for all radionuclides divided by two
thousand; or
(c) 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 ten per cent of
the maximum weighted value of HT,50 , that is,
WT H T,50, per unit intake for
any organ or tissue.
(3) If the occupationally exposed individual
also receives an intake of radionuclides by oral ingestion greater than ten
percent of the applicable oral ALI, the licensee shall account for this intake
and include it in demonstrating compliance with the limits set forth in
paragraph (A) of this rule.
(4)
The licensee 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
further evaluated or accounted for pursuant to this paragraph.
(C) Determination of external dose
from airborne radioactive material shall be in accordance with the following:
(1) When determining the dose from airborne
radioactive material, the licensee shall include the contribution to the deep
dose equivalent, lens dose equivalent, and shallow dose equivalent from
external exposure to the radioactive cloud as specified in appendix C to this
rule, footnotes
A and
B.
(2) The licensee should not use airborne
radioactivity measurements or DAC values 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 should be based upon measurements using instruments
or individual monitoring devices.
(D) Determination of internal exposure shall
be in accordance with the following:
(1) For
purposes of assessing dose used to determine compliance with occupational dose
equivalent limits, the licensee shall, when required under paragraph (B) of
rule
3701:1-38-14
of the Administrative Code, take suitable and timely measurements of:
(a) Concentrations of radioactive materials
in air in work areas; or
(b)
Quantities of radionuclides in the body; or
(c) Quantities of radionuclides excreted from
the body; or
(d) Combinations of
these measurements.
(2)
Unless respiratory protective equipment is used, as provided in paragraph (C)
of rule
3701:1-38-16
of the Administrative Code or the assessment of intake is based on bioassays,
the licensee 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 may:
(a) Use that information to calculate the
committed effective dose equivalent, and, if used, the licensee shall document
that information in the individual's record; and
(b) 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; and
(c)
Separately assess the contribution of fractional intakes of Class D, W, or Y
compounds of a given radionuclide to the committed effective dose equivalent as
specified in appendix A to this rule.
(4) If the licensee chooses to assess intakes
of Class Y material using the measurements given in paragraph (D)(1)(b) or
(D)(1)(c) of this rule in order to make additional measurements basic to the
assessments, the licensee may delay the recording and reporting of the
assessments for periods up to seven months, unless otherwise required by
paragraph (B)(2) or (C) of rule
3701:1-38-21 of the
Administrative Code.
(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:
(a) The sum of the ratios of
the concentration to the appropriate DAC value, that is, D, W, or Y, from
appendix C to this rule for each radionuclide in the mixture; or
(b) 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 by 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 all of
the following occur:
(a) The licensee uses
the total activity of the mixture in demonstrating compliance with the dose
limits in paragraph (A) of this rule and in complying with the monitoring
requirements in paragraph (B) of rule
3701:1-38-14
of the Administrative Code;
(b)
The concentration of any radionuclide disregarded is less than ten percent of
its DAC; and
(c) The sum of these
percentages for all of the radionuclides disregarded in the mixture does not
exceed thirty percent.
(8) When determining the committed effective
dose equivalent, the licensee may consider the following:
(a) In order to calculate the committed
effective dose equivalent, the licensee may assume that the inhalation of one
ALI, or an exposure of two thousand DAC-hours, results in a committed effective
dose equivalent of 0.05 sievert (five rem), for radionuclides that have their
ALIs or DACs based on the committed effective dose equivalent; or
(b) For an ALI and the associated DAC
determined by the nonstochastic organ dose limit of 0.5 sievert (fifty rem),
the intake of radionuclides that would result in a committed effective dose
equivalent of 0.05 sievert (five rem), that is, the stochastic ALI, is listed
in parentheses in table I of appendix C to this rule. The licensee may, as a
simplifying assumption, use the stochastic ALI to determine committed effective
dose equivalent. However, if the licensee uses the stochastic ALI, the licensee
shall also demonstrate that the limit in paragraph (A)(1)(b) of this rule is
met.
(E)
Determination of prior occupational dose shall be made in accordance with the
following:
(1) For each individual who is
likely to receive an annual occupational dose requiring monitoring pursuant to
paragraph (B) of rule
3701:1-38-14
of the Administrative Code, the licensee or registrant shall determine the
occupational radiation dose received during the current year.
(2) Prior to permitting an individual to
participate in a planned special exposure, the licensee shall determine:
(a) The internal and external doses from all
previous planned special exposures; and
(b) All doses in excess of the limits,
including doses received during accidents and emergencies, received during the
lifetime of the individual.
(3) In complying with the requirements of
paragraph (E)(1) or (E)(2) of this rule, a licensee or registrant may:
(a) Accept, as a record of the occupational
dose that the individual received during the current year, a written signed
statements 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 may have received during the
current year;
(b) Accept, as the
record of lifetime cumulative radiation dose, a current department form
entitled "lifetime occupational 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
(c) 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,
e-mail 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, as required by paragraph (A) of this rule, on a form
provided by the department or other clear and legible record, of all the
information required on that form. 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 exposure
history form. For any period in which the licensee or registrant does not
obtain a report, the licensee or registrant shall place a notation on the
exposure history form indicating the periods of time for which data are not
available.
(5) If the licensee or
registrant is unable to obtain a complete record of an individual's current and
previously accumulated occupational dose, the licensee or registrant shall
assume:
(a) In establishing administrative
controls pursuant to paragraph (A)(6) of this rule for the current year, that
the allowable dose limit for the individual is reduced by 12.5 millisievert (
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
(b) That
the individual is not available for planned special exposures.
(6) The licensee or registrant
shall retain the records on the exposure history form until the department
terminates each pertinent license or registration requiring this record. The
licensee or registrant shall retain records used in preparing the exposure
history form for three years after the record is made.
(F) A planned special exposure may be
authorized by a licensee in accordance with this paragraph. A licensee may
authorize an adult worker to receive doses in addition to and accounted for
separately from the doses received under the limits specified in paragraph (A)
of this rule provided that each of the following is satisfied:
(1) The licensee authorizes a planned special
exposure only in an exceptional situation when alternatives that might avoid
the higher exposure are unavailable or impractical;
(2) The licensee and employer, if the
employer is not the licensee, specifically authorizes the planned special
exposure, in writing, before the exposure occurs;
(3) Before a planned special exposure, the
licensee ensures that each individual involved is:
(a) Informed of the purpose of the planned
operation; and
(b) 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
(c) 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
ascertains prior doses as required by paragraph (E)(2) of this rule during the
lifetime of the individual for each individual involved;
(5) The licensee shall not authorize a
planned special exposure that would cause an individual to receive a dose from
all planned special exposures and all doses in excess of the limits to exceed:
(a) The numerical values of any of the dose
limits in paragraph (A) of this rule in any calendar year; and
(b) Five times the annual dose limits
specified in paragraph (A) of this rule during the individual's lifetime;
(6) The licensee
maintains records of the conduct of a planned special exposure in accordance
with paragraph (E) of rule
3701:1-38-20 of the
Administrative Code and submits a written report in accordance with paragraph
(D) of rule
3701:1-38-21 of the
Administrative Code;
(7) The
licensee 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 thirty 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 rule, but shall be included in evaluations required by
paragraphs (F)(4) and (F)(5) of this rule.
(G) Occupational dose limits for minors shall
be ten per cent of the annual occupational dose limits specified for adult
workers in paragraph (A) of this rule.
(H) Dose equivalent to an embryo or fetus
shall be in accordance with the following:
(1) The licensee or registrant shall ensure
that the dose equivalent to an embryo or fetus during the entire pregnancy, due
to occupational exposure of a declared pregnant woman, does not exceed five
millisievert ( 0.5 rem). Records shall be maintained in accordance with
paragraph (I) of rule
3701:1-38-20 of the
Administrative Code.
(2) The
licensee or registrant shall make efforts to avoid substantial variation above
a uniform monthly exposure rate to a declared pregnant woman so as to satisfy
the limit in paragraph (H)(1) of this rule.
(3) The dose equivalent to the embryo or
fetus is the sum of:
(a) The deep-dose
equivalent to the declared pregnant woman; and
(b) The dose equivalent to the embryo or
fetus resulting from radionuclides in the embryo or fetus and from
radionuclides in the declared pregnant woman.
(4) If the declared pregnant woman's exposure
includes exposure from radiation generating equipment and a protective apron is
worn, the dose equivalent to an embryo or fetus shall be taken as the sum of:
(a) The dose equivalent to the embryo or
fetus from radionuclides in the embryo or fetus and radionuclides in the
declared pregnant woman; and
(b)
The dose equivalent that is most representative of the dose to the embryo or
fetus from external radiation, that is, in the mother's lower torso region.
(i) If multiple measurements have not been
made, assignment of the highest deep dose equivalent for the declared pregnant
woman shall be the dose to the embryo or fetus, in accordance with paragraph
(A)(4) of this rule; or
(ii) If
multiple measurements have been made, assignment of the deep dose equivalent
for the declared pregnant woman from the individual monitoring device which is
most representative of the dose to the embryo or fetus shall be the dose to the
embryo or fetus. Assignment of the highest deep dose equivalent for the
declared pregnant woman to the embryo or fetus is not required unless that dose
is also the most representative deep dose equivalent for the region of the
embryo or fetus.
(5) If by the time the woman declares
pregnancy to the licensee or registrant, the dose equivalent to the embryo or
fetus has exceeded five millisievert, or 0.5 rem, the licensee or registrant
shall be deemed to be in compliance with paragraph (A) of this rule, provided
that the additional dose equivalent to the embryo or fetus does not exceed 0.5
millisievert ( 0.05 rem), during the remainder of the pregnancy.
Click to
view Appendix
Click to
view Appendix
Click to
view Appendix
Five Year Review (FYR) Dates:
1/24/2022 and
01/20/2027
Promulgated
Under:
119.03
Statutory Authority:
3748.02,
3748.04
Rule Amplifies:
3748.04
Prior Effective Dates: 07/22/2001, 06/20/2003, 08/15/2005,
04/05/2009, 10/04/2010