AUTHORITY: Implementing and authorized by the Radiation Protection Act of 1990 [420 ILCS 40].
SOURCE: Filed April 24, 1970 by the Department of Public Health; transferred to the Department of Nuclear Safety by P.A. 81-1516, effective December 3, 1980; amended at 5 Ill. Reg. 9586, effective September 10, 1981; codified at 7 Ill. Reg. 16027; recodified at 10 Ill. Reg. 11273; amended at 10 Ill. Reg. 17538, effective September 25, 1986; amended at 16 Ill. Reg. 11538, effective July 7, 1992; old Part repealed, new Part adopted at 17 Ill. Reg. 18507, effective January 1, 1994; amended at 19 Ill. Reg. 8264, effective June 12, 1995; emergency amendment at 27, Ill. Reg. 17273, effective November 18, 2002, for a maximum of 150 days; amended at 27 Ill. Reg. 5445, effective March 17, 2003; recodified from the Department of Nuclear Safety to the Illinois Emergency Management Agency at 27 Ill. Reg. 13641; amended at 29 Ill. Reg. 20841, effective December 16, 2005; amended at 31 Ill. Reg. 11593, effective July 26, 2007; amended at 35 Ill. Reg. 934, effective December 30, 2010; amended at 39 Ill. Reg. 15728, effective November 24, 2015; amended at 45 Ill. Reg. 4895, effective April 1, 2021; amended at 47 Ill. Reg. 9163, effective June 22, 2023; Chapter II recodified at 49 Ill. Reg. 2239.
Section 340.10 Purpose
a) This Part establishes standards for protection against
ionizing radiation resulting from activities conducted pursuant to licenses or
registrations issued by the Illinois Emergency Management Agency (Agency).
This Part is issued pursuant to the Radiation Protection Act of 1990 [420 ILCS
40].
b) The requirements of this Part are designed to control the
receipt, possession, use, transfer, and disposal of sources of radiation by any
licensee or registrant so that the total dose to an individual, including doses
resulting from all sources of radiation other than background radiation, does
not exceed the standards for protection against radiation prescribed in this
Part. However, nothing in this Part shall be construed as limiting actions
that may be necessary to protect health and safety in an emergency.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.20 Scope
Except as specifically provided
in other regulations of the Agency, this Part applies to persons licensed or
registered by the Agency to receive, possess, use, transfer or dispose of
sources of radiation pursuant to 32 Ill. Adm. Code: Chapter II, Subchapters b
and d. The limits in this Part do not apply to doses due to background
radiation, to exposure of patients to radiation for the purpose of medical
diagnosis or therapy, to exposure from individuals administered radioactive
material and released under 32 Ill. Adm. Code 335 or to voluntary participation
in medical research programs.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.25
Incorporations by Reference
All rules, standards and
guidelines of agencies of the United States or nationally recognized
organizations or associations that are incorporated by reference in this Part
are incorporated as of the date specified in the reference and do not include
any later amendments or editions. Copies of rules, standards and guidelines
that have been incorporated by reference are available for public inspection and
copying at the Agency, 1035 Outer Park Drive, Springfield, Illinois.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.30 Definitions
"Air-purifying
respirator" or "APR" means a respirator with an air-purifying
filter, cartridge or canister that removes specific air contaminants by passing
ambient air through the air-purifying element.
"Annual limit on intake" or "ALI" means the derived
limit for the amount of radioactive material taken into the body of an adult
worker by inhalation or ingestion in a year. ALI is the smaller value of
intake of a given radionuclide in a year by the reference man that would result
in a committed effective dose equivalent of 0.05 Sv (5 rem) or a committed dose
equivalent of 0.5 Sv (50 rem) to any individual organ or tissue. ALI values
for intake by ingestion and by inhalation of selected radionuclides are given
in table 1, columns 1 and 2 of appendix B to 10 CFR 20, published at 72 Fed.
Reg. 55922, October 1, 2007, exclusive of subsequent amendments or editions.
"Assigned protection factor" or "APF" means the
expected workplace level of respiratory protection that would be provided by a
properly functioning respirator or a class of respirators to properly trained
and fitted users.
"Atmosphere-supplying respirator" means a respirator that
supplies the respirator user with breathing air from a source independent of
the ambient atmosphere, and includes supplied-air respirators (SARs) and
self-contained breathing apparatus (SCBA) units.
"Chelating agent"
means amine polycarboxylic acids (e.g., EDTA, DTPA), hydroxy-carboxylic acids,
and polycarboxylic acids (e.g., citric acid, carbolic acid, and glucinic acid).
"Class" (lung class or inhalation class) means a classification
scheme for inhaled material according to its rate of clearance from the
pulmonary region of the lung. Materials are classified as D, W or Y, which
applies to a range of clearance half-times: for Class D (Days) of less than 10
days, for Class W (Weeks) from 10 to 100 days, and for Class Y (Years) of
greater than 100 days.
"Collector" means a licensee whose principal purpose is to
collect and consolidate waste generated by others, and to transfer this waste,
without processing or repackaging the collected waste, to another licensed
waste collector, licensed waste processor or licensed land disposal facility.
"Consignee" means the designated receiver of a shipment of
low-level radioactive waste.
"Constraint" (dose constraint) means a value above which
specified licensee actions are required.
"Demand
respirator" means an atmosphere-supplying respirator that admits breathing
air to the face piece only when a negative pressure is created inside the face
piece by inhalation.
"Derived air concentration" or "DAC" means the
concentration of a given radionuclide in air, which, if breathed by the
reference man for a working year of 2,000 hours under conditions of light work
would result in an intake of one ALI. For purposes of this definition, the
condition of light work is an inhalation rate of 1.2 cubic meters of air per
hour for 2,000 hours in a year. DAC values are given in table 1, column 3 of appendix
B to 10 CFR 20, published at 72 Fed. Reg. 55922, October 1, 2007, exclusive of
subsequent amendments or editions.
"Derived air concentration-hour" or "DAC-hour" means
the product of the concentration of radioactive material in air (expressed as a
fraction or multiple of the derived air concentration for each radionuclide)
and the time of exposure to that radionuclide (expressed in hours). A licensee
may take 2,000 DAC-hours to represent one ALI, equivalent to a committed
effective dose equivalent of 0.05 Sv (5 rem).
"Disposal container" means a
container principally used to confine low-level radioactive waste during
disposal operations at a land disposal facility (also see "high integrity
container"). Note that, for some shipments, the disposal container may be
the transport package.
"Disposable respirator" means a respirator for which
maintenance is not intended and that is designed to be discarded after
excessive breathing resistance, sorbent exhaustion, physical damage, or
end-of-service-life renders it unsuitable for use. Examples of this type of
respirator are a disposable half-mask respirator or a disposable escape-only
self-contained breathing apparatus (SCBA).
"EPA identification number"
means the number received by a transporter following application to the
Administrator of USEPA as required by 40 CFR 263.
"Filtering face piece" or "dust mask" means a
negative pressure particulate respirator with a filter as an integral part of
the face piece or with the entire face piece composed of the filtering medium,
not equipped with elastomeric sealing surfaces and adjustable straps.
"Fit factor" means a quantitative estimate of the fit of a
particular respirator to a specific individual and typically estimates the
ratio of the concentration of a substance in ambient air to its concentration
inside the respirator when worn.
"Fit Test" means the use of a protocol to qualitatively or
quantitatively evaluate the fit of a respirator on an individual.
"Helmet"
means a rigid respiratory inlet covering that also provides head protection
against impact and penetration.
"Hood"
means a respiratory inlet covering that completely covers the head and neck and
may also cover portions of the shoulders and torso.
"Inhalation class" (see "class").
"Land disposal facility" means the land, buildings,
structures and equipment which are intended to be used for the disposal of
radioactive wastes.
"Lens dose equivalent" or "LDE" applies to the
external exposure of the lens of the eye and is taken as the dose equivalent at
a tissue depth of 0.3 centimeter (300 mg/cm2).
"Loose-fitting face piece" means a respiratory inlet covering
designed to form a partial seal with the face.
"Lung class" (see "class").
"Negative pressure respirator (tight fitting)" means a
respirator in which the air pressure inside the face piece is negative during
inhalation with respect to the ambient air pressure outside the respirator.
"Nonstochastic effect" (deterministic effect) means a health
effect, the severity of which varies with the dose and for which a threshold is
believed to exist. Radiation-induced cataract formation is an example of a
nonstochastic effect.
"Occupational dose" means the dose received by an individual in
the course of employment in which the individual's assigned duties involve
exposure to radiation or to radioactive material from licensed and unlicensed
sources of radiation, whether in the possession of the licensee or another
person. Occupational dose does not include doses received from background
radiation, from any medical administration the individual has received, from
exposure to individuals administered radioactive material and released under 32
Ill. Adm. Code 335, from voluntary participation in medical research programs
or as a member of the public.
"Physical description"
means the items called for on NRC Form 541 to describe a low-level radioactive
waste.
"Planned special exposure" means an infrequent exposure to
radiation, the dose from which is separate from and in addition to the annual
occupational dose limits.
"Positive pressure respirator" means a respirator in which
the pressure inside the respiratory inlet covering exceeds the ambient air
pressure outside the respirator.
"Powered air-purifying respirator" or "PAPR" means
an air-purifying respirator that uses a blower to force the ambient air through
air-purifying elements to the inlet covering.
"Pressure demand respirator" means a positive pressure
atmosphere-supplying respirator that admits breathing air to the face piece
when the positive pressure is reduced inside the face piece by inhalation.
"Public dose"
means the dose received by a member of the public from exposure to radiation or
to radioactive material released by a licensee or to any other source of radiation
under the control of a licensee. Public dose does not include occupational
dose or doses received from background radiation, from any medical
administration the individual has received, from exposure to individuals
administered radioactive material and released under 32 Ill. Adm. Code 335, or
from voluntary participation in medical research programs.
"Qualitative fit test" or "QLFT" means a pass/fail
fit test to assess the adequacy of respirator fit that relies on the individual's
response to the test agent.
"Quantitative fit test" or "QNFT" means an assessment
of the adequacy of respirator fit by numerically measuring the amount of
leakage into the respirator.
"Reference Man" means a hypothetical aggregation of human
physical and physiological characteristics determined by international
consensus. These characteristics may be used by researchers and public health
workers to standardize results of experiments and to relate biological insult
to a common base.
AGENCY NOTE: A description of the Reference Man is contained in the
International Commission on Radiological Protection report, ICRP Publication
23, "Report of the Task Group on Reference Man."
"Respiratory protective equipment" means an apparatus, such as
a respirator, used to reduce an individual's intake of airborne radioactive
materials.
"Sanitary sewerage" means a system of public sewers for
carrying off waste water and refuse, but excluding sewage treatment facilities,
septic tanks, and leach fields owned or operated by the licensee.
"Self-contained breathing apparatus" or "SCBA"
means an atmosphere-supplying respirator for which the breathing air source is
designed to be carried by the user.
"Shipping paper"
means NRC Form 540 and, if required, NRC Form 540A, which includes the
information required by DOT in 49 CFR 172, revised October 1, 2008, exclusive
of subsequent amendments or editions.
"Stochastic effect" (probabilistic effect) means a health
effect that occurs randomly and for which the probability of the effect
occurring, rather than its severity, is assumed to be a linear function of dose
without threshold. Hereditary effects and cancer incidence are examples of
stochastic effects.
"Supplied-air respirator" or "SAR" or "airline
respirator" means an atmosphere-supplying respirator for which the source
of breathing air is not designed to be carried by the user.
"Tight-fitting face piece" means a respiratory inlet covering
that forms a complete seal with the face.
"Uniform Low-Level Radioactive Waste Manifest"
or "uniform manifest"
means the combination of NRC Forms 540, 541 and, if necessary, 542, and their
respective continuation sheets as needed, or equivalent.
"User seal check" or "fit check" means an action
conducted by the respirator user to determine if the respirator is properly
seated to the face. Examples include negative pressure check, positive
pressure check, irritant smoke check, or isoamyl acetate check.
"Waste description" means the
physical, chemical and radiological description of a low-level radioactive
waste as called for on NRC Form 541.
"Waste processor"
means an entity, operating under an Agency, Nuclear Regulatory Commission or
Agreement State license, whose principal purpose is to process, repackage, or
otherwise treat low-level radioactive material or waste generated by others
prior to eventual transfer of waste to a licensed low-level radioactive waste
land disposal facility.
"Waste type" means a waste
within a disposal container having a unique physical description (i.e., a
specific waste descriptor code or description or a waste sorbed on or
solidified in a specifically defined media).
"Weighting factor" (wT), means the proportion of the
risk of stochastic effects resulting from irradiation of an organ or tissue (T)
to the total risk of stochastic effects when the whole body is irradiated
uniformly. For calculating the effective dose equivalent, the values of (wT)
are:
|
Organ or Tissue
|
(wT)
|
|
|
|
|
Gonads
|
0.25
|
|
Breast
|
0.15
|
|
Red bone marrow
|
0.12
|
|
Lung
|
0.12
|
|
Thyroid
|
0.03
|
|
Bone surfaces
|
0.03
|
|
Remainder
|
0.30a
|
|
Whole Body
|
1.00b
|
a0.30 results from 0.06 for each of 5 "remainder"
organs, excluding the skin and the lens of the eye, that receive the highest
doses.
bFor the purpose of weighting the external whole-body dose,
for adding it to the internal dose, a single weighting factor, (wT)
= 1.0, has been specified.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.40
Implementation
Any existing license condition
that is more restrictive than this Part remains in force until there is an
amendment or renewal of the license.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.210 Occupational
Dose Limits for Adults
a) The licensee or registrant shall control the occupational dose
to individual adults, except for planned special exposures pursuant to Section
340.260, to the following dose limits:
1) An annual limit, which is the more limiting of:
A) The total effective dose equivalent being 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
being equal to 0.5 Sv (50 rem).
2) The annual limits to the lens of the eye, to the skin and to
the extremities which are:
A) A lens dose equivalent of 0.15 Sv (15 rem); and
B) A shallow dose equivalent of 0.5 Sv (50 rem) to the skin or to
any extremity.
b) 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 year and during the individual's lifetime (see
Section 340.260(e)).
c) When the external exposure is determined by measurement with
an external personal monitoring device, the deep dose equivalent shall be used
in place of the effective dose equivalent unless the effective dose equivalent
is determined by a dosimetry method approved by the Agency. The assigned deep
dose equivalent shall be for the portion of the body receiving the highest
exposure. The assigned shallow dose equivalent shall be the dose averaged over
the contiguous 10 square centimeters of skin receiving the highest dose.
AGENCY NOTE:
The deep dose equivalent, lens dose equivalent or 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.
d) 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.
e) Derived air concentration (DAC) and annual limit on intake
(ALI) values are specified in table 1 of appendix B to 10 CFR 20, published at
72 Fed. Reg. 55922, October 1, 2007, exclusive of subsequent amendments or
editions, and may be used to determine the individual's dose (see Section
340.1160) and to demonstrate compliance with the occupational dose limits.
f) Notwithstanding the annual dose limits, the licensee shall
limit the soluble uranium intake by an individual to 10 milligrams in a week in
consideration of chemical toxicity (see footnote 3 of appendix B to 10 CFR 20, published
at 72 Fed. Reg. 55922, October 1, 2007, exclusive of subsequent amendments or
editions.)
g) 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 during the
current year (see Section 340.250(a) and (d)).
AGENCY NOTE:
The purpose of this requirement is to ensure that no individual receives an annual
occupational dose in excess of the occupational dose limits set forth in this
Section.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.220 Compliance
with Requirements for Summation of External and Internal Doses
a) General Requirement. If the licensee is required to monitor
individual occupational dose pursuant to both Section 340.520(a) and (b) of
this Part, the licensee shall demonstrate compliance with the dose limits by
summing external and internal doses. If the licensee or registrant is required
to monitor individual occupational dose only pursuant to Section 340.520(a) of
this Part or only pursuant to Section 340.520(b) of this Part, 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 pursuant to subsections (b), (c) and (d) of this Section. 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.
b) 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:
1) The sum of the fractions of the inhalation ALI for each
radionuclide; or
2) The total number of derived air concentration-hours
(DAC-hours) for all radionuclides divided by 2,000; or
3) The sum of the calculated committed effective dose equivalents
to all significantly irradiated organs or tissues (T) calculated from bioassay
data using 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
factor (wT) and the committed dose equivalent, HT,50, per
unit intake is greater than ten percent of the maximum weighted value of HT,50
(i.e., wTHT,50) per unit intake for any organ or tissue.
c) Intake by Oral Ingestion. If the occupationally exposed
individual 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.
d) Intake Through Wounds or Absorption Through Skin. The
licensee shall evaluate and, to the extent practicable, 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 subsection.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.230
Determination of External Dose from Airborne Radioactive Material
a) Licensees shall, when determining the dose from airborne
radioactive material, include the contribution to the deep dose equivalent, lens
dose equivalent and shallow dose equivalent from external exposure to the
radioactive cloud (see footnotes 1 and 2 of appendix B to 10 CFR 20, published
at 72 Fed. Reg. 55922, October 1, 2007, exclusive of subsequent amendments or
editions).
b) 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 shall be based upon
measurements using instruments or individual monitoring devices.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.240
Determination of Internal Exposure
a) For purposes of assessing dose used to determine compliance
with occupational dose equivalent limits, the licensee shall, when required
pursuant to Section 340.520, take measurements of:
1) Concentrations of radioactive materials in air in work areas
during conditions of operations; or
2) Quantities of radionuclides in the body after exposure to
materials that could result in an intake; or
3) Quantities of radionuclides excreted from the body after
exposure to materials that could result in an intake; or
4) Combinations of these measurements.
b) Unless respiratory protective equipment is used, as provided
in Section 340.730, 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.
c) 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:
1) 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
2) Upon prior approval of the Agency, adjust the DAC or ALI
values to reflect the actual physical and chemical characteristics of airborne
radioactive material (e.g., aerosol size distribution or density); and
3) Separately assess the contribution of fractional intakes of
Class D, W or Y compounds of a given radionuclide (see appendix B to 10 CFR 20,
published at 72 Fed. Reg. 55922, October 1, 2007, exclusive of subsequent
amendments or editions) to the committed effective dose equivalent.
d) If the licensee chooses to assess intakes of Class Y material
using the measurements specified in subsections (a)(2) or (3), the licensee may
delay the recording and reporting of the assessments for periods up to 7
months, unless otherwise required by Sections 340.1220 or 340.1230.
AGENCY NOTE:
This delay permits the licensee to make additional measurements basic to the
assessments.
e) 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:
1) The sum of the ratios of the concentration to the appropriate
DAC value (e.g., D, W or Y) from appendix B to 10 CFR 20, published at 72 Fed.
Reg. 55922, October 1, 2007, exclusive of subsequent amendments or editions,
for each radionuclide in the mixture; or
2) The ratio of the total concentration for all radionuclides in
the mixture to the most restrictive DAC value for any radionuclide in the
mixture.
f) 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.
g) When a mixture of radionuclides in air exists, a licensee may
disregard certain radionuclides in the mixture if:
1) The licensee uses the total activity of the mixture in
demonstrating compliance with the dose limits in Section 340.210 and in
complying with the monitoring requirements in Section 340.520(b);
2) The concentration of any radionuclide disregarded is less than
10 percent of its DAC; and
3) The sum of these percentages for all of the radionuclides
disregarded in the mixture does not exceed 30 percent.
h) When determining the committed effective dose equivalent, the
following information may be considered:
1) In order to calculate the committed effective dose equivalent,
the licensee 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.
2) For an ALI (and the associated DAC) determined by the
nonstochastic organ dose limit of 0.5 Sv (50 rem), the intake of radionuclides
that would result in a committed effective dose equivalent of 0.05 Sv (5 rem)
(the stochastic ALI) is listed in parentheses in table 1 of appendix B to 10
CFR 20, published at 72 Fed. Reg. 55922, October 1, 2007, exclusive of
subsequent amendments or editions. 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 Section 340.210(a)(1)(B) is met.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.250
Determination of Prior Occupational Dose
a) 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 340.520 of this Part,
the licensee or registrant shall determine the occupational radiation dose
received during the current year prior to allowing such individual to enter a
restricted area. In order to comply with this requirement, a licensee or
registrant may 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 employers 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. To accomplish this, a licensee or registrant may use the NRC Form 5 or
submit equivalent information.
AGENCY NOTE:
Licensees and registrants also should attempt to obtain the records of
cumulative occupational radiation dose.
b) Prior to permitting an individual to participate in a planned
special exposure, the licensee shall:
1) Determine the cumulative occupational radiation dose.
A) In order to comply with this requirement, a licensee may
accept, as the record of cumulative radiation dose, an up-to-date NRC Form 4,
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 employers (if the individual is not employed by the
licensee); and
B) Obtain reports of the individual's dose equivalent for the time
period subsequent to that included in NRC Form 4, or equivalent, as specified
in subsection (b)(1)(A) of this Section. Such reports shall be signed by the
individual and countersigned by an appropriate official of the most recent employers
for work involving radiation exposure, or the individual's current employers
(if the individual is not employed by the licensee). The information shall be
recorded on NRC Form 5, or equivalent.
2) Determine the internal and external doses from all previous
planned special exposures.
3) Determine all doses in excess of the limits received during
the lifetime of the individual, including doses received during accidents and
emergencies.
c) The licensee or registrant shall record the exposure history,
as required by subsections (a) and (b) of this Section, on NRC Form 4 or 5, or
equivalent, as applicable, or other clear and legible record containing all of
the information required on that form.
1) The form or record shall show each period in which the
individual received occupational exposure to sources of radiation 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. 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
indicating the periods of time for which data are not available.
2) For the purpose of complying with this requirement, licensees
or registrants are not required to reevaluate the separate external dose
equivalents and internal committed dose equivalents or intakes of radionuclides
assessed before January 1, 1994. Further, although occupational exposure
histories obtained and recorded before January 1, 1994, would not have included
effective dose equivalent, such histories may be used in the absence of
specific information on the intake of radionuclides by the individual.
d) 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:
1) When establishing administrative controls pursuant to Section
340.210(g) of this Part for the current year, shall assume that the allowable
dose limit for the individual is reduced by 12.5 mSv (1.25 rem) for each
calendar quarter for which records were unavailable and the individual was
engaged in activities that could have resulted in occupational radiation
exposure; and
2) Shall not authorize the individual to receive any planned
special exposures.
e) Records shall be retained in accordance with the requirements
of Section 340.1140(a) of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.260 Planned
Special Exposures
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 Section 340.210 of this
Part, provided that each of the following conditions are satisfied:
a) The licensee authorizes a planned special exposure only in an
exceptional situation when alternatives that might avoid the dose estimated to
result from the planned special exposure are unavailable or impractical.
b) The management official of the licensee and employer, if the
employer is not the licensee, specifically authorize the planned special
exposure, in writing, before the exposure occurs.
c) Before a planned special exposure, the licensee ensures that
each individual involved is:
1) Informed of the purpose of the planned operation; and
2) 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
3) Instructed in the measures to be taken to keep the dose ALARA
considering other risks that may be present.
d) Prior to permitting an individual to participate in a planned
special exposure, the licensee ascertains previous doses received during the
lifetime of the individual as required by Section 340.250(b) of this Part.
e) Subject to Section 340.210(b) of this Part, the licensee shall
not authorize a planned special exposure that would cause an individual's dose
from all planned special exposures and all doses in excess of the limits to exceed:
1) The numerical values of any of the dose limits in Section
340.210(a) of this Part in any year; and
2) Five times the annual dose limits in Section 340.210(a) of
this Part during the individual's lifetime.
f) The licensee maintains records of the conduct of a planned
special exposure in accordance with Section 340.1150 of this Part and submits a
written report in accordance with Section 340.1240 of this Part.
g) 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 30 days from the date of the planned
special exposure. The dose from planned special exposure need not be
considered in controlling future occupational dose of the individual pursuant
to Section 340.210(a) of this Part but shall be included in evaluations
required by subsections (d) and (e) of this Section.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.270 Occupational
Dose Limits for Minors
The annual occupational dose
limits for minors are ten percent of the annual occupational dose limits
specified for adult workers in Section 340.210 of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.280 Dose Equivalent
to an Embryo/Fetus
a) Except as otherwise provided in subsections (d) and (e) of
this Section, the licensee or registrant shall ensure that the dose equivalent to
an embryo/fetus during the entire pregnancy, due to occupational exposure of a
declared pregnant woman, does not exceed 5 mSv (0.5 rem). (For recordkeeping
requirements, see Section 340.1160(d) of this Part.)
b) The dose equivalent to an embryo/fetus shall be taken as the
sum of:
1) The deep dose equivalent to the declared pregnant woman during
the entire pregnancy; and
2) The dose equivalent to the embryo/fetus from radionuclides in
the embryo/fetus and radionuclides in the declared pregnant woman during the
entire pregnancy.
c) 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 subsection (a) of this Section.
AGENCY NOTE:
The National Council on Radiation Protection and Measurements report entitled
"Recommendations on Limits for Exposure to Ionizing Radiation", NCRP
91, published June 1, 1987, recommends that no more than 0.5 mSv (0.05 rem) of
the allowed dose to the embryo/fetus be received during any one month during a
declared pregnancy.
d) If the declared pregnant woman has not notified the licensee
or registrant of the estimated date of conception, the licensee or registrant
shall ensure that the dose equivalent to an embryo/fetus, as specified in
subsection (b) of this Section, due to occupational exposure of the declared
pregnant woman does not exceed 0.5 mSv (0.05 rem) per month, during the
remainder of the pregnancy. If after initially declaring her pregnancy, a
declared pregnant woman advises the licensee or registrant of the estimated
date of conception, the dose limits specified in subsections (a) and (e) of
this Section shall apply.
AGENCY NOTE:
The Agency encourages licensees and registrants to explain to declared pregnant
workers that providing an estimated date of conception will enable the licensee
or registrant to more accurately assess the radiation dose equivalent to the
embryo/fetus and assist the licensee or registrant in determining appropriate
precautions to be taken for the remainder of the pregnancy.
e) If by the time the woman informs the licensee or registrant of
the estimated date of conception the dose equivalent to the embryo/fetus has
exceeded 4.5 mSv (0.45 rem), the licensee or registrant shall be deemed to be
in compliance with subsection (a) of this Section if the additional dose equivalent
to the embryo/fetus as specified in subsection (b) of this Section does not
exceed 0.5 mSv (0.05 rem) during the remainder of the pregnancy.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.510 General
a) Each licensee or registrant shall make, or cause to be made,
surveys, including surveys of the subsurface, where appropriate:
1) That demonstrate compliance with this Part; and
2) That evaluate:
A) The extent of radiation levels;
B) Concentrations or quantities of radioactive material; and
C) The potential radiological hazards of radiation levels and
residual radioactivity detected.
b) The licensee or registrant shall ensure that instruments and
equipment used for quantitative radiation measurements (e.g., dose rate and
effluent monitoring) are calibrated at intervals not to exceed 12 months for
the radiation measured or at alternative intervals specified in regulations of
the Agency, the U.S. Nuclear Regulatory Commission, an Agreement State or a
Licensing State. To satisfy this requirement, the licensee shall:
1) Post a legible note on the instrument showing the date of
calibration; and
2) Ensure that instrument calibrations are performed by persons
specifically licensed by the Agency, the U.S. Nuclear Regulatory Commission, an
Agreement State or a Licensing State to perform such calibrations.
c) On each day of use, prior to using an instrument to perform
required monitoring, the licensee or registrant shall verify that the
instrument is operational. Operational checks for radiation measurement or
radiation detection instruments shall include verification of response to a
source of radiation.
d) Except for those dosimeters used to measure the dose to any
extremity, personnel dosimeters that require processing to determine the
radiation dose and that are used by licensees or registrants to comply with
Section 340.210, with other applicable provisions of 32 Ill. Adm. Code: Chapter
II, Subchapters b and d or with conditions specified in a license shall be
processed and evaluated by a qualified dosimetry processor. A dosimetry
processor is qualified if:
1) It holds current personnel dosimetry accreditation from the
National Voluntary Laboratory Accreditation Program (NVLAP) of the National
Institute of Standards and Technology; and
2) It is approved by NVLAP for the type of radiation or
radiations that most closely approximate the type of radiation or radiations
for which the individual wearing the dosimeter is monitored.
e) A licensee or registrant shall obtain Agency approval prior to
using pocket ionization chambers or electronic dosimeters to determine
radiation dose, to comply with Section 340.210, or with other applicable
provisions of 32 Ill. Adm. Code: Chapter II, Subchapters b and d or with
conditions specified in a license. The Agency will grant approval provided the
licensee or registrant submits information describing the type and range of the
dosimeters and describes a program to ensure the accuracy, reliability,
precision and security of the dosimetry data.
f) The licensee or registrant shall ensure that adequate
precautions are taken to prevent deceptive exposure of an individual monitoring
device.
(Source: Amended at 39 Ill.
Reg. 15728, effective Novermber 24, 2015)
Section 340.520 Conditions
Requiring Individual Monitoring of External and Internal Occupational Dose
Each licensee or registrant
shall monitor doses from sources of radiation at levels sufficient to
demonstrate compliance with the occupational dose limits of this Part. As a
minimum:
a) Each licensee or registrant shall monitor occupational dose
from sources of radiation and shall supply and require the use of individual
monitoring devices by:
1) Adults likely to receive, in 1 year from sources external to
the body, a dose in excess of 10 percent of the limits in Section 340.210(a);
2) Minors likely to receive, in 1 year from sources external to
the body, a dose in excess of 10 percent of any of the applicable limits in Section
340.270;
3) Declared pregnant women likely to receive during the entire
pregnancy, from radiation sources external to the body, a deep dose equivalent
in excess of 1 mSv (0.1 rem); and
4) Individuals entering a high or very high radiation area.
b) Each licensee shall monitor, to determine compliance with
Section 340.240, the occupational intake of radioactive material by and assess
the committed effective dose equivalent to:
1) Adults likely to receive, in 1 year, an intake in excess of 10
percent of the applicable ALIs in table 1, columns 1 and 2 of appendix B to 10
CFR 20, published at 72 Fed. Reg. 55922, October 1, 2007, exclusive of
subsequent amendments or editions; and
2) Minors and declared pregnant women likely to receive, in 1
year, a committed effective dose equivalent in excess of 0.5 mSv (0.05 rem).
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.530 Location of
Individual Monitoring Devices
Each licensee or registrant
shall ensure that individuals who are required to monitor occupational doses in
accordance with Section 340.520(a) of this Part wear individual monitoring
devices as follows:
a) An individual monitoring device used for monitoring the dose
to the whole body shall be worn at the unshielded location of the whole body
likely to receive the highest exposure. When a protective apron is worn, the
location of the individual monitoring device is typically at the neck (collar).
b) An individual monitoring device used for monitoring the dose
to an embryo/fetus of a declared pregnant woman, pursuant to Section 340.280(a)
of this Part, shall be located at the waist under any protective apron being
worn by the woman.
c) An individual monitoring device used for monitoring the eye
dose equivalent, to demonstrate compliance with Section 340.210(a)(2)(A) of
this Part, shall be located at the neck (collar), outside any protective apron
being worn by the monitored individual, or at an unshielded location closer to
the eye.
d) An individual monitoring device used for monitoring the dose
to the extremities, to demonstrate compliance with Section 340.210(a)(2)(B) of
this Part, shall be worn on the extremity likely to receive the highest
exposure. Each individual monitoring device shall be oriented to measure the
highest dose to the extremity being monitored.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.540 Calibration
of Survey Instruments
a) Unless specified in another Part, a licensee shall have each
survey instrument used to show compliance with this Part calibrated before
first use, annually and following a repair that affects the calibration. A
licensee shall:
1) Calibrate all scales with readings up to 10 mSv (1000 mrem)
per hour with a radiation source;
2) Calibrate two separated readings on each scale or decade that
will be used to show compliance; and
3) Conspicuously note on the instrument the date of calibration.
b) A licensee may not use survey instruments if the difference
between the indicated exposure rate and the calculated exposure rate is more
than 20 percent.
(Source: Added at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.610 Control of
Access to High Radiation Areas
a) The licensee shall ensure that each entrance or access point
to a high radiation area has one or more of the following features:
1) A control device that, upon entry into the area, causes the
level of radiation to be reduced below that level at which an individual might
receive a deep dose equivalent of 1 mSv (0.1 rem) in 1 hour at 30 centimeters
from the source of radiation or from any surface that the radiation penetrates;
or
2) A control device that energizes a conspicuous visible or
audible alarm signal so that the individual entering the high radiation area
and the supervisor of the activity are made aware of the entry; or
3) Entryways that are locked, except during periods when access
to the areas is required, with positive control over each individual entry.
b) In place of the controls required by subsection (a) of this
Section for a high radiation area, the licensee may substitute continuous
direct or electronic surveillance to enable action to be taken to prevent
unauthorized entry.
c) The licensee may apply to the Agency for approval of
alternative methods for controlling access to high radiation areas.
d) The licensee shall establish the controls required by
subsections (a) and (c) of this Section in a way that does not prevent
individuals from leaving a high radiation area.
e) The licensee is not required to control each entrance or
access point to a room or other area that is a high radiation area solely
because of the presence of radioactive materials prepared for transport and
packaged and labeled in accordance with the regulations of the U.S. Department
of Transportation provided that:
1) The packages do not remain in the area longer than 3 days; and
2) The dose rate at 1 meter from the external surface of any
package does not exceed 0.1 mSv (0.01 rem) per hour.
f) The licensee is not required to control entrance or access to
rooms or other areas in hospitals solely because of the presence of patients containing
radioactive material, provided that there are personnel in attendance who are
taking the necessary precautions, as required by 32 Ill. Adm. Code 335, to
prevent the exposure of individuals to radiation or radioactive material in
excess of the limits established in this Part and to operate within the ALARA
provisions of the licensee's radiation protection program.
g) The registrant shall control entrance or access to rooms or
other areas containing sources of radiation capable of producing a high
radiation area as described in this Section in accordance with the requirements
for access and control specified in other applicable Parts of 32 Ill. Adm.
Code: Chapter II, Subchapters b and d (i.e., 32 Ill. Adm. Code 350 for
industrial radiography, 32 Ill. Adm. Code 360 for use of x-rays in the healing
arts and 32 Ill. Adm. Code 390 for particle accelerators).
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.620 Control of
Access to Very High Radiation Areas
In addition to the controls
required by Section 340.610 of this Section, the licensee or registrant shall
institute measures to ensure that an individual is not able to gain
unauthorized or inadvertent access to areas in which radiation levels could be
encountered at 5 Gy (500 rad) or more in 1 hour at 1 meter from a source of
radiation or any surface through which the radiation penetrates.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.630 Control of
Access to Very High Radiation Areas – Irradiators
a) This Section applies to licensees or registrants with sources
of radiation in irradiators that are not self-shielded. This Section does not
apply to sources of radiation that are used in teletherapy, in industrial
radiography or in completely self-shielded irradiators in which the source is
both stored and operated within the same radiation shielding barrier and, in
the designed configuration of the irradiator, is always physically inaccessible
to any individual and cannot create a radiation level of 5 Gy (500 rad) or more
in 1 hour at 1 meter in an area that is accessible to any individual.
b) Each area in which there may exist radiation levels in excess
of 5 Gy (500 rad) in 1 hour at 1 meter from a source of radiation that is used
to irradiate matter shall meet the following requirements:
1) Each entrance or access point shall be equipped with entry
control devices that:
A) Function automatically to prevent any individual from
inadvertently entering a very high radiation area;
B) Permit deliberate entry into the area only after a control
device is actuated that causes the radiation level within the area, from the
source of radiation, to be reduced below that at which it would be possible for
an individual to receive a deep dose equivalent in excess of 1 mSv (0.1 rem) in
1 hour; and
C) Prevent operation of the source of radiation if it would
produce radiation levels in the area that could result in a deep dose
equivalent to an individual in excess of 1 mSv (0.1 rem) in 1 hour.
2) Additional control devices shall be provided so that, upon
failure of the entry control devices to function as required by subsection
(b)(1) of this Section:
A) The radiation level within the area, from the source of
radiation, is reduced below that at which it would be possible for an
individual to receive a deep dose equivalent in excess of 1 mSv (0.1 rem) in 1
hour; and
B) Conspicuous visible and audible alarm signals are generated to
make an individual attempting to enter the area aware of the hazard. The alarm
signals shall be located so that at least one other authorized individual, who
is physically present, familiar with the activity, and prepared to render or
summon assistance, is made aware of the failure of the entry control devices.
3) The licensee or registrant shall provide control devices so
that, upon failure or removal of any physical radiation barriers, other than
the shielded storage container for sealed sources:
A) The radiation level from the source of radiation is reduced below
that at which it would be possible for an individual to receive a deep dose
equivalent in excess of 1 mSv (0.1 rem) in 1 hour; and
B) Conspicuous visible and audible alarm signals are generated to
make potentially affected individuals aware of the hazard and the licensee or
registrant or at least one other individual, who is familiar with the activity
and prepared to render or summon assistance, aware of the failure or removal of
the physical barrier.
4) When the shield for the stored sealed source is a liquid, the
licensee shall provide means to monitor the integrity of the shield and to
signal, automatically, loss of adequate shielding.
5) Physical radiation barriers that comprise permanent structural
components, such as walls, that have no credible probability of failure or
removal in ordinary circumstances need not meet the requirements of subsections
(b)(3) and (4) of this Section.
6) Each area shall be equipped with devices that will
automatically generate conspicuous visible and audible alarm signals to alert
personnel in the area before the source of radiation can be put into operation
and in time for any individual in the area to operate a clearly identified
control device, which must be installed in the area and that can prevent the
source of radiation from being put into operation.
7) Each area shall be controlled by use of devices and
administrative procedures that ensure that the area is cleared of personnel
prior to each use of the source of radiation.
8) Each area shall be checked by a radiation measurement to
ensure that, prior to the first individual's entry into the area after any use
of the source of radiation, the radiation level from the source of radiation in
the area is below that at which it would be possible for an individual to
receive a deep dose equivalent in excess of 1 mSv (0.1 rem) in 1 hour.
9) The entry control devices required in subsection (b)(1) of
this Section shall be tested for proper functioning (see Section 340.1190 of
this Part for recordkeeping requirements).
A) Testing shall be conducted prior to initial operation with the
source of radiation on any day, unless operations were continued uninterrupted
from the previous day;
B) Testing shall be conducted prior to resumption of operation of
the source of radiation after any unintentional interruption; and
C) The licensee or registrant shall submit and adhere to a
schedule for periodic tests of the entry control and warning systems.
10) The licensee or registrant shall not conduct operations,
other than those necessary to place the source of radiation in safe condition
or to effect repairs on controls, unless control devices are functioning
properly.
11) Entry and exit portals that are used in transporting matter
to and from the irradiation area, and that are not intended for use by
individuals, shall be controlled by such devices and administrative procedures
as are necessary to physically protect and warn against inadvertent entry by any
individual through these portals. Exit portals for irradiated matter shall be
equipped to detect and signal the presence of any loose sealed sources that are
carried toward such an exit and to automatically prevent loose sealed sources
from being carried out of the area.
c) Registrants, licensees or applicants for licenses for sources
of radiation that are within the purview of subsection (b) of this Section and that
will be used in a variety of positions or in locations (e.g., open fields or
forests) that make it impracticable to comply with certain requirements of
subsection (b) of this Section, such as those for the automatic control of
radiation levels, may apply to the Agency for approval of alternative safety
measures. Alternative safety measures shall provide personnel protection at
least equivalent to those specified in subsection (b) of this Section. At
least one of the alternative measures shall include an entry-preventing
interlock control based on a measurement of the radiation that ensures the
absence of high radiation levels before an individual can gain access to the
area where such sources of radiation are used.
d) The entry control devices required by subsections (b) and (c) of
this Section shall be established in such a way that no individual will be
prevented from leaving the area.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
SUBPART H: RESPIRATORY PROTECTION AND CONTROLS TO RESTRICT INTERNAL EXPOSURE IN RESTRICTED AREAS
Section 340.710 Use of
Process or Other Engineering Controls
a) The licensee shall use, to the extent practicable, process or
other engineering controls (e.g., containment or ventilation) to control the
concentrations of radioactive material in air.
b) The licensee
shall measure airflow rates initially and semiannually thereafter to assure
proper ventilation system performance. Records of the evaluation of
ventilation system performance shall be maintained for Agency inspection and
shall include:
1) The date of evaluation;
2) Results of
ventilation rate measurements;
3) Manufacturer,
model and serial number of the measurement instrument used; and
4) The
identity of the individual performing the measurements.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.720 Use of Other
Controls
a) When it is not practical to apply process or other engineering
controls to control the concentrations of radioactive material in air to values
below those that define an airborne radioactivity area, the licensee shall,
consistent with maintaining the total effective dose equivalent ALARA, increase
monitoring and limit intakes by one or more of the following means:
1) Control of access; or
2) Limitation of exposure times; or
3) Use of respiratory protection equipment; or
4) Other controls.
b) If the licensee performs an ALARA analysis to determine
whether respirators shall be used, the licensee may consider safety factors
other than radiological factors. The licensee shall also consider the impact
of respirator use on workers' industrial health and safety.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.730 Use of
Individual Respiratory Protection Equipment
a) If the licensee assigns or permits the use of respiratory
protection equipment to limit the intake of radioactive material then:
1) Except as provided in subsection (a)(2), the licensee shall
use only respiratory protection equipment that is tested and certified by the
National Institute for Occupational Safety and Health (NIOSH).
2) The licensee may use equipment that has not been tested or
certified by NIOSH, or for which there is no schedule for testing or
certification, provided the Agency has approved an application for authorized
use of that equipment. The application shall include evidence that the material
and performance characteristics of the equipment are capable of providing the
proposed degree of protection under anticipated conditions of use. This shall
be demonstrated either by licensee testing or on the basis of reliable test
information.
3) The licensee shall implement and maintain a respiratory
protection program that includes:
A) Air
sampling sufficient to identify the potential hazard, permit proper equipment
selection, and estimate doses.
B) Surveys and bioassays,
as necessary, to evaluate actual intakes.
C) Testing
of respirators for operability (user seal check for face sealing devices and
functional check for others) immediately prior to each use.
D) Written procedures
regarding:
i) Monitoring,
including air sampling and bioassays;
ii) Supervision
and training of respirator users;
iii) Fit
testing;
iv) Respirator
selection;
v) Breathing
air quality;
vi) Inventory
and control;
vii) Storage,
issuance, maintenance, repair, testing, and quality assurance of respiratory protection
equipment;
viii) Recordkeeping;
and
ix) Limitations
on periods of respirator use and relief from respirator use.
E) Determination
by a physician that the individual user is medically fit to use respiratory
protection equipment:
i) Before
the initial fitting of a face sealing respirator;
ii) Before
the first field use of non-face sealing respirators; and
iii) Either
every 12 months thereafter or periodically at a frequency determined by a
physician.
F) Fit testing, with a fit factor > 10 times the APF for
negative pressure devices, and a fit factor > 500 for any positive pressure,
continuous flow, and pressure-demand devices, before the first field use of
tight fitting, face-sealing respirators and periodically thereafter at a
frequency not to exceed 1 year. Fit testing must be performed with the
facepiece operating in the negative pressure mode.
4) The licensee shall advise each respirator user that the user
may leave the area at any time for relief from respirator use in the event of
equipment malfunction, physical or psychological distress, procedural or
communication failure, significant deterioration of operating conditions, or
any other conditions that might require such relief.
5) The
licensee shall consider limitations appropriate to the type and mode of use.
When selecting respiratory devices the licensee shall provide for vision
correction, adequate communication, low temperature work environments, and the
concurrent use of other safety or radiological protection equipment. The licensee
shall use equipment in such a way as not to interfere with the proper operation
of the respirator.
6) Standby
rescue persons are required whenever one-piece atmosphere-supplying suits, or
any combination of supplied air respiratory protection device and personnel
protective equipment are used from which an unaided individual would have
difficulty extricating himself or herself. The standby persons shall be
equipped with respiratory protection devices or other apparatus appropriate for
the potential hazards. The standby rescue persons shall observe or otherwise
maintain continuous communication with the workers (visual, voice, signal line,
telephone, radio, or other suitable means), and be immediately available to
assist them in case of a failure of the air supply or for any other reason that
requires relief from distress. A sufficient number of standby rescue persons shall
be immediately available to assist all users of this type of equipment and to
provide effective emergency rescue if needed.
7) Atmosphere-supplying
respirators must be supplied with respirable air of grade D quality or better
as defined by the Compressed Gas Association in publication G-7.1,
"Commodity Specification for Air", 1997 and included in the
regulations of the Occupational Safety and Health Administration at 29 CFR
1910.134(i)(1)(ii)(A) through (E) (2019). Grade D quality air criteria include:
i) Oxygen content (v/v)
of 19.5-23.5%;
ii) Hydrocarbon
(condensed) content of 5 milligrams per cubic meter of air or less;
iii) Carbon monoxide (CO)
content of 10 ppm or less;
iv) Carbon dioxide content
of 1,000 ppm or less; and
v) Lack of noticeable
odor.
8) The
licensee shall ensure that no objects, materials, or substances, such as facial
hair, or any conditions that interfere with the face, facepiece seal, or valve
function, under the control of the respirator wearer, are present between the
skin of the respirator wearer's face and the sealing surface of a tight-fitting
respirator facepiece.
b) When estimating the dose to individuals from intake of
airborne radioactive materials, the concentration of radioactive material in
the air that is inhaled when respirators are worn is initially assumed to be
the ambient concentration in air without respiratory protection, divided by the
assigned protection factor. If the dose is later found to be greater than the
estimated dose, the corrected value shall be used; if the dose is later found
to be less than the estimated dose, the corrected value may be used.
Protection factors for respirators are specified in Appendix A to 10 CFR 20
(1999).
c) The licensee shall obtain authorization from the Agency before
using assigned protection factors in excess of those specified in Appendix A to
10 CFR 20 (1999). The Agency may authorize a licensee to use higher assigned protection
factors on receipt of an application that:
1) Describes the situation for which a need exists for higher
protection factors; and
2) Demonstrates that the respiratory protection equipment
provides these higher protection factors under the proposed conditions of use.
d) The Agency may impose restrictions in addition to the
provisions of this Section, Section 340.720, and Appendix A to 10 CFR 20 (1999)
in order to ensure the respiratory protection program of the licensee is
adequate to limit doses to individuals from intakes of airborne radioactive
materials consistent with maintaining total effective dose equivalent ALARA and
limit the extent to which a licensee may use respiratory protection equipment
instead of process or other engineering controls.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.910 Caution
Signs
a) Standard Radiation Symbol. Unless otherwise authorized by the
Agency, the symbol prescribed by this Part shall use the colors magenta, purple
or black on yellow background. The symbol prescribed by this Part is the
three-bladed design shown in Illustration A of this Part.
b) Exception to Color Requirements for Standard Radiation Symbol.
Notwithstanding the requirements of subsection (a) of this Section, licensees
or registrants are authorized to label sources, source holders, or device
components containing sources of radiation that are subjected to high
temperatures, with conspicuously etched or stamped radiation caution symbols
and without a color requirement.
c) Additional Information on Signs and Labels. In addition to
the contents of signs and labels prescribed in this Part, the licensee or
registrant may provide, on or near the required signs and labels, information
to make individuals aware of potential radiation exposures and to minimize the
exposures.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.920 Posting
Requirements
a) Posting of Radiation Areas. The licensee or registrant shall
post each radiation area with a conspicuous sign or signs bearing the radiation
symbol and the words "CAUTION, RADIATION AREA".
b) Posting of High Radiation Areas. The licensee or registrant shall
post each high radiation area with a conspicuous sign or signs bearing the
radiation symbol and the words "CAUTION, HIGH RADIATION AREA" or
"DANGER, HIGH RADIATION AREA".
c) Posting of Very High Radiation Areas. The licensee or
registrant shall post each very high radiation area with a conspicuous sign or
signs bearing the radiation symbol and words "GRAVE DANGER, VERY HIGH
RADIATION AREA".
d) Posting of Airborne Radioactivity Areas. The licensee shall
post each airborne radioactivity area with a conspicuous sign or signs bearing
the radiation symbol and the words "CAUTION, AIRBORNE RADIOACTIVITY
AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA".
e) Posting of Areas or Rooms in Which Licensed Material is Used
or Stored. The licensee shall post each area or room in which there is used or
stored an amount of licensed material exceeding ten times the quantity of such
material specified in Appendix C to 10 CFR 20, effective January 1, 2004,
exclusive of subsequent amendments or editions, with a conspicuous sign or
signs bearing the radiation symbol and the words "CAUTION, RADIOACTIVE
MATERIAL(S)" or "DANGER, RADIOACTIVE MATERIAL(S)".
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.930 Exceptions
to Posting Requirements
a) A licensee or registrant is not required to post caution signs
in areas or rooms containing sources of radiation for periods of less than 8
hours, if each of the following conditions is met:
1) The sources of radiation are constantly attended during these
periods by an individual who takes the precautions necessary to prevent the
exposure of individuals to sources of radiation in excess of the limits
established in this Part; and
2) The area or room is subject to the licensee's or registrant's
control.
b) Rooms or other areas in hospitals that are occupied by
patients are not required to be posted with caution signs pursuant to Section
340.920 of this Part provided that the patient door posting requirements of 32
Ill. Adm. Code 335.5030(a)(5) or 335.7030(b) are met.
c) Rooms or other areas in hospitals that are occupied by
patients are not required to be posted with caution signs, provided that:
1) A patient being treated with a permanent implant could be
released from confinement pursuant to 32 Ill. Adm. Code 335.2110; or
2) A patient being treated with a therapeutic radiopharmaceutical
could be released from confinement pursuant to 32 Ill. Adm. Code 335.5030(b).
d) A room or area is not required to be posted with a caution
sign because of the presence of a sealed source provided the radiation level at
30 centimeters (12 inches) from the surface of the sealed source container or
housing does not exceed 0.05 mSv (0.005 rem) per hour.
e) A room or area is not required to be posted with a caution sign
because of the presence of radiation machines used solely for diagnosis in the
healing arts.
f) If a room or area in which radioactive material or radiation
machines are used for the treatment of patients is required to be posted with
the words, "GRAVE DANGER, VERY HIGH RADIATION AREA" in accordance
with 340.920(c) of this Part, the following words may be substituted: "DANGER,
VERY HIGH RADIATION AREA".
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.940 Labeling
Containers and Radiation Machines
a) The licensee shall ensure that each container of licensed
material bears a durable, clearly visible label bearing the radiation symbol
and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER,
RADIOACTIVE MATERIAL". The label shall also provide information (such as
the radionuclides present, an estimate of the quantity of radioactivity, the
date for which the activity is estimated, radiation levels, kinds of materials
and mass enrichment) to permit individuals handling or using the containers, or
working in the vicinity of the containers, to take precautions to avoid or
minimize exposures.
b) Each licensee shall, prior to removal or disposal of empty
uncontaminated containers to unrestricted areas, remove or deface the
radioactive material label or otherwise clearly indicate that the container no
longer contains radioactive materials.
c) Each registrant shall ensure that each radiation machine is
labeled in a manner that cautions individuals that radiation is produced when
it is energized.
Section 340.950 Exemptions
to Labeling Requirements
A licensee is not required to
label:
a) Containers holding licensed material in quantities less than
the quantities listed in appendix C to 10 CFR 20, published at 60 Fed. Reg.
20186, April 25, 1995; or
b) Containers holding licensed material in concentrations less
than those specified in Table 3 of appendix B to 10 CFR 20, published at 72
Fed. Reg. 55922, October 1, 2007; or
c) Containers attended by an individual who takes the precautions
(e.g., controlling access) necessary to prevent the exposure of individuals in
excess of the limits established by this Part; or
d) Containers when they are in transport, provided the containers
are packaged and labeled in accordance with the regulations of the U.S.
Department of Transportation; or
AGENCY NOTE:
Labeling of packages containing radioactive materials is required by the U.S.
Department of Transportation if the amount and type of radioactive material
exceeds the limits for an excepted quantity or article as defined and limited
by 49 CFR 173.403 and 173.421 through 173.424, revised October 1, 2008.
e) Containers that are accessible only to individuals authorized
to handle or use them, or to work in the vicinity of the containers, if the
contents are identified to these individuals by a readily available written
record (examples of containers of this type are containers in locations such as
water-filled canals, storage vaults or hot cells). The record shall be
retained as long as the containers are in use for the purpose indicated on the
record; or
f) Installed manufacturing
or process equipment, such as piping and tanks.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.960 Procedures
for Receiving and Opening Packages
a) Each licensee who is authorized to receive a package
containing quantities of radioactive material in excess of a Type A quantity,
as defined in 49 CFR 173.403 and listed in 49 CFR 173.435 (2020), shall:
1) Make arrangements to receive the package when the carrier
offers it for delivery; or
2) Make arrangements to receive the notification of the arrival
of the package at the carrier's terminal and to take possession of the package
expeditiously.
b) Each licensee shall:
1) Monitor the external surfaces of a labeled package for
radioactive contamination unless the package contains only radioactive material
in the form of a gas or in special form radioactive material as defined in 32
Ill. Adm. Code 310.20;
AGENCY NOTE:
Labeled means labeled with a Radioactive White I, Radioactive Yellow II or
Radioactive Yellow III label as specified in U.S. Department of Transportation
regulations, 49 CFR 172.403 and 172.436-440, published October 1, 2004.
2) Monitor the external surfaces of a labeled package for
radiation levels unless the package contains quantities of radioactive material
that are less than or equal to the Type A quantity; and
3) Monitor all packages known to contain radioactive material for
radioactive contamination and radiation levels if there is evidence of
degradation of package integrity, such as packages that are crushed, wet or
damaged.
c) The licensee shall perform the monitoring required by
subsection (b) as soon as practicable after receipt of the package, but not
later than 3 hours after the package is received at the licensee's facility if
it is received during the licensee's normal working hours or if there is
evidence of degradation of package integrity, such as a package that is
crushed, wet or damaged. If a package is received after working hours, and has
no evidence of degradation of package integrity, the package shall be monitored
no later than 3 hours from the beginning of the next working day.
d) The licensee shall immediately notify the final delivery
carrier and the Agency by telephone at (217) 782-7860, and shall confirm the
initial contact within 24 hours by overnight letter or telefacsimile to the Agency,
when:
1) Removable radioactive surface contamination exceeds the limits
of 32 Ill. Adm. Code 341.10 (49 CFR 173.443 (2014)); or
2) External radiation levels exceed the limits of 32 Ill. Adm.
Code 341.10 (49 CFR 173.441 (2004)).
e) Each licensee shall:
1) Establish, maintain, and retain written procedures for safely
opening packages in which radioactive material is received; and
2) Ensure that the procedures are followed and that special
instructions for the type of package being opened are adhered to.
f) Licensees transferring special form sources in licensee-owned
or licensee-operated vehicles to and from a work site are exempt from the
contamination monitoring requirements of subsection (b), but are not exempt
from the survey requirement in subsection (b) for measuring radiation levels
that is required to ensure that the source is still properly lodged in its
shield.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1010 General
Requirements
a) A licensee shall dispose of licensed material only:
1) By transfer to an authorized recipient as provided in Section
340.1060 or in 32 Ill. Adm. Code 330, 332 or 601, or to the U.S. Department of
Energy; or
2) By release in effluents within the limits in Section 340.310;
or
3) As authorized pursuant to Sections 340.1020, 340.1030,
340.1040, 340.1045, or 340.1050.
b) A person shall be specifically licensed by the Agency prior to
receiving waste containing licensed material from any other point of generation
for:
1) Storage for decay; or
2) Treatment prior to disposal; or
3) Treatment or disposal by incineration; or
4) Disposal at a land disposal facility licensed pursuant to 32
Ill. Adm. Code 601; or
5) Storage until transferred to a disposal facility authorized to
receive the waste.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1020 Method for
Obtaining Approval of Proposed Disposal Procedures
A licensee or applicant for a
license may apply to the Agency for approval of proposed procedures, not
otherwise authorized in 32 Ill. Adm. Code: Chapter II, Subchapters b and d, to
dispose of licensed material generated in the licensee's operations. Each
application shall include:
a) A description of the waste containing licensed material to be
disposed of, including the physical and chemical properties that have an impact
on risk evaluation, and the proposed manner and conditions of waste disposal;
b) An analysis and evaluation of pertinent information on the nature
of the environment;
c) The nature and location of other potentially affected
facilities; and
d) Analyses and procedures to ensure that doses are maintained
ALARA and within the dose limits in this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1030 Disposal by
Release into Sanitary Sewerage
a) A licensee may discharge licensed material into sanitary
sewerage if each of the following conditions is satisfied:
1) The material is readily soluble, or is readily dispersible
biological material, in water;
2) The quantity of licensed radioactive material that the
licensee releases into the sewer in 1 month divided by the average monthly
volume of water released into the sewer by the licensee does not exceed the
concentration listed in table 3 of appendix B to 10 CFR 20, published at 72
Fed. Reg. 55922, October 1, 2007, exclusive of subsequent amendments or
editions;
3) If more than one radionuclide is released, the following
conditions must also be satisfied:
A) The licensee shall determine the fraction of the limit in table
3 of appendix B to 10 CFR 20, published at 72 Fed. Reg. 55922, October 1, 2007,
exclusive of subsequent amendments or editions, represented by discharges into
sanitary sewerage by dividing the actual monthly average concentration of each
radionuclide released by the licensee into the sewer by the concentration of
that radionuclide listed in table 3 of appendix B to 10 CFR 20, published at 72
Fed. Reg. 55922, October 1, 2007, exclusive of subsequent amendments or
editions; and
B) The sum of the fractions for each radionuclide required by
subsection (a)(3)(A) of this Section does not exceed unity;
4) The total quantity of licensed radioactive material that the
licensee releases into sanitary sewerage in a year does not exceed 185 GBq (5
Ci) of hydrogen-3, 37 GBq (1 Ci) of carbon-14, and 37 GBq (1 Ci) of all other
radioactive materials combined; and
5) In determining compliance with subsections (a)(1) through (4),
the licensee shall not include the activity from radioactive material excluded
by subsection (b).
b) Excreta from individuals undergoing medical diagnosis or
therapy with radioactive material are not subject to the limitations contained
in subsection (a).
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.1040 Treatment
or Disposal by Incineration
A licensee may treat or dispose
of licensed material by incineration only in the amounts and forms specified in
Section 340.1050 of this Part or as specifically approved by the Agency
pursuant to Section 340.1020 of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1045 Decay-In-Storage
A licensee may store waste containing or composed of
radioactive material with a physical half-life of less than 120 days for
"decay-in-storage" before disposal as normal waste without regard to
its radioactivity if it:
a) Holds the radioactive material for a minimum of 10 half-lives; and
b) Pursuant
to Section 340.510(a) and (b), performs radiation surveys prior to disposal of
the radioactive material to ensure that the material's radioactivity cannot be
distinguished from background radiation levels. The package/container surface
shall be surveyed with an appropriate radiation detection survey instrument set
on its most sensitive scale, with no interposed shielding between the detector
and the material, in a low background radiation environment; and
c) Maintains
records of monitoring to include: date of disposal; date placed in storage;
manufacturer, model and serial number of the survey instrument used; background
radiation levels; and measured radiation levels; and
d) Records
the identity of the individual performing the monitoring; and
e) Removes or obliterates
all radiation labels.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.1050 Disposal of
Specific Wastes
a) A licensee may dispose of the following licensed material as
if it were not radioactive:
1) 1.85 kBq (0.05 µCi), or less, of hydrogen-3, carbon-14 or
iodine-125 per gram of medium used for scintillation counting; and
2) 1.85 kBq (0.05 µCi), or less, of hydrogen-3, carbon-14 or
iodine-125 per gram of animal tissue, averaged over the weight of the entire
animal.
b) A licensee shall not dispose of tissue pursuant to subsection
(a)(2) of this Section in a manner that would permit its use either as food for
humans or as animal feed.
c) The licensee shall maintain records in accordance with Section
340.1180 of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1052
Classification of Radioactive Waste for Land Disposal
a) Considerations. Determination of the classification of
radioactive waste involves two considerations. First, consideration must be
given to the concentration of long-lived radionuclides (and their shorter-lived
precursors) whose potential hazard will persist long after such precautions as
institutional controls, improved waste form and deeper disposal have ceased to
be effective. These precautions delay the time when long-lived radionuclides
could cause exposures. In addition, the magnitude of the potential dose is
limited by the concentration and availability of the radionuclide at the time
of exposure. Second, consideration must be given to the concentration of
shorter-lived radionuclides for which requirements on institutional controls,
waste form and disposal methods are effective.
b) Classes of waste.
1) Class A waste is waste that is usually segregated from other
waste classes at the disposal site. The physical form and characteristics of
Class A waste must meet the minimum requirements set forth in Section
340.1055(a) of this Part. If Class A waste also meets the stability
requirements set forth in Section 340.1055(b) of this Part, it is not necessary
to segregate the waste for disposal.
2) Class B waste is waste that must meet more rigorous
requirements on waste form to ensure stability (as defined in 32 Ill. Adm. Code
601.20) after disposal. The physical form and characteristics of Class B waste
must meet both the minimum and stability requirements set forth in Section
340.1055 of this Part.
3) Class C waste is waste that not only must meet more rigorous
requirements on waste form to ensure stability but also requires additional
measures at the disposal facility to protect against inadvertent intrusion.
The physical form and characteristics of Class C waste must meet both the
minimum and stability requirements set forth in Section 340.1055 of this Part.
c) Classification determined by long-lived radionuclides. If the
radioactive waste contains only radionuclides listed in Table 1 of this Section,
classification shall be determined as follows:
1) If the concentration does not exceed 0.1 times the value in
Table 1, the waste is Class A.
2) If the concentration exceeds 0.1 times the value in Table 1,
but does not exceed the value in Table 1, the waste is Class C.
3) If the concentration exceeds the value in Table 1, the waste
is not generally acceptable for land disposal.
4) For wastes containing mixtures of radionuclides listed in
Table 1, the total concentration shall be determined by the sum of fractions
rule described in subsection (g) of this Section.
|
Table
1
|
|
Radionuclide
|
Concentration
curies/cubic meter
|
|
C-14
|
8
|
|
C-14 in
activated metal
|
80
|
|
Ni-59 in
activated metal
|
220
|
|
Nb-94 in
activated metal
|
0.2
|
|
Tc-99
|
3
|
|
I-129
|
0.08
|
|
Alpha emitting transuranic radionuclides with half-life greater than
five years
|
100
|
|
Pu-241
|
3,500
|
|
Cm-242
|
20,000
|
|
Ra-226
|
100
|
AGENCY NOTE:
Units are nanocuries per gram.
d) Classification determined by short-lived radionuclides. If
the waste does not contain any of the radionuclides listed in Table 1,
classification shall be determined based on the concentrations shown in Table 2
of this Section. However, as specified in subsection (f) of this Section, if
radioactive waste does not contain any nuclides listed in either Table 1 or
Table 2, it is Class A.
1) If the concentration does not exceed the value in Column 1,
the waste is Class A.
2) If the concentration exceeds the value in Column 1 but does
not exceed the value in Column 2, the waste is Class B.
3) If the concentration exceeds the value in Column 2 but does
not exceed the value in Column 3, the waste is Class C.
4) If the concentration exceeds the value in Column 3, the waste
is not generally acceptable for near-surface disposal.
5) For wastes containing mixtures of the radionuclides listed in
Table 2, the total concentration shall be determined by the sum of fractions
rule described in subsection (g) of this Section.
|
Table
2
|
|
Radionuclide
|
Concentration
(curies/cubic meter)
|
|
Column 1
|
Column 2
|
Column 3
|
|
Total of all radionuclides with less than 5-year half-life
|
700
|
–
|
–
|
|
H-3
|
40
|
–
|
–
|
|
Co-60
|
700
|
–
|
–
|
|
Ni-63
|
3.5
|
70
|
700
|
|
Ni-63 in activated metal
|
35
|
700
|
7000
|
|
Sr-90
|
0.04
|
150
|
7000
|
|
Cs-137
|
1
|
44
|
4600
|
AGENCY NOTE:
There are no limits established for these radionuclides in Class B or C
wastes. Practical considerations such as the effects of external radiation and
internal heat generation on transportation, handling and disposal will limit
the concentrations for these wastes. These wastes shall be Class B unless the
concentrations of other radionuclides in Table 2 determine the waste to be
Class C independent of these radionuclides.
e) Classification determined by both long- and short-lived
radionuclides. If the radioactive waste contains a mixture of radionuclides,
some of which are listed in Table 1 and some of which are listed in Table 2,
classification shall be determined as follows:
1) If the concentration of a radionuclide listed in Table 1 is
less than 0.1 times the value listed in Table 1, the class shall be that
determined by the concentration of radionuclides listed in Table 2.
2) If the concentration of a radionuclide listed in Table 1
exceeds 0.1 times the value listed in Table 1, but does not exceed the value in
Table 1, the waste shall be Class C, provided the concentration of
radionuclides listed in Table 2 does not exceed the value shown in Column 3 of
Table 2.
f) Classification of wastes with radionuclides other than those
listed in Tables 1 and 2. If the waste does not contain any radionuclides
listed in either Tables 1 or 2, it is Class A.
g) The sum of the fractions rule for mixtures of radionuclides.
For determining classification for waste that contains a mixture of radionuclides,
it is necessary to determine the sum of fractions by dividing each
radionuclide's concentration by the appropriate limit and adding the resulting
values. The appropriate limits must all be taken from the same column of the
same table. The sum of the fractions for the column must be less than 1.0 if
the waste class is to be determined by that column. Example: A waste contains
Sr-90 in a concentration of 50 Ci/m3 and Cs-137 in a concentration of 22 Ci/m3.
Since the concentrations both exceed the values in Column 1, Table 2, they must
be compared to Column 2 values. For Sr-90 fraction, 50/150 = 0.33, for Cs-137
fraction, 22/44 = 0.5; the sum of the fractions = 0.83. Since the sum is less
than 1.0, the waste is Class B.
h) Determination of concentrations in wastes. The concentration
of a radionuclide may be determined by indirect methods such as use of scaling
factors which relate the inferred concentration of one radionuclide to another
that is measured, or radionuclide material accountability, if there is
reasonable assurance that the indirect methods can be correlated with actual
measurements. The concentration of a radionuclide may be averaged over the
volume of the waste, or weight of the waste if the units are expressed as
nano-curies per gram.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1055 Radioactive
Waste Characteristics
a) The following are minimum requirements for all classes of
waste and are intended to facilitate handling and provide protection of health
and safety of personnel at the disposal site.
1) Wastes shall be packaged in conformance with the conditions of
the license issued to the site operator to which the waste will be shipped.
Where the conditions of the site license are more restrictive than the
provisions of this Part, the site license conditions shall govern.
2) Wastes shall not be packaged for disposal in cardboard or
fiberboard boxes.
3) Liquid waste shall be packaged in sufficient absorbent
material to absorb twice the volume of the liquid.
4) Solid waste containing liquid shall contain as little
free-standing and non-corrosive liquid as is reasonably achievable, but in no
case shall the liquid exceed 1% of the volume.
5) Waste shall not be readily capable of detonation or of
explosive decomposition or reaction at normal pressures and temperatures, or of
explosive reaction with water.
6) Waste shall not contain, or be capable of generating,
quantities of toxic gases, vapors, or fumes harmful to persons transporting,
handling, or disposing of the waste. This does not apply to radioactive
gaseous waste packaged in accordance with subsection (a)(8).
7) Waste must not be pyrophoric. Pyrophoric materials contained
in wastes shall be treated, prepared, and packaged to be nonflammable.
8) Wastes in a gaseous form shall be packaged at an absolute
pressure that does not exceed 1.5 atmospheres at 20°C (68°F). Total activity
shall not exceed 100 Ci per container.
9) Wastes containing hazardous, biological, pathogenic, or
infectious material shall be treated to reduce to the maximum extent
practicable the potential hazard from the non-radiological materials.
b) The following requirements are intended to provide stability
of the waste. Stability is intended to ensure that the waste does not degrade
and affect overall stability of the site through slumping, collapse, or other
failure of the disposal unit and thereby lead to water infiltration. Stability
is also a factor in limiting exposure to an inadvertent intruder, since it
provides a recognizable and nondispersible waste.
1) Waste shall have structural stability. A structurally stable
waste form will generally maintain its physical dimensions and its form, under
the expected disposal conditions such as weight of overburden and compaction
equipment, the presence of moisture, and microbial activity, and internal factors
such as radiation effects and chemical changes. Structural stability can be
provided by the waste form itself, processing the waste to a stable form, or
placing the waste in a disposal container or structure that provides stability
after disposal.
2) Notwithstanding the provisions in subsections (a)(3) and
(a)(4), liquid wastes, or wastes containing liquid, shall be converted into a
form that contains as little free-standing and non-corrosive liquid as is
reasonably achievable, but in no case shall the liquid exceed 1% of the volume
of the waste when the waste is in a disposal container designed to ensure
stability, or 0.5% of the volume of the waste for waste processed to a stable
form.
3) Void spaces within the waste and between the waste and its
package shall be reduced to the extent practicable.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1057 Labeling
Each package of waste shall be
clearly labeled to identify whether it is Class A, Class B or Class C waste, in
accordance with Section 340.1052 of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1060 Transfer
for Disposal and Manifests
a) Each licensee who transports or offers for transportation
low-level radioactive waste intended for ultimate disposal at a licensed
low-level radioactive waste disposal facility shall prepare a manifest
reflecting information requested on the applicable NRC Forms 540 (Uniform
Low-Level Radioactive Waste Manifest-Shipping Paper) and 541 (Uniform Low-Level
Radioactive Waste Manifest-Container and Waste Description) and, if necessary,
on an applicable NRC Form 542 (Uniform Low-Level Radioactive Waste Manifest-Manifest
Index and Regional Compact Tabulation).
AGENCY NOTE:
For guidance in completing these forms, refer to the instructions that
accompany the forms. NRC Forms 540, 540A, 541, 541A, 542, and 542A and the
accompanying written instructions may be obtained from the Office of the Chief
Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001,
telephone (301) 415-5877, or http://www.nrc.gov.
b) NRC
Forms 540 and 540A shall be completed and shall physically accompany each
low-level radioactive waste shipment. Each licensee shipping low-level
radioactive waste shall transfer manifest information to the consignee.
c) Upon agreement between the shipper and the consignee, NRC
Forms 541, 541A, 542, or 542A may be completed, transmitted, and stored in
electronic media with the capability of producing legible, accurate, and
complete records on the respective forms. Copies of manifests required by this
Section may be legible carbon copies, photocopies, or computer printouts that
reproduce the data in the format of the uniform manifest.
d) Licensees
are exempt from the manifesting requirements of this Section when shipping:
1) Low-level
radioactive waste for processing and when they expect its return (i.e., for
storage under their license) prior to disposal at a licensed disposal facility;
2) Low-level
radioactive waste that is being returned to the licensee who is the waste generator;
or
3) Radioactively
contaminated material to a waste processor that becomes the processor's
residual waste.
e) Each licensee shipping low-level radioactive waste shall also
comply with the reporting requirements specified in 32 Ill. Adm. Code 609.
f) Each
shipper of radioactive waste shall provide the following information regarding
the waste shipment on the uniform manifest:
1) The
name, facility address, and telephone number of the licensee shipping the
waste;
2) An
explicit declaration indicating whether the shipper is acting as a waste
generator, collector or processor, or a combination of these identifiers, for
purposes of the manifested shipment;
3) The
name, address, and telephone number, or the name and USEPA identification
number, for the carrier transporting the waste;
4) The
date of the waste shipment;
5) The
total number of packages/disposal containers;
6) The
total disposal volume and disposal weight in the shipment;
7) The
total radionuclide activity in the shipment;
8) The
activity of each of the radionuclides H-3, C-14, Tc-99 and I-129 contained in
the shipment; and
9) The
total masses of U-233, U-235, and plutonium in special nuclear material, and
the total mass of uranium and thorium in source material.
AGENCY NOTE:
The reporting requirements of the uniform manifest meet the reporting
requirements of USDOT for the shipments of waste. Therefore, no additional USDOT
forms are required for shipments of low-level radioactive waste. However, the
uniform manifest does not meet the reporting requirements of USEPA for the
shipment of hazardous, medical, or other waste. Any additional USEPA
requirements shall be met by using an additional USEPA manifest. In addition,
the uniform manifest reporting requirements do not meet the tracking
requirements of 32 Ill. Adm. Code 609.
g) For
waste shipments in disposal containers, each shipper shall provide the
following information on the uniform manifest regarding the waste and each
disposal container of waste in the shipment:
1) An
alphabetic or numeric identification that identifies each disposal container in
the shipment;
2) A
physical description of the disposal container, including the manufacturer and
model of any high integrity container;
3) The
volume displaced by the disposal container;
4) The
gross weight of the disposal container, including the waste;
5) For
waste consigned to a disposal facility, the maximum radiation level at the
surface of each disposal container;
6) A
physical and chemical description of the waste;
7) The
total weight percentage of chelating agent for any waste containing more than
0.1 percent chelating agent by weight, plus the identity of the principal
chelating agent;
8) The
approximate volume of waste within a container;
9) The
sorbing or solidification media, if any, and the identity of the manufacturer
of the solidification media and brand name;
10) The identities and activities of individual radionuclides
contained in each container, the masses of U-233, U-235, and plutonium in
special nuclear material, and the masses of uranium and thorium in source
material. For discrete waste types (i.e., activated materials, contaminated
equipment, mechanical filters, sealed sources/devices, and wastes in
solidification/ stabilization media), the identities and activities of
individual radionuclides associated with or contained in these waste types
within a disposal container shall be reported;
11) The total radioactivity within each container; and
12) For wastes consigned to a disposal facility, the
classification of the waste shall be identified on the manifest pursuant to
Section 340.1052. Waste not meeting the structural stability requirements of
Section 340.1055(b) shall also be identified on the manifest.
h) For
waste shipments delivered without a disposal container, the shipper of the
radioactive waste shall provide the following information on the uniform
manifest:
1) The
approximate volume and weight of the waste;
2) A
physical and chemical description of the waste;
3) The
total weight percentage of chelating agent for any waste containing more than
0.1 percent chelating agent by weight, plus the identity of the principal
chelating agent;
4) For
wastes consigned to a disposal facility, the classification of the waste shall
be identified on the manifest pursuant to Section 340.1052. Waste not meeting
the structural stability requirements of Section 340.1055(b) shall also be
identified on the manifest;
5) The
identities and activities of individual radionuclides contained in the waste,
the masses of U-233, U-235, and plutonium in special nuclear material, and the
masses of uranium and thorium in source material; and
6) For
waste consigned to a disposal facility, the maximum radiation levels at the
surface of the waste.
i) For
waste comprised of mixtures of waste originating from different waste
generators, the shipper shall provide the following information on the uniform
manifest:
AGENCY NOTE:
The origin of the low-level radioactive waste resulting from a processor's
activities may be attributable to one or more "waste generators" as
defined in this Part.
1) For
homogeneous mixtures of waste, such as incinerator ash, provide the waste
description applicable to the mixture and the volume of the waste attributed to
each waste generator.
2) For
heterogeneous mixtures of waste, such as the combined products from a large
compactor, identify each generator contributing waste to the disposal
container, and for discrete waste types (i.e., activated materials,
contaminated equipment, mechanical filters, sealed source/devices and wastes in
solidification/stabilization media), the identities and activities of individual
radionuclides contained on these waste types within the disposal container.
For each waste generator, provide the following:
A) The
volume of waste;
B) A
physical and chemical description of the waste, including the solidification
agent, if any;
C) The
total weight percentage of chelating agents for any waste containing more than
0.1 percent chelating agent by weight, plus the identity of the principal
chelating agent;
D) The
sorbing or solidification media, if any, and the identity of the solidification
media vendor and brand name if the media is claimed to meet stability
requirements in Section 340.1055(b); and
E) Radionuclide
identities and activities contained in the waste, the masses of U-233, U-235,
and plutonium in special nuclear material, and the masses of uranium and
thorium in source material if contained in the waste.
j) An
authorized representative of the licensee shall certify, by signing and dating
the shipment manifest, that the transported materials are properly classified,
described, packaged, marked, and labeled and are in proper condition for
transportation according to the requirements of USDOT regulations and this
Part. A collector, in signing the certification, is certifying that nothing
has been done to the collected waste that would invalidate the waste generator's
certification.
k) Any
licensee who transfers radioactive waste to a land disposal facility or a
licensed waste collector shall comply with the requirements in subsections
(k)(1) through (9). Any licensee who transfers waste to a licensed waste
processor for waste treatment or repackaging shall comply with the requirements
of subsections (k)(4) through (9). The licensee shall:
1) Prepare
all wastes so that the waste is classified according to Section 340.1052 and
meets the waste characteristics requirements in Section 340.1055;
2) Label
each disposal container (or transport package if potential radiation hazards
preclude labeling of the individual disposal container) of waste to identify
whether it is Class A waste, Class B waste, Class C waste, or greater than
Class C waste, in accordance with Section 340.1052;
3) Conduct
a quality assurance program to assure compliance with Sections 340.1052 and
340.1055 (the program shall include management evaluation of audits);
4) Prepare
the appropriate NRC Uniform Low-Level Radioactive Waste Manifest form as
required by this Part;
5) Forward
a copy or electronically transfer the Uniform Low-Level Radioactive Waste
Manifest to the intended consignee so that receipt of the manifest precedes the
low-level radioactive waste shipment, or the manifest is delivered to the
consignee with the waste at the time the waste is transferred to the consignee.
Using either or both of these methods is acceptable;
6) Include
NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of
the option chosen in subsection (k)(5);
7) Receive
acknowledgement of the receipt of the shipment in the form of a signed copy of
NRC Form 540;
8) Retain
a copy of or electronically store the Uniform Low-Level Radioactive Waste
Manifest and documentation of acknowledgement of receipt as the record of
transfer of licensed material as required by the Agency; and
9) For
any shipments or any part of a shipment for which acknowledgement of receipt
has not been received within the times set forth in this Part, conduct an
investigation in accordance with Section 340.1270.
l) Any
waste collector licensee who handles only prepackaged waste shall comply with
subsections (l)(1) and (2) and (l)(7) through (12). Any licensed waste
processor who treats or repackages waste shall comply with subsections (l)(1)
and (l)(3) through (12).
1) Acknowledge
receipt of the waste from the shipper within one week after receipt by
returning a signed copy of NRC Form 540 to the shipper;
2) Prepare
a new manifest to reflect consolidated shipments that meet the requirements of
this Part. The waste collector shall ensure that, for each container of waste
in the shipment, the manifest identifies the generator of that container of
waste;
3) Prepare
a new manifest that meets the requirements of this Part. Preparation of the
new manifest reflects that the processor is responsible for meeting these
requirements. For each container of waste in the shipment, the manifest shall
identify the waste generators, the preprocessed waste volume, and the other
information required in subsection (i);
4) Prepare
all wastes so that the waste is classified according to Section 340.1052 and
meets the waste characteristics requirements in Section 340.1055;
5) Label
each package of waste to identify whether it is Class A waste, Class B waste,
or Class C waste, in accordance with Sections 340.1052 and 340.1055;
6) Conduct
a quality assurance program to assure compliance with Sections 340.1052 and
340.1055 (the program shall include management evaluation of audits);
7) Forward
a copy or electronically transfer the Uniform Low-Level Radioactive Waste
Manifest to the intended consignee so that receipt of the manifest precedes the
low-level radioactive waste shipment, or the manifest is delivered to the
consignee with the waste at the time the waste is transferred to the
consignee. Using either or both of these methods is acceptable;
8) Include
NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of
the option chosen in subsection (l)(7);
9) Receive
acknowledgement of the receipt of the shipment in the form of a signed copy of
NRC Form 540;
10) Retain
a copy of or electronically store the Uniform Low-Level Radioactive Waste
Manifest and documentation of acknowledgement of receipt as the record of
transfer of licensed material as required by the Agency;
11) For
any shipments or any part of a shipment for which acknowledgement of receipt
has not been received within the times set forth in this Part, conduct an
investigation in accordance with Section 340.1270; and
12) Notify
the shipper and the Agency when any shipment or part of a shipment has not
arrived within 60 days after receipt of an advance manifest, unless notified by
the shipper that the shipment has been cancelled.
m) Any licensed land
disposal facility operator shall:
1) Acknowledge
receipt of low-level radioactive waste within 1 week after receipt by returning,
at a minimum, a signed copy of NRC Form 540 to the shipper. The shipper to be
notified is the licensee who last possessed the waste and transferred the waste
to the operator. If any discrepancy exists between materials listed on the
Uniform Low-Level Radioactive Waste Manifest and materials received, copies or
electronic transfer of the affected forms shall be returned indicating the
discrepancy;
2) Maintain
copies of all completed manifests until the Agency terminates the license; and
3) Notify
the shipper and the Agency when any shipment or part of a shipment has not
arrived within 60 days after receipt of an advance manifest, unless notified by
the shipper that the shipment has been cancelled.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1070 Compliance
with Environmental and Health Protection Regulations
Nothing in this Subpart K
relieves the licensee from complying with other applicable federal, State and
local regulations governing any other toxic or hazardous properties of
materials that are disposed of pursuant to this Subpart.
Section 340.1110 General
Provisions
a) Each licensee or registrant shall use the SI units becquerel,
gray, sievert and coulomb/kilogram or the special units curie, rad, rem and
roentgen, including multiples and subdivisions, and shall clearly indicate the
units of all quantities on records required by this Part.
b) The licensee or registrant shall make a clear distinction
among the quantities entered on the records required by this Part (e.g., total
effective dose equivalent, total organ dose equivalent, shallow dose
equivalent, lens dose equivalent, deep dose equivalent, committed effective
dose equivalent).
c) No licensee or registrant shall subtract radiation exposures
from official personnel monitoring records without the prior written approval
of the Agency.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1120 Records of
Radiation Protection Programs
a) Each licensee or registrant shall maintain records of the
radiation protection program required pursuant to Section 340.110 of this Part,
including:
1) The provisions of the program; and
2) Audits and other reviews of program content and
implementation.
b) The licensee or registrant shall retain the records required
by subsection (a)(1) of this Part until the Agency terminates each license or
registration for which the record is required. The licensee or registrant
shall retain the records required by subsection (a)(2) of this Section for 5
years after the record is made.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1130 Records of
Surveys and Calibrations
a) Each licensee or registrant shall maintain records showing the
results of surveys and calibrations required by Sections 340.510 and
340.960(b). The licensee or registrant shall retain these records for 5 years
after the record is made.
1) Records of surveys shall include:
A) The location and date of the survey and the model and serial
number of the instrument used to perform the survey;
B) The identity of the individual performing the survey; and
C) The results of the survey and any corrective actions that were
taken as a result.
2) For each survey instrument calibrated in accordance with Section
340.510(b), the licensee shall maintain the following records:
A) A copy of the licensee's own calibration procedures or a copy
of a license issued by the Agency, the U.S. Nuclear Regulatory Commission, an
Agreement State, or a Licensing State authorizing the person that performed the
calibrations to perform calibrations as a customer service; and
B) A record identifying the manufacturer, model, and serial number
of the instrument that was calibrated, the calibration results, the identity of
the individual who performed the calibration, and the date of the calibration.
3) Each licensee authorized to perform instrument calibrations
shall maintain a copy of each calibration document created in accordance with
subsection (a)(2)(B) and a copy of the procedures followed to perform that
calibration.
4) The licensee shall retain a record of each check required in
Section 340.510(c) for 5 years.
b) The licensee or registrant shall retain each of the following
records until the Agency terminates each license or registration for which the
record is required:
1) Records of the results of surveys to determine the dose from
external sources of radiation that are used, in the absence of or in
combination with individual monitoring data, in the assessment of individual
dose equivalents;
2) Records of the results of measurements and calculations that
are used to determine individual intakes of radioactive material and that are
used in the assessment of internal dose;
3) Records showing the results of air sampling, surveys, and
bioassays required pursuant to Section 340.730(a)(3)(A) and (B);
4) Records of the results of measurements and calculations used
to evaluate the release of radioactive effluents to the environment; and
5) Records from surveys describing the location and amount of
subsurface residual radioactivity identified at the site.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1135 Records of
Tests for Leakage or Contamination of Sealed Sources
a) Records of tests for leakage or contamination required by
Section 340.410 of this Part shall be kept in units of becquerel or microcurie
and maintained for inspection by the Agency for 5 years after the records are
made.
b) The records of tests for leakage and/or
contamination shall contain the manufacturer, model and serial number, if assigned,
of each source tested, the identity of each source radionuclide, the results
for each test sample expressed in Bq or µCi, the date the sample was collected,
the date the sample was analyzed, the identity of the individual who collected
the samples and the identity of the individual who analyzed the samples.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1140 Records of
Prior Occupational Dose
a) The licensee or registrant shall retain the records of prior
occupational dose and exposure history as specified in Section 340.250 of this
Part until the Agency terminates each pertinent license or registration
requiring this record. The licensee or registrant shall retain records used in
preparing the prior occupational dose and exposure history for 3 years after
the record is made.
b) Upon termination of the license or registration, the records
of prior occupational dose and exposure history shall be transferred to the Agency.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1150 Records of
Planned Special Exposures
a) For each use of the provisions of Section 340.260 of this Part
for planned special exposures, the licensee shall maintain records that
describe:
1) The exceptional circumstances requiring the use of a planned
special exposure;
2) The name of the management official who authorized the planned
special exposure and a copy of the signed authorization;
3) What actions were necessary;
4) Why the actions were necessary;
5) What precautions were taken to assure that doses were
maintained ALARA;
6) What individual and collective doses were expected to result;
and
7) The doses actually received in the planned special exposure.
b) The licensee shall retain the records until the Agency
terminates each license for which these records are required.
c) Upon termination of the license, the records of doses received
during planned special exposures shall be transferred to the Agency.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1160 Records of
Individual Monitoring Results
a) Recordkeeping Requirement. Each licensee or registrant shall
maintain records of doses received by all individuals for whom monitoring was
required pursuant to Section 340.520, and records of doses received during
planned special exposures, accidents, and emergency conditions. These records
shall include, when applicable:
1) The deep dose equivalent to the whole body, lens dose
equivalent, shallow dose equivalent to the skin, and shallow dose equivalent to
the extremities;
2) The estimated intake of radionuclides (see Section 340.220);
3) The committed effective dose equivalent assigned to the intake
of radionuclides;
4) The specific information used to calculate the committed
effective dose equivalent pursuant to Section 340.240(c);
5) The total effective dose equivalent when required by Section
340.220; and
6) The total of the deep dose equivalent and the committed dose
equivalent to the organ receiving the highest total dose.
b) Recordkeeping Frequency. The licensee or registrant shall
make entries of the records specified in subsection (a) at least annually.
c) Recordkeeping Format. The licensee or registrant shall
maintain the records specified in subsection (a) on NRC Form 5, in accordance
with the instructions for NRC Form 5, or in clear and legible records
containing all the information required by NRC Form 5.
d) The licensee or registrant shall maintain the records of dose
to an embryo/fetus with the records of dose to the declared pregnant woman.
The declaration of pregnancy, and the estimated date of conception, shall also
be kept on file, but may be maintained separately from the dose records.
e) The licensee or registrant shall retain each required form or
record until the Agency terminates each license or registration for which the
record is required.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1170 Records of
Dose to Members of the Public
a) Each licensee or registrant shall maintain records sufficient
to demonstrate compliance with the dose limit for individual members of the
public (see Sections 340.310 and 340.320 of this Part).
b) The licensee or registrant shall retain the records required
by subsection (a) of this Section until the Agency terminates each license or
registration for which the record is required.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1180 Records of
Waste Disposal
a) Each licensee shall maintain records of the disposal of
licensed materials made pursuant to Sections 340.1020 through 340.1052 and 340.1060
and 32 Ill. Adm. Code 601. Each licensee shall also maintain records of
disposal by burial in soil, including burials authorized before January 28,
1981, pursuant to 10 CFR 20.304.
AGENCY NOTE:
Prior to January 28, 1981, the U.S. Nuclear Regulatory Commission permitted
licensees to dispose of small quantities of licensed materials by burial in
soil without specific Nuclear Regulatory Commission authorization. This was
authorized pursuant to 10 CFR 20.304, which has been rescinded.
b) The licensee shall retain the records required by subsection
(a) until the Agency terminates each license for which the record is required.
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.1190 Records of
Testing Entry Control Devices for Very High Radiation Areas
a) Each licensee or registrant shall maintain records of tests
made pursuant to Section 340.630(b)(9) of this Part on entry control devices
for very high radiation areas. These records must include the date, time and
results of each such test of function.
b) The licensee or registrant shall retain the records required
by subsection (a) of this Section for 3 years after the record is made.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1195 Form of
Records (Repealed)
(Source: Repealed at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.1205 Notification of Credible Threats
Upon notification to or by any Federal, State or local law
enforcement agency or the U.S. Department of Homeland Security that radioactive
material in possession by the licensee is the subject of a credible threat, the
licensee shall:
a) follow the instructions
from the law enforcement agency; and
b) notify
the Agency within 1 hour by calling the Agency's 24-hour emergency number at
(217)782-7860 or (800)782-7860. This notification is required unless otherwise
instructed by the law enforcement agency.
AGENCY NOTE: "Credible threat" means any threat
to radioactive material that a licensee believes warrants notice to law
enforcement or any threat that law enforcement believes warrants notice to a
licensee.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1210 Reports of
Stolen, Lost, or Missing Sources of Radiation
a) Telephone Reports. Each licensee or registrant shall report
to the Agency by telephone at (217) 782-7860 each stolen, lost, or missing
source of radiation immediately after its absence becomes known to the licensee
or registrant. This requirement does not apply to sources of radiation that
are not required to be licensed or registered.
b) Written Reports. Each licensee or registrant required to make
a report pursuant to subsection (a) shall, within 30 days after making the
telephone report, make a written report to the Agency setting forth the
following information:
1) A description of the source of radiation involved, including
for radioactive material, the kind, quantity, and chemical and physical form;
and, for radiation machines, the type of unit, the manufacturer, model, and
serial number;
2) A description of the circumstances under which the loss or
theft occurred;
3) A statement of disposition, or probable disposition, of the
source of radiation involved;
4) Exposures of individuals to radiation, circumstances under
which the exposures occurred, and the possible total effective dose equivalent
to persons in unrestricted areas;
5) Actions that have been taken, or will be taken, to recover the
source of radiation; and
6) Procedures or measures that have been, or will be, adopted to
ensure against a recurrence of the theft or loss of sources of radiation.
c) Subsequent to filing the written report, the licensee or
registrant shall also report any additional substantive information on the loss
or theft within 30 days after the licensee or registrant learns of such
information.
d) The licensee or registrant shall prepare any report filed with
the Agency pursuant to this Section so that names of individuals who may have
received exposure to radiation are stated in a separate and detachable portion
of the report.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1220
Notification of Incidents
a) Immediate Notification. Notwithstanding any other
requirements for notification, each licensee or registrant shall immediately
report to the Agency discovery of an event that prevents immediate protective
actions necessary to avoid releases of radioactive material or doses in excess
of the regulatory limits, or each event involving a source of radiation
possessed by the licensee or registrant that may have caused or threatens to
cause any of the following conditions:
1) An individual to receive:
A) A total effective dose equivalent of 0.25 Sv (25 rem) or more;
or
B) A lens dose equivalent of 0.75 Sv (75 rem) or more; or
C) A shallow dose equivalent to the skin or extremities or a total
organ dose equivalent of 2.5 Gy (250 rad) or more; or
2) The release of radioactive material, inside or outside of a
restricted area, so that, had an individual been present for 24 hours, the
individual could have received an intake five times the ALI, except the
provisions of this subsection (a) do not apply to locations where personnel are
not normally stationed during routine operations, such as hot cells or process
enclosures.
b) 24 Hour Notification. Each licensee or registrant shall,
within 24 hours of discovery of the event, report to the Agency each event involving
loss of control of a licensed or registered source of radiation possessed by
the licensee or registrant that may have caused, or threatens to cause, any of
the following conditions:
1) An individual to receive, in a period of 24 hours:
A) A total effective dose equivalent exceeding 0.05 Sv (5 rem); or
B) A lens dose equivalent exceeding 0.15 Sv (15 rem); or
C) A shallow dose equivalent to the skin or extremities or a total
organ dose equivalent exceeding 0.5 Sv (50 rem); or
2) The release of radioactive material, inside or outside of a
restricted area, so that, had an individual been present for 24 hours, the individual
could have received an intake in excess of one occupational ALI, except the
provisions of this subsection (b) do not apply to locations where personnel are
not normally stationed during routine operations, such as hot cells or process
enclosures.
c) Additional 24 Hour Notifications for Licensees. Each licensee
shall notify the Agency within 24 hours after the discovery of any of the
following events involving radioactive material:
1) An unplanned contamination event that:
A) Requires access to the contaminated area by workers or the
public to be restricted for more than 24 hours by imposing radiological
controls in addition to those established by the licensee prior to the event or
by prohibiting entry into the area;
B) Involves a quantity of material greater than five times the
lowest annual limit on intake specified in 10 CFR 20, appendix B, published at
72 Fed. Reg. 55922, October 1, 2007, for the material; and
C) Results in access to the area being restricted for a reason
other than to comply with operating procedures established by the licensee or
to allow radionuclides with a half-life of less than 24 hours to decay prior to
decontamination.
2) An event in which equipment is disabled or fails to function
as designated when:
A) The equipment is required by regulation or license condition to
prevent releases or doses exceeding regulatory limits, or to mitigate the
consequences of an accident;
B) The equipment is required to be available and operable when it
is disabled or fails to function; and
C) No redundant equipment is available and operable to perform the
required safety function.
3) An event that requires unplanned medical treatment at a
medical facility of an individual with radioactive contamination on the
individual's clothing or body.
4) An unplanned fire or explosion damaging any licensed material
or any device, container, or equipment containing licensed material when:
A) The quantity of material involved is greater than five times
the lowest annual limit on intake specified in 10 CFR 20, appendix B, published
at 72 Fed. Reg. 55922, October 1, 2007, for the material; and
B) The damage affects the integrity of the licensed material or
its container.
d) Licensees or registrants shall make the reports required by
subsections (a) through (c) by initial contact by telephone to the Agency at
(217) 782-7860 and shall confirm the initial contact within 24 hours by
overnight letter or telefacsimile to the Agency.
e) The licensee or registrant shall prepare each written report
filed with the Agency pursuant to this Section so that names of individuals who
have received exposure to sources of radiation are stated in a separate and
detachable portion of the report.
f) The provisions of this Section do not apply to doses that
result from planned special exposures, provided such doses are within the
limits for planned special exposures and are reported pursuant to Section
340.1240.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
Section 340.1230 Reports of
Exposures, Radiation Levels and Concentrations of Radioactive Material
Exceeding the Constraints or Limits
a) Reportable Events. In addition to the notification required
by Section 340.1220 of this Part, each licensee or registrant shall submit a
written report to the Agency within 30 days after learning of any of the
following occurrences:
1) Incidents for which notification is required by Section
340.1220 of this Part; or
2) Doses in excess of any of the following:
A) The occupational dose limits for adults in Section 340.210 of
this Part; or
B) The occupational dose limits for a minor in Section 340.270 of
this Part; or
C) The limits for an embryo/fetus of a declared pregnant woman in
Section 340.280 of this Part; or
D) The limits for an individual member of the public in Section
340.310 of this Part; or
E) Any applicable limit in the license; or
F) The ALARA constraints for air emissions established pursuant
to Section 340.110(d) of this Part; or
3) Levels of radiation or concentrations of radioactive material
in:
A) A restricted area in excess of any applicable limit in the
license; or
B) An unrestricted area in excess of ten times any applicable
limit set forth in this Part or ten times any applicable limit set forth in the
license, whether or not involving exposure of any individual in excess of the
limits in Section 340.310.
b) Contents of Reports
1) Each report required by subsection (a) of this Section shall
include a description of the event, including the date, time and location of
the event, the manufacturer and model number of any equipment that failed or
malfunctioned and the identity, quantities and chemical forms of any
radionuclides involved. Each report shall also describe the extent of exposure
of individuals to radiation and radioactive material, including, as
appropriate:
A) Estimates of each individual's dose;
B) The levels of radiation and concentrations of radioactive
material involved;
C) The cause of the elevated exposures, dose rates or
concentrations; and
D) Corrective steps taken or planned to ensure against a
recurrence, including the schedule for achieving conformance with applicable
limits, generally applicable environmental standards and associated license
conditions.
2) Each report filed pursuant to subsection (a) of this Section
shall include for each individual exposed: the name, Social Security account
number and date of birth. With respect to the limit for the embryo/fetus in
Section 340.280 of this Part, the identifiers shall be those of the declared
pregnant woman. The report shall be prepared so that this information is
stated in a separate and detachable portion of the report.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1240 Reports of
Planned Special Exposures
The licensee shall submit a
written report to the Agency within 30 days following any planned special
exposure conducted in accordance with Section 340.260 of this Part, informing
the Agency that a planned special exposure was conducted and indicating the
date the planned special exposure occurred and the information required by
Section 340.1150 of this Part.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1250
Notifications and Reports to Individuals
a) Requirements for notification and reports to individuals of
exposure to radiation or radioactive material are specified in 32 Ill. Adm.
Code 400.130.
b) When a licensee or registrant is required by Section 340.1230 or
340.1240 to report to the Agency an exposure of an individual to radiation or
radioactive material, the licensee or registrant shall also notify the
individual. The notice shall be transmitted at a time not later than the
transmittal to the Agency and shall comply with the provisions of 32 Ill. Adm.
Code 400.130(a).
(Source: Amended at 35 Ill.
Reg. 934, effective December 30, 2010)
Section 340.1260 Reports of
Leaking or Contaminated Sealed Sources
The licensee shall file a report
within 5 days with the Agency if the test for leakage or contamination required
pursuant to Section 340.410 of this Part indicates a sealed source is leaking
or contaminated. The report shall describe the equipment involved, the test
results and the corrective action taken.
(Source: Amended at 29 Ill.
Reg. 20841, effective December 16, 2005)
Section 340.1270 Reports of
Missing Waste Shipments
Any shipment or part of a
shipment for which acknowledgement is not received within the times set forth
in Subpart K shall:
a) Be
investigated by the shipper if the shipper has not received notification or
receipt within 20 days after transfer; and
b) Be
traced and reported. The investigation shall include tracing the shipment and each
licensee who conducts a trace investigation shall file a written report with
the Agency within 2 weeks after completion of the investigation.
(Source: Amended at 47 Ill.
Reg. 9163, effective June 22, 2023)
