TITLE 32: ENERGY
CHAPTER II: DEPARTMENT OF NUCLEAR SAFETY
SUBCHAPTER b: RADIATION PROTECTION
PART 340
STANDARDS FOR PROTECTION AGAINST RADIATION
SUBPART A: GENERAL
Section
340.1000 Purpose and Scope
340.1010 Radiation Dose Standards for Individuals in Restricted Areas
340.1020 Determination of Accumulated Dose
340.1030 Exposure to Concentrations of Radioactive Material in Air in
Restricted Areas
340.1040 Exposure of Minors
340.1050 Permissible Levels of Radiation for External Sources in
Unrestricted Areas
340.1060 Concentration of Radioactivity in Effluents to Unrestricted
Areas
340.1070 Orders Requiring Furnishing of Bioassay Service
SUBPART B: PRECAUTIONARY PROCEDURES
Section
340.2010 Surveys
340.2020 Personnel Monitoring
340.2030 Caution Signs, Labels, and Signals
340.2040 Exceptions from Posting and Labeling Requirements
340.2050 Instruction of Personnel
340.2060 Storage and Control of Sources of Radiation
340.2070 Procedures for Picking Up, Receiving, and Opening Packages
SUBPART C: WASTE DISPOSAL
Section
340.3010 General Requirements
340.3020 Method of Obtaining Approval of Proposed Disposal Procedures
340.3030 Disposal by Release Into Sanitary Sewage Systems
340.3040 Land Disposal
340.3050 Disposal by Incineration
340.3060 Disposal of Specific Wastes
340.3070 Classification of Radioactive Waste for Land Disposal
340.3080 Radioactive Waste Characteristics
340.3090 Labeling
340.3110 Transfer for Disposal and Manifests
SUBPART D: RECORDS, MONITORING AND DISPOSAL
Section
340.4010 Records of Surveys, Radiation Monitoring, and Disposal
340.4020 Reports of Theft or Loss of Sources of Radiation
340.4030 Notification of Incidents
Section
340.4040 Reports to Former Employees and Others of Exposure to
Radiation (Repealed)
340.4050 Reports of Overexposures and Excessive Levels and
Concentrations
340.4060 Notice to Employees and Others of Exposure to Radiation
(Repealed)
340.4070 Vacating Premises
340.4080 Notifications and Reports to Individuals
340.4090 Removal of Radioactive Contamination
APPENDIX A Concentrations in Air and Water Above Natural Background
APPENDIX B Quantities for use with 340.2030 and 340.3030 Material and
Microcuries
APPENDIX C Decontamination Guides
ILLUSTRATION A Radiation Symbol
AUTHORITY: Implementing and authorized by the Radiation Protection Act (Ill.
Rev. Stat. 1985, ch. 111�, pars. 211 et seq.).
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.
SUBPART A: GENERAL
Section 340.1000 Purpose and Scope
a) This Part establishes standards for protection against radiation
hazards. Except as otherwise specifically provided, this Part
applies to all licensees and registrants. It is the purpose of
the regulations in this Part to control the possession, use, and
transfer of sources of radiation by any licensee or registrant in
such a manner that the total dose to an individual does not exceed
the standards of radiation protection prescribed in this Part.
Nothing in this Part shall be interpreted as limiting the
intentional exposure of patients to radiation for the purpose of
medical diagnosis or therapy.
b) In addition to complying with the requirements set forth in this
Part, every reasonable effort should be made to maintain radiation
exposures, and releases of radioactive materials in effluents to
unrestricted areas, as low as is reasonably achievable. The term
"as low as is reasonably achievable" means as low as is reasonably
achievable taking into account the state of technology, and the
economics of improvements in relation to benefits to the public
health and safety, and other societal and socioeconomic consider-
ations, and in relation to the utilization of ionizing radiation
in the public interest.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1010 Radiation Dose Standards for Individuals in Restricted
Areas*
a) In accordance with the provisions of Section 340.1020(a), and
except as provided in Section 340.1010(b), no licensee or
registrant shall possess, use, receive, or transfer sources of
radiation in such a manner as to cause any individual in a
restricted area to receive in any period of 1 calendar quarter
from all sources of radiation a total occupational dose in excess
of the standards specified as follows:
Rems (Sv) per
Calendar Quarter
Whole body; head and trunk; active
blood-forming organs; lens of eyes;
or gonads ................. 1 1/4 (12.5 mSv)
Hands and forearms;
feet and ankles ........... 18 3/4 (187.5 mSv)
Skin of whole body ........ 7 1/2 (75 mSv)
b) A licensee or registrant may permit an individual in a restricted
area to receive a total occupational dose to the whole body
greater than that permitted under Section 340.1010(a), provided:
1) during any calendar quarter, the total occupational dose to
the whole body shall not exceed 3 rems (30 mSv);
2) the dose to the whole body, when added to the accumulated
occupational dose to the whole body, shall not exceed 5(N-
18) rems (50(N-18) mSv) where "N" equals the individual's
age in years at his last birthday; and
3) the licensee or registrant has determined the individual's
accumulated occupational dose to the whole body on
Department of Nuclear Safety (Department) Form KLA.002, or
on a clear and legible record containing all the information
required in that form and has otherwise complied with the
requirements of Section 340.1020. As used in Section
340.1010(b), "dose to the whole body" shall be deemed to
include any dose to the whole body, gonads, active blood-
forming organs, head and trunk, or lens of eye.
*AGENCY NOTE: For determining the doses specified in
Section 340.1010, a dose from X or gamma rays up to 10 MeV
may be assumed to be equivalent to the exposure measured by
a properly calibrated appropriate instrument in air at or
near the body surface in the region of the highest dose
rate.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1020 Determination of Accumulated Dose
a)
1) Each licensee or registrant shall require any individual,
prior to first entry of the individual into the licensee's
or registrant's restricted area during each employment or
work assignment under such circumstances that the individual
will receive or is likely to receive in any period of 1
calendar quarter an occupational dose in excess of 25
percent of the applicable standards specified in Sections
340.1010(a) and 340.1040(a), to disclose in a written,
signed statement, either:
A) that the individual had no prior occupational dose
during the current calendar quarter, or
B) the nature and amount of any occupational dose which
the individual may have received during the
specifically identified current calendar quarter, from
sources of radiation possessed or controlled by other
persons.
2) Each licensee or registrant shall maintain records of such
statements until the Department authorizes disposition.
Such disposition of records will be authorized by the
Department only if the licensee or registrant establishes to
the satisfaction of the Department that the records do not
contain accurate information concerning occupational dose or
the records are no longer required to establish compliance
with this section.
b) Before permitting, pursuant to Section 340.1010(b), any individual
in a restricted area to receive an occupational radiation dose in
excess of the standards specified in Section 340.1010(a), each
licensee or registrant shall:
1) obtain a certificate on Department Form KLA.002 or on a
clear and legible record containing all the information
required in that form, signed by the individual, showing
each period of time after the individual attained the age of
18 in which the individual received an occupational dose of
radiation; and
2) calculate on Department Form KLA.002, in accordance with the
instructions appearing therein, or on a clear and legible
record containing all the information required in that form,
the previously accumulated occupational dose received by the
individual and the additional dose allowed for that
individual under Section 340.1010(b).
c)
1) In the preparation of Department Form KLA.002, or a clear
and legible record containing all the information required
in that form, the licensee or registrant shall make a
reasonable effort to obtain reports of the individual's
previously accumulated occupational dose. For each period
for which the licensee or registrant obtains such reports,
he shall use the dose shown in the report in preparing the
form. In any case where a licensee or registrant is unable
to obtain reports of the individual's occupational dose for
a previous complete calendar quarter, it shall be assumed
that the individual has received the occupational dose
specified in whichever of the following columns apply:
Column 1 Column 2
Assumed Dose in Assumed Dose in
Rems (mSv) for Rems (mSv) for
Calendar Quarters Calendar Quarters
Prior to January Beginning on or
1, 1961. After January 1,
1961.
Part of Body
Whole body, gonads,
active blood-forming
organs, head and trunk,
lens of eye ............... 3 3/4 (37.5 mSv) 1 1/4 (12.5 mSv)
2) The licensee or registrant shall retain and preserve records
used in preparing Department Form KLA.002 until the
Department authorizes their disposition. Such disposition
of records will be authorized by the Department only when
the records are no longer required to establish compliance
with this section. If calculation of the individual's
accumulated occupational dose for all periods prior to
January 1, 1961, yields a result higher than the applicable
accumulated dose value for the individual as of that date,
as specified in Section 340.1010(b)(2), the excess may be
disregarded.
d) Vacation - A person shall not be granted time off from work as a
substitute for adequate protection against exposure to radiation.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1030 Exposure to Concentrations of Radioactive Material in Air in
Restricted Areas
a)
1) No licensee or registrant shall possess, use, or transfer
radioactive material in such a manner as to permit any
individual in a restricted area to inhale a quantity of
radioactive material in any period of 1 calendar quarter
greater than the quantity which would result from inhalation
for 40 hours per week for 13 weeks at uniform concentrations
of radioactive material in air specified in Appendix A, Table
I, Column 1, of this Part*. If the radioactive material is of
such form that intake by absorption through the skin is
likely, individual exposures to radioactive material shall be
controlled so that the uptake of radioactive material by any
organ from either inhalation or absorption or both routes of
intake** in any calendar quarter does not exceed that which
would result from inhaling such radioactive material for 40
hours per week for 13 weeks at uniform concentrations
specified in Appendix A, Table I, Column 1, of this Part.
*AGENCY NOTE: Since the concentration specified for tritium
oxide vapor assumes equal intakes by skin absorption and
inhalation, the total intake permitted is twice that which
would result from inhalation alone at the concentration
specified for H-3(S) in Appendix A, Table I, Column 1, of this
Part for 40 hours per week for 13 weeks.
For radon-222, the limiting quantity is that inhaled in a
period of one calendar year. For radioactive material
designated "Sub" in the "Isotope" column of the table, the
concentration value specified is based upon exposure to the
material as an external radiation source. Individual
exposures to these materials may be accounted for as part of
the limitation on individual dose in Section 340.1010. These
nuclides shall be subject to the precautionary procedures
required by Section 340.1030(b)(1).
Multiply the concentration values specified in Appendix
A, Table I, Column 1, of this Part by 6.3 x 108 milliliters to
obtain the quarterly quantity limit. Multiply the
concentration value specified in Appendix A, Table I, Column
1, of this Part by 2.5 x 109 milliliters to obtain the annual
quantity limit for Rn-222.
**AGENCY NOTE: Significant intake by ingestion or injection
is presumed to occur only as a result of circumstances such as
accident, inadvertence, poor procedure, or similar special
conditions. Such intakes must be evaluated and accounted for
by techniques and procedures as may be appropriate to the
circum-stances of the occurrence. Exposures so evaluated
shall be included in determining whether the limitation on
individual exposures in Section 340.1030(a)(1) has been
exceeded.
Regulatory guidance on assessment of individual intakes
of radioactive material is given in U.S. Nuclear Regulatory
Commission Regulatory Guide 8.9, "Acceptable Concepts, Models,
Equations and Assumptions for a Bioassay Program." Single
copies of Regulatory Guide 8.9 are available from the Office
of Standards Development, U.S. Nuclear Regulatory Commission,
Washington, D.C. 20555, upon written request.
2) No licensee or registrant shall possess, use, or transfer mix-
tures of U-234, U-235, and U-238 in soluble form in such a
manner as to permit any individual in a restricted area to
inhale a quantity of such material in excess of the intake
limits specified in Appendix A, Table I, Column 1, of this
Part. If such soluble uranium is of a form such that
absorption through the skin is likely, individual exposures to
such material shall be controlled so that the uptake of such
material by any organ from either inhalation or absorption or
both routes of intake* does not exceed that which would result
from inhaling such material at the limits specified in
Appendix A, Table I, Column 1, of this Part and AGENCY NOTE
under Section 340.1030(a) (1).
*AGENCY NOTE: Significant intake by ingestion or injection is
presumed to occur only as a result of circumstances such as
accident, inadvertence, poor procedure, or similar special
conditions. Such intakes must be evaluated and accounted for
by techniques and procedures as may be appropriate to the
circumstances of the occurrence. Exposures so evaluated shall
be included in determining whether the limitation on
individual exposures in Section 340.1030(a)(1) has been
exceeded.
3) For purposes of determining compliance with the requirements
of Section 340.1030, the licensee or registrant shall measure
concentrations of radioactive material in air for purposes of
detecting and evaluating airborne radioactivity in restricted
areas, and shall measure radioactivity in the body,
radioactivity excreted from the body, or any combination of
such measurements as may be necessary for timely detection and
assessment of intakes of radioactivity by exposed individuals.
For purposes of these assessments, it shall be assumed that an
individual inhales radioactive material at the airborne
concentration in which he is present unless he uses
respiratory protective equipment pursuant to Section
340.1030(c). If an individual intake is less than that which
would result from inhalation for 2 hours, in any one day, or
for 10 hours in any one week at uniform concentrations
specified in Appendix A, Table I, Column 1 of this Part, it
need not be included in such assessment, provided that for any
assessment in excess of these amounts, the entire amount must
be included.
b) Precautionary Measures:
1) The licensee or registrant shall, as a precautionary
procedure, use process or other engineering controls, to the
extent practicable, to limit concentrations of radioactive
material in air to levels below those which delimit an
airborne radioactivity area as defined in 32 Ill. Adm. Code
310.20.
2) When it is impracticable to apply process or other engineering
controls to limit concentrations of radioactive material in
air below those defined in 32 Ill. Adm. Code 310.20, other
precautionary procedures, such as increased surveillance,
limitation of working times, or provision of respiratory
protective equipment, shall be used to maintain intake of
radioactive material by any individual within any period of
seven consecutive days as far below that intake of radioactive
material which would result from inhalation of such material
for 40 hours at the uniform concentrations specified in
Appendix A, Table I, Column 1, of this Part as is reasonably
achievable. Whenever the intake of radioactive material by
any individual exceeds this 40-hour control measure, the
licensee or registrant shall make such evaluations and take
such actions as are necessary to assure against recurrence.
The licensee or registrant shall maintain records of such
occurrences, evaluations, and actions taken in a clear and
readily identifiable form suitable for summary review and
evaluation.
c) When respiratory protective equipment is used to limit the
inhalation of airborne radioactive material pursuant to Section
340.1030(b)(2), the licensee or registrant may make allowance for
such use in estimating exposures of individuals to such material
provided that such equipment is used and exposures are evaluated as
stipulated in Section 20.103(c) of 10 CFR 20, revised as of January
1, 1985, exclusive of subsequent amendments or editions. A copy of
10 CFR 20 is available for public inspection at the Department of
Nuclear Safety.
d) Unless otherwise authorized by the Department, the licensee or
registrant shall not assign protection factors in excess of those
specified in Appendix A of 10 CFR 20 in selecting and using
respiratory protective equipment.* The Department may authorize a
licensee to use higher protection factors on receipt of an
application providing that the applicant:
1) describes the situation for which a need exists for higher
protection factors; and
2) demonstrates that the respiratory protective equipment will
provide these higher protection factors under the proposed
conditions of use.
*AGENCY NOTE: The reference to 10 CFR 20 is to the version revised
as of January 1, 1985, exclusive of subsequent amendments or
editions. A copy of 10 CFR 20 is available for public inspection
at the Department of Nuclear Safety.
e) Where equipment of a particular type has not been tested and
certified, or had certification extended by the National Institute
for Occupational Safety and Health/Mine Safety and Health Adminis-
tration (NIOSH/MSHA), or where there is no existing schedule for
test and certification of certain equipment, the licensee or
registrant shall not make allowance for this equipment without
specific authorization by the Department. An application for this
authorization must include a demonstration by testing, or on the
basis of reliable test information, that the material and
performance characteristics of the equipment are capable of
providing the proposed degree of protection under anticipated
conditions of use.
f) Only equipment that has been specifically certified or had certifi-
cation extended for emergency use by NIOSH/MSHA shall be used as
emergency devices.
g) The licensee or registrant shall notify, in writing, the Department
at least 30 days before the date that respiratory protection
equipment is first used under the provisions of Section 340.1030.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1040 Exposure of Minors*
a) No licensee or registrant shall possess, use, or transfer sources
of radiation in such a manner as to cause any individual within a
restricted area, who is under 18 years of age, to receive in any
period of one calendar quarter from all sources of radiation in
such licensee's or registrant's possession a dose in excess of 10
percent of the standards specified in Section 340.1010(a).
b) No licensee or registrant shall possess, use, or transfer
radioactive material in such a manner as to cause any individual
within a restricted area, who is under 18 years of age, to be
exposed to air-borne radioactive material in an average
concentration in excess of the limits specified in Appendix A,
Table II, of this Part. For purposes of this paragraph,
concentrations may be averaged over periods not greater than a
week.
c) The provisions of Section 340.1030(b)(2) and 340.1030(c) shall
apply to exposures subject to Section 340.1040(b) except that the
references in Sections 340.1030(b)(2) and 340.1030(c) to Appendix
A, Table I, Column 1 of this Part shall be deemed to be references
to Appendix A, Table II, Column 1, of this Part.
*AGENCY NOTE: For determining the doses specified in this Section,
a dose from x or gamma rays up to 10 Mev may be assumed to be
equivalent to the exposure measured by a properly calibrated
appropriate instrument in air at or near the body surface in the
region of the highest dose rate.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1050 Permissible Levels of Radiation from External Sources in
Unrestricted Areas*
a) Except as authorized by the Department pursuant to Section
340.1050(b), no licensee or registrant shall possess, use, or
transfer sources of radiation in such a manner as to create in any
unrestricted area from such sources of radiation in his possession:
1) radiation levels which, if an individual were continuously
present in the area, could result in his receiving a dose in
excess of 2 millirems (0.02 mSv) in any one hour; or
2) radiation levels which, if an individual were continuously
present in the area, could result in his receiving a dose in
excess of 100 millirems (1.0 mSv) in any seven consecutive
days.
b) Any person may apply to the Department for proposed limits upon
levels of radiation in unrestricted areas in excess of those
specified in Section 340.1050(a) resulting from the applicant's
possession or use of sources of radiation. Such applications
should include information as to anticipated average radiation
levels and anticipated occupancy times for each unrestricted area
involved. The Department will approve the proposed limits if the
applicant demonstrates to the satisfaction of the Department that
the proposed limits are not likely to cause any individual to
receive a dose to the whole body in any period of one calendar year
in excess of 0.5 rem (5.0 mSv).
*AGENCY NOTE: It is the intent of Section 340.1050 to limit
radiation levels so that it is unlikely that individuals in
unrestricted areas would receive a dose to the whole body in excess
of 0.5 rem (5.0 mSv) in any one year. If in specific instances, it
is determined by the Department that this intent is not met, the
Department may, pursuant to 32 Ill. Adm. Code 310.70 impose such
additional requirements on the licensee or registrant as may be
necessary to meet the intent.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1060 Concentration of Radioactivity in Effluents to Unrestricted
Areas
a) A licensee or registrant shall not possess, use, or transfer
licensed material so as to release to an unrestricted area
radioactive material in concentrations which exceed the limits
specified in Appendix A, Table II, of this Part, except as
authorized pursuant to Sections 340.3020 or 340.1060(b). For
purposes of Section 340.1060, concentrations may be averaged over a
period of not greater than 1 year.
b) An application for a license or amendment may include proposed
limits higher than those specified in Section 340.1060(a). The
Department will approve the proposed limits if the applicant
demonstrates:
1) that the applicant has made a reasonable effort to minimize
the radioactivity contained in effluents to unrestricted
areas; and
2) that it is not likely that radioactive material discharged in
the effluent would result in the exposure of an individual to
concentrations of radioactive material in air or water
exceeding the limits specified in Appendix A, Table II, of
this Part.
c) An application for higher limits pursuant to Section 340.1060(b)
shall include information demonstrating that the applicant has made
a reasonable effort to minimize the radioactivity discharged in
effluents to unrestricted areas, and shall include, as pertinent:
1) information as to flow rates, total volume of effluent, peak
concentration of each radionuclide in the effluent, and
concentration of each radionuclide in the effluent averaged
over a period of 1 year at the point where the effluent leaves
a stack, tube, pipe, or similar conduit;
2) a description of the properties of the effluents, including;
A) chemical composition,
B) physical characteristics, including suspended solids
content in liquid effluents, and nature of gas or aerosol
for air effluents,
C) the hydrogen ion concentrations (pH) of liquid effluents;
and,
D) the size range of particulates in effluents released into
air;
3) a description of the anticipated human occupancy in the
unrestricted area where the highest concentration of
radioactive material from the effluent is expected, and, in
the case of a
river or stream, a description of water uses downstream from
the point of release of the effluent;
4) information as to the highest concentration of each
radionuclide in an unrestricted area, including anticipated
concentrations averaged over a period of 1 year:
A) in air at any point of human occupancy, or
B) in water at points of use downstream from the point of
release of the effluent;
5) the background concentration of radionuclides in the receiving
river or stream prior to the release of liquid effluent;
6) a description of the environmental monitoring equipment,
including sensitivity of the system, and procedures and calcu-
lations to determine concentrations of radionuclides in the
unrestricted area and possible reconcentrations of radionu-
clides; and
7) a description of the waste treatment facilities and procedures
used to reduce the concentration of radionuclides in effluents
prior to their release.
d) For the purposes of Section 340.1060, the concentration limits in
Appendix A, Table II, of this Part shall apply at the boundary of
the restricted area. The concentration of radioactive material
discharged through a stack, pipe, or similar conduit may be
determined with respect to the point where the material leaves the
conduit. If the conduit discharges within the restricted area, the
concentration at the boundary may be determined by applying
appropriate factors for dilution, dispersion, or decay between the
point of discharge and the boundary.
e) In addition to limiting concentrations in effluent streams, the
Department may limit quantities of radioactive material released in
air or water during a specified period of time if it appears that
the daily intake of radioactive material from air, water, or food
by a suitable sample of an exposed population group, averaged over
a period not exceeding 1 year, would otherwise exceed the daily
intake resulting from continuous exposure to air or water
containing one-third (1/3) the concentration of radioactive
material specified in Appendix A, Table II, of this Part.
f) The provisions of Section 340.1060 do not apply to disposal of
radioactive material into sanitary sewage systems, which is
governed by Section 340.3030.
g) In addition to the other requirements of this Part, licensees or
registrants engaged in uranium fuel cycle operations shall also
comply with the provisions of 40 CFR 190, "Environmental Radiation
Protection Standard for Nuclear Power Operations", revised as of
July 1, 1984, exclusive of subsequent amendments or editions.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.1070 Orders Requiring Furnishing of Bioassay Services
Where necessary or desirable in order to aid in determining the extent of an
individual's exposure to concentrations of radioactive material, the Depart-
ment may incorporate provisions in the license or issue an order requiring a
licensee or registrant to make available to the individual appropriate bio-
assay services and to furnish a copy of the reports of such services to the
Department.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
SUBPART B: PRECAUTIONARY PROCEDURES
Section 340.2010 Surveys
a) Each licensee or registrant shall make or cause to be made such
surveys as may be necessary for him to establish compliance with
this Part.
b) In addition, each licensee or registrant shall make or cause to be
made such surveys as are reasonable under the circumstances to
evaluate the extent of radiation hazards that may be present.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2020 Personnel Monitoring
a) Each licensee or registrant shall supply appropriate personnel
monitoring equipment to, and shall require the use of such
equipment by:
1) Each individual who enters a restricted area under such
circumstances that he receives, or is likely to receive, a
dose in any calendar quarter in excess of 25 percent of the
applicable value specified in Section 340.1010(a).
2) Each individual under 18 years of age who enters a restricted
area under such circumstances that he receives, or is likely
to receive, a dose in any calendar quarter in excess of 5
percent of the applicable value specified in Section
340.1010(a).
3) Each individual who enters a high radiation area.
b) At the present time, monitoring for compliance with Section
340.2020 shall be by film badge and/or thermoluminescent dosimetry
only. However, the Department reserves the right to approve
additional monitoring systems.*
*AGENCY NOTE: Monitoring devices used to estimate whole body
exposure normally should be worn on the chest or abdomen. When a
protective apron is worn (e.g. during fluoroscopy), particular care
should be taken in choosing the location of the monitoring device
and in interpreting its reading. If only a single monitor is worn
in conjunction with protective apparel, it should be worn on the
front collar outside the protective lead apron since this is the
region of the total body which receives the most exposure.
c) Dosimetry of the instant reading type may also be required
depending upon the likelihood of an immediate hazard to life or
health of personnel.
d) Blood counts shall not be used as a substitute for physical means
of personnel monitoring.
e) All personnel dosimeters, except extremity dosimeters and pocket
ionization chambers, that require processing to yield a dose
equivalent and that are supplied by licensees to comply with
paragraph (a) of this section:
1) shall be processed by a processor holding a current personnel
dosimetry accreditation certificate from the National
Voluntary Laboratory Accreditation Program of the National
Bureau of Standards in accordance with accreditation criteria
established in 15 CFR 7b, revised as of January 1, 1985, in
conformity with National Standard for Dosimetry Testing ANSI
N13.11-1983, 1983 edition*, and
2) shall be approved in this accreditation process for the type
of radiation or radiations from Table 1 of ANSI N13.11-1983,
1983 edition*, that most closely approximate the type of
radiation or radiations for which the individual wearing the
dosimeter is monitored.
*AGENCY NOTE: This Section incorporates the criteria in the
January 1, 1985 revision of 15 CFR 7b, and in ANSI N13.11-
1983, 1983 edition, exclusive of subsequent amendments or
editions. Copies of both 15 CFR 7b and ANSI N13.11-1983 are
available for public inspection at the Department of Nuclear
Safety. Copies of ANSI N13.11-1983 can be obtained directly
from the American National Standards Institute, 1430 Broadway,
New York, New York 10018.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2030 Caution Signs, Labels, and Signals
a) General
1) Except as otherwise authorized by the Department, symbols pre-
scribed by Section 340.2030 shall use the conventional
radiation caution colors (magenta or purple on yellow
background). The symbol prescribed by this Section is the
conventional three-blade design (as depicted in Illustration
A):
RADIATION SYMBOL
A) Cross-hatch area is to be magenta or purple.
B) Background is to be yellow.
2) In addition to the contents of signs and labels prescribed in
this Section, a licensee or registrant may provide on or near
such signs and labels any additional information which may be
appropriate in aiding individuals to minimize exposure to
radiation.
b) Radiation Areas. Each radiation area shall be conspicuously posted
with a sign or signs bearing the radiation caution symbol and the
words:
CAUTION *
RADIATION AREA
*AGENCY NOTE: Or "Danger."
c) High Radiation Areas.
1) Each high radiation area shall be conspicuously posted with a
sign or signs bearing the radiation caution symbol and the
words:
CAUTION *
HIGH RADIATION AREA
*AGENCY NOTE: Or "Danger."
2) Each entrance or access point to a high radiation area shall
be:
A) equipped with a control device which shall cause the
level of radiation to be reduced below that at which an
individual might receive a dose of 100 millirems (1.0
mSv) in 1 hour upon entry into the area; or
B) equipped with a control device which shall energize a
conspicuous visible or audible alarm signal in such a
manner that the individual entering the high radiation
area and the licensee or a supervisor of the activity are
made aware of the entry; or
C) maintained locked except during periods when access to
the area is required, with positive control over each
individual entry.
3) The controls required by Section 340.2030(c)(2) shall be
established in such a way that no individual will be prevented
from leaving a high radiation area.
4) In the case of a high radiation area established for a period
of 30 days or less, direct surveillance to prevent
unauthorized entry may be substituted for the controls
required by Section 340.2030(c)(2).
5) Any licensee or registrant may apply to the Department for
approval of methods not included in Section 340.2030(c)(2) and
(4) for controlling access to high radiation areas. The
Department will approve the proposed alternatives if the
licensee or registrant demonstrates that the alternative
methods of control will prevent unauthorized entry into a high
radiation area, and that the requirement of Section
340.2030(c)(3) is met.
6) Each area in which there may exist radiation levels in excess
of 500 rems (5.0 Sv) in 1 hour at 1 meter from a sealed
radioactive source that is used to irradiate materials shall
have entry control devices and alarms meeting the criteria
specified in Section 20.203(c)(6) of 10 CFR 20, revised as of
January 1, 1985, exclusive of subsequent amendments or
editions. A copy of 10 CFR 20 is available for public
inspection at the Department of Nuclear Safety.
7) The requirements of Section 340.2030(c)(6) shall not apply to
radioactive sources that are used in teletherapy, industrial
radiography, or in completely self-contained irradiators.
Licensees with, or applicants for, licenses for radiation
sources that are within the purview of Section 340.2030(c)(6),
and that must be used in a variety of positions or in peculiar
locations, such as open fields or forests, that make it
impracticable to comply with certain requirements of Section
340.2030 (c)(6), such as those for the automatic control of
radiation levels, may apply to the Director, Illinois
Department of Nuclear Safety for approval, prior to use of
safety measures that are alternative to those specified in
Section 340.2030(c) (6), and that will provide at least an
equivalent degree of personnel protection in the use of such
sources. At least one of the alternative measures must
include an entry-preventing interlock control based on a
physical measurement of radiation that assures the absence of
high radiation levels before an individual can gain access to
an area where such sources are used.
d) Airborne Radioactivity Areas. Each airborne radioactivity area
shall be conspicuously posted with a sign or signs bearing the
radiation caution symbol and the words:
CAUTION *
AIRBORNE RADIOACTIVITY AREA
*AGENCY NOTE: Or "Danger."
e) Additional Requirements.
1) Each area or room in which any radioactive material, other
than natural uranium or thorium, is used or stored in an
amount exceeding 10 times the quantity of radioactive material
specified in Appendix B of this Part shall be conspicuously
posted with a sign or signs bearing the radiation caution
symbol and the words:
CAUTION *
RADIOACTIVE MATERIAL
*AGENCY NOTE: Or "Danger."
2) Each area or room in which natural uranium or thorium is used
or stored in an amount exceeding 100 times the quantity
specified in Appendix B of this Part shall be conspicuously
posted with a sign or signs bearing the radiation caution
symbol and the words:
CAUTION *
RADIOACTIVE MATERIAL
*AGENCY NOTE: Or "Danger."
f) Containers.
1) Except as provided in Section 340.2030(f)(3), each container
of radioactive material shall bear a durable, clearly visible
label identifying the radioactive contents.
2)
A) A label required pursuant to Section 340.2030(f)(1) shall
bear the radiation caution symbol and the words:
CAUTION *
RADIOACTIVE MATERIAL
*AGENCY NOTE: Or "Danger."
B) It shall also provide sufficient information* to permit
individuals handling or using the containers, or working
in the vicinity thereof, to take precautions to avoid or
minimize exposures.
*AGENCY NOTE: As appropriate, the information will
include radiation levels, kinds of material, estimate of
activity, date for which activity is estimated, etc.
3) Notwithstanding the provisions of Section 340.2030(f)(1),
labeling is not required:
A) for containers that do not contain radioactive material
in quantities greater than the applicable quantities
listed in Appendix B of this Part;
B) for containers containing only natural uranium or thorium
in quantities no greater than 10 times the applicable
quantities listed in Appendix B of this Part;
C) for containers that do not contain radioactive material
in concentrations greater than the applicable
concentrations listed in Appendix A, Table I, Column 2 of
this Part;
D) for containers when they are attended by an individual
who takes the precautions necessary to prevent the
exposure of any individual to radiation or radioactive
material in excess of the limits established by the
regulations in this Part;
E) for containers when they are in transport and packaged
and labeled in accordance with regulations published by
the U.S. Department of Transportation;
F) for containers which are accessible only to individuals
authorized to handle or use them* or to work in the
vicinity thereof, provided that the contents are
identified to such individuals by a readily available
written record; and
*AGENCY NOTE: For example, containers in locations such
as water-filled canals, storage vaults, or hot cells.
G) for manufacturing and process equipment such as piping
and tanks.
4) Each licensee or registrant shall, prior to disposal of an
empty uncontaminated container to unrestricted areas, remove
or deface the radioactive material label or otherwise clearly
indicate that the container no longer contains radioactive
material.
g) All radiation machines shall be labeled in a manner which cautions
individuals that radiation is produced when the machine is being
operated.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2040 Exceptions from Posting and Labeling Requirements
Notwithstanding the provisions of Section 340.2030:
a) 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 12 inches (30.5 cm) from the surface of the source container
or housing does not exceed 5 millirems per hour (0.05 mSv/h).
b) Rooms or other areas in hospitals are not required to be posted
with caution signs, and control of entrance or access thereto
pursuant to Section 340.2030(c) is not required because of the
presence of patients containing radioactive material, provided that
there are hospital personnel available who are responsible for
taking the precautions necessary to prevent the exposure of any
individual to radiation or radioactive material in excess of the
limits established in the regulations of this Part.
c) Caution signs are not required to be posted in areas or rooms con-
taining radioactive material for periods of less than 8 hours
provided that:
1) the material is constantly attended during such periods by an
individual who shall take the precautions necessary to prevent
the exposure of any individual to radiation or radioactive
material in excess of the limits established in this Part, and
2) such area or room is subject to the licensee's or registrant's
control.
d) A room or other area is not required to be posted with a caution
sign, and control is not required for each entrance or access point
to a room or other area which is a high radiation area solely
because of the presence of radioactive material prepared for
transport and packaged and labeled in accordance with regulations
of the U.S. Department of Transportation.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2050 Instruction of Personnel
Instructions required for individuals working in or frequenting any portion of
a restricted area are specified in 32 Ill. Adm. Code 400.120.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2060 Storage and Control of Sources of Radiation
a) Sources of radiation shall be secured against unauthorized removal
from the place of storage.
b) Sources of radiation in an unrestricted area and not in storage
shall be tended under the constant surveillance and immediate
control of the licensee or registrant.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.2070 Procedures for Picking Up, Receiving, and Opening Packages
a)
1) Each licensee or registrant who expects to receive a package
containing quantities of radioactive material in excess of the
A2 quantities specified in Appendix A of 32 Ill. Adm. Code 341
shall:
A) if the package is to be delivered to the licensee's or
registrant's facility by the carrier, make arrangements
to receive the package when it is offered for delivery by
the carrier; or
B) if the package is to be picked up by the licensee or
registrant at the carrier's terminal, make arrangements
to receive notification from the carrier of the arrival
of the package, at the time of the arrival.
2) Each licensee or registrant who picks up a package of radio-
active material from a carrier's terminal shall pick up the
package expeditiously upon receipt of notification from the
carrier of its arrival.
b)
1) Each licensee or registrant, upon receipt of a package of
radioactive material, shall monitor the external surfaces of
the package for radioactive contamination caused by leakage of
the radioactive contents. The monitoring shall be performed
as soon as practicable after receipt, but no later than 3
hours after the package is received at the licensee's facility
if received during the licensee's normal working hours or 18
hours if received after normal working hours. Such monitoring
need not be performed on:
A) packages containing less than 1 millicurie (37 MBq) of
beta and/or gamma emitting radioactive material or 10
microcuries (370 KBq) of alpha emitting radioactive
material;
B) packages containing no more than 10 millicuries (370 MBq)
of radioactive material consisting solely of tritium,
carbon-14, sulfur-35, or iodine-125;
C) packages containing only special form radioactive
material or gases;
D) packages containing only radioactive material in other
than liquid form, including Mo-99/Tc-99m generators, and
less than the A2 quantity specified in Appendix A of 32
Ill. Adm. Code 341; and
E) packages containing only radionuclides with half-lives of
less than 30 days and a total quantity of no more than
100 millicuries (3.7 GBq).
2) If removable radioactive contamination in excess of 0.01
microcurie (370 Bq) per 100 square centimeters of package
surface is found on the external surfaces of the package, the
licensee or registrant shall immediately notify, by telephone
and telegraph, the final delivering carrier and the
Department.
c)
1) Each licensee or registrant, upon receipt of a package
containing quantities of radioactive material in excess of the
A2 quantities specified in Appendix A of 32 Ill. Adm. Code
341, other than those transported by exclusive use vehicle,
shall monitor the radiation levels external to the package.
The package shall be monitored as soon as practicable after
receipt, but no later than 3 hours after the package is
received at the licensee's facility if received during the
licensee's normal working hours, or 18 hours if received after
normal working hours.
2) If radiation levels are found on the external surface of the
package in excess of 200 millirems per hour (2.0 mSv/h), or in
excess of 10 millirems per hour (0.1 mSv/h) at 1 meter from
the external surface of the package, the licensee or
registrant shall immediately notify, by telephone and
telegraph, the final delivering carrier and the Department.
d) Each licensee or registrant shall establish and maintain procedures
for safely opening packages in which radioactive material is
received and shall assure that such procedures are followed and
that due consideration is given to special instructions for the
type of package being opened.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
SUBPART C: WASTE DISPOSAL
Section 340.3010 General Requirement.
No licensee shall dispose of any radioactive material except:
a) by transfer to an authorized recipient as provided in 32 Ill. Adm.
Code 330.400, or
b) as authorized pursuant to Sections 340.1060, 340.3020, 340.3030,
340.3040, 340.3050, and 340.3060.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3020 Method of Obtaining Approval of Proposed Disposal Procedures
a) Any person may apply to the Department for approval of proposed
procedures to dispose of radioactive material in a manner not
other-wise authorized in this Part. Each application shall include
a description of the radioactive material, including the quantities
and kinds of radioactive material and levels of radioactivity
involved, and the proposed manner and conditions of disposal. The
application, where appropriate, should also include an analysis and
evaluation of pertinent information as to the nature of the
environment, including topographical, geological, meteorological,
and hydrological characteristics; usage of ground and surface
waters in the general area; the nature and location of other
potentially affected facilities; and procedures to be observed to
minimize the risk of unexpected or hazardous exposures.
b) The Department will not approve any application for a license to
receive radioactive material from other persons for disposal on
land not owned by a State or the Federal Government.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3030 Disposal by Release Into Sanitary Sewage Systems
a) No licensee or registrant shall discharge radioactive material into
a sanitary sewage system unless:
1) it is readily soluble or dispersible in water; and
2) the quantity of any radioactive material released into the
system by the licensee or registrant in any one day does not
exceed the larger of:
A) the quantity which, if diluted by the average daily
quantity of sewage released into the sewer by the
licensee or registrant, will result in an average
concentration equal to the limits specified in Appendix
A, Table I, Column 2, of this Part, or
B) 10 times the quantity of such material specified in
Appendix B of this Part; and
3) the quantity of any radioactive material released in any one
month, if diluted by the average monthly quantity of water
released by the licensee or registrant, will not result in an
average concentration exceeding the limits specified in
Appendix A, Table I, Column 2, of this Part; and
4) the gross quantity of radioactive material, excluding
hydrogen-3 and carbon-14, released into the sewage system by
the licensee does not exceed 1 curie (37 GBq) per year. The
quantities of hydrogen-3 and carbon-14 released into the
sanitary sewage system may not exceed 5 curies (185 GBq) per
year for hydrogen-3 and 1 curie (37 GBq) per year for carbon-
14.
b) No licensee or registrant shall discharge radioactive material into
an individual sewage disposal system used for the treatment of
waste water serving only a single dwelling, office building,
industrial plant, or institution except as specifically approved by
the Department pursuant to Sections 340.1060 and 340.3020.
c) Excreta from individuals undergoing medical diagnosis or therapy
with radioactive material shall be exempt from any limitations
contained in Section 340.3030.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3040 Land Disposal
No licensee or registrant shall dispose of radioactive material by land
disposal except as specifically approved by the Department pursuant to Section
340.3020.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3050 Disposal by Incineration
No licensee or registrant shall incinerate radioactive material for the
purpose of disposal or preparation for disposal except as specifically
approved by the Department pursuant to Sections 340.1060 and 340.3020.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3060 Disposal of Specific Wastes
a) Any licensee or registrant may dispose of the following radioactive
material without regard to its radioactivity:
1) 0.05 microcurie (1.850 kBq) or less of hydrogen-3 or carbon-14
per gram of medium used for liquid scintillation counting, and
2) 0.05 microcurie (1.850 kBq) or less of hydrogen-3 or carbon-14
per gram of animal tissue averaged over the weight of the
entire animal; provided, however, tissue may not be disposed
of under this Section in a manner that would permit its use
either as food for humans or as animal feed.
b) Nothing in Section 340.3060(a), however, relieves the licensee or
registrant of maintaining records showing the receipt, transfer and
disposal of such radioactive material as specified in 32 Ill. Adm.
Code 310.40.
c) Nothing in Section 340.3060(a) relieves the licensee or registrant
from complying with other applicable federal, state, and local
regulations governing any other toxic or hazardous property of
these materials.
(Source: Added at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3070 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 340.3080(a). If Class A
waste also meets the stability requirements set forth in
Section 340.3080 (b), 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
340.3080.
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 340.3080.
c) Classification determined by long-lived radionuclides. If the
radioactive waste contains only radionuclides listed in Table 1,
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 Section 340.3070(g).
Table 1
Concentration
Radionuclide 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
Concentration
Radionuclide curies/cubic
meter
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. However, as specified in Section 340.3070(f), if
radioactive waste does not contain any nuclides listed in either
Table 1 or 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 Section 340.3070(g).
*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 radio-
nuclides. If the radioactive waste contains a mixture of radionu-
clides, 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 Table 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 concen-
tration 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: Added at 10 Ill. Reg. 17538, effective September 25, 1986)
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 Section 340.3080(a)(8).
7) Waste must not be pyrophoric. Pyrophoric materials contained
in wastes shall be treated, prepared, and packaged to be
nonflammable. (See 32 Ill. Adm. Code 601 for definition of
pyrophoric.)
8) Wastes in a gaseous form shall be packaged at an absolute
pressure that does not exceed 1.5 atmospheres at 20�C. Total
activity shall not exceed 100 curies 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-radio-
logical 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 Section 340.3080(a)(3) and
(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: Added at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3090 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 340.3070.
(Source: Added at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.3110 Transfer for Disposal and Manifests
a) Each shipment of radioactive waste to a licensed land disposal
facility shall be accompanied by a shipment manifest that contains
the name, address, and telephone number of the person generating
the waste, as well as the name, address, and telephone number or
the name and U.S. Environmental Protection Agency hazardous waste
identification number of the person transporting the waste. The
manifest shall also indicate as completely as practicable: a
physical description of the waste; the waste volume; radionuclide
identity and quantity; the total radioactivity; and the principal
chemical form. The solidification agent shall be specified.
Wastes containing more than 0.1% chelating agents by weight shall
be identified and the weight percentage of the chelating agent
shall be estimated. Wastes classified as Class A, Class B, or
Class C in Section 340.3070 shall be clearly identified as such in
the manifest. The total quantity of the radionuclides H-3, C-14,
Tc-99 and I-129 shall be shown.
b) The manifest required by Section 340.3110(a) may be shipping papers
used to meet USDOT or U.S. Environmental Protection Agency regula-
tions (i.e., 40 CFR 262 and 263, revised as of July, 1984,
exclusive of subsequent amendments or editions), or requirements of
the receiver, provided all the required information is included.
c) Each manifest shall include a certification by the waste generator
that the materials being transported are properly classified, de-
scribed, packaged, marked, and labeled and are in proper condition
for transportation according to the applicable regulations of the
USDOT and the Department. An authorized representative of the
waste generator shall sign and date the manifest.
d) Any licensee or registrant who transfers waste to a land disposal
facility or a licensed waste collector shall comply with the
following requirements. Any licensee who transfers waste to a
licensed waste processor who treats or repackages waste shall
comply with the requirements of Section 340.3110(d)(4) through (8).
A licensee shall:
1) Prepare all wastes so that the waste is classified according
to Section 340.3070 and meets the waste characteristics
requirements in Section 340.3080;
2) Label each package of waste to identify whether it is Class A
waste, Class B waste, or Class C waste, in accordance with
Section 340.3070;
3) Conduct a quality control program to assure compliance with
Sections 340.3070 and 340.3080; the program must include
management evaluation of audits;
4) Prepare shipping manifests to meet the requirements of Section
340.3110(a) and (c);
5) Forward a copy of the manifest to the intended recipient at
the time of shipment; or, deliver to a collector at the time
the waste is collected, obtaining acknowledgement of receipt
in the form of a signed copy of the manifest from the
collector;
6) Include one copy of the manifest with the shipment;
7) Retain a copy of the manifest with documentation of
acknowledgement of receipt as the record of transfer of
licensed material as required by this Part;
8) For any shipments or any part of a shipment for which acknow-
ledgement of receipt has not been received within the times
set forth in Section 340.3110, conduct an investigation in
accordance with Section 340.3110(h).
e) Any waste collector licensee who handles only prepackaged waste
shall:
1) Acknowledge receipt of the waste from the generator within one
week of receipt by returning a signed copy of the manifest to
the generator;
2) Prepare a new manifest to reflect consolidated shipments; the
new manifest shall serve as a listing or index for the
detailed generator manifests. Copies of the generator
manifests shall be a part of the new manifest. The waste
collector may prepare a new manifest without attaching the
generator manifests, provided the new manifest contains for
each package the information specified in Section 340.3110(a).
The collector licensee shall certify that nothing has been
done to the waste which would invalidate the generator's
certification;
3) Forward a copy of the new manifest to the land disposal
facility operator at the time of shipment;
4) Include the new manifest with the shipment to the disposal
site;
5) Retain a copy of the manifest with documentation of acknow-
ledgement of receipt as the record of transfer of licensed
material as required by this Part, and retain information from
generator manifests until disposition is authorized by the
Department; and
6) For any shipments or any part of a shipment for which acknow-
ledgement of receipt is not received within the times set
forth in this section, conduct an investigation in accordance
with Section 340.3110(h).
f) Any licensed waste processor who treats or repackages wastes shall:
1) Acknowledge receipt of the waste from the generator within one
week of receipt by returning a signed copy of the manifest to
the generator;
2) Prepare a new manifest that meets the requirements of Section
340.3110(a), (b), and (c). Preparation of the new manifest
reflects that the processor is responsible for the waste;
3) Prepare all wastes so that the waste is classified according
to Section 340.3070 and meets the waste characteristics
requirement in Section 340.3080;
4) Label each package of waste to identify whether it is Class A
waste, Class B waste, or Class C waste, in accordance with
Sections 340.3070 and 340.3090 of this Part;
5) Conduct a quality control program to assure compliance with
Sections 340.3070 and 340.3080. This program shall include
management evaluation of audits;
6) Forward a copy of the new manifest to the disposal site
operator or waste collector at the time of shipment, or
deliver to a collector at the time the waste is collected,
obtaining acknowledgement of receipt in the form of a signed
copy of the manifest by the collector;
7) Include the new manifest with the shipment;
8) Retain copies of original manifests and new manifests with
documentation of acknowledgement of receipt as the record of
transfer of licensed material as required by this Part; and
9) For any shipment or part of a shipment for which
acknowledgement is not received within the times set forth in
this section, conduct an investigation in accordance with
Section 340.3110(h).
g) The land disposal facility operator shall:
1) Acknowledge receipt of the waste within one week of receipt by
returning a signed copy of the manifest to the shipper. The
shipper to be notified is the licensee who last possessed the
waste and transferred the waste to the operator. The returned
copy of the manifest shall indicate any discrepancies between
materials listed on the manifest and materials received;
2) Retain a copy of the manifest with documentation of
acknowledgement of receipt as the record of transfer of
licensed material as required by this Part, and retain
information from generator manifests until disposition is
authorized by the Department; and
3) Notify the shipper (i.e., the generator, the collector, or
processor) and the Department when any shipment or part of a
shipment has not arrived within 60 days after the advance
manifest was received.
h) Any shipment or part of a shipment for which acknowledgement is not
received within the times set forth in this section must:
1) Be investigated by the shipper if the shipper has not received
notification of receipt within 20 days after transfer; and
2) Be traced and reported. The investigation shall include
tracing the shipment and filing a report with the Department.
Each licensee who conducts a trace investigation shall file a
written report with the Department within 2 weeks of
completion of the investigation.
(Source: Added at 10 Ill. Reg. 17538, effective September 25, 1986)
SUBPART D: RECORDS, MONITORING AND DISPOSAL
Section 340.4010 Records of Surveys, Radiation Monitoring, and Disposal
a)
1) Each licensee or registrant shall maintain records showing the
radiation exposures of all individuals for whom personnel
monitoring is required under Section 340.2020 of this Part,
and shall report to the Department at intervals prescribed by
the Department, each quarterly radiation dose which exceeds
25% of the limits specified in Section 340.1010(a) for each
monitored person, except for persons under 18 years of age, in
which case all monthly doses shall be reported on a monthly
basis. Such records shall be kept on Form RMA-1/RMA-2 in
accordance with the instructions contained on the form, or on
clear and legible records containing all the information
required by Form RMA-1/RMA-2. The doses entered on the form
or records shall be for periods of time not exceeding one
calendar quarter and one month respectively. Reports
submitted to the Department shall be on Form RMA-1/RMA-2 or a
facsimile approved by the Department.
2) No licensee or registrant shall subtract radiation exposures
from official personnel monitoring records without the prior
approval of the Department.
b) Each licensee or registrant shall maintain records in the same
units used in this Part, showing the results of surveys required by
Section 340.2010, monitoring required by Sections 340.2070(b) and
(c), and disposals made under Sections 340.3020, 340.3030, 340.3040
and 32 Ill. Adm. Code 601.
c)
1) Records of individual exposure to radiation and to radioactive
material which must be maintained pursuant to the provisions
of Section 340.4010(a) and records of bioassays, including
results of whole body counting examinations, made pursuant to
Section 340.1070 shall be preserved until the Department
authorizes their disposition.
2) Records of the results of surveys and monitoring which must be
maintained pursuant to Section 340.4010(b) shall be preserved
for 2 years after completion of the survey except that the
following records shall be maintained until the Department
authorizes their disposition:
A) records of the results of surveys to determine compliance
with Section 340.1030(a);
B) in the absence of personnel monitoring data, records of
the results of surveys to determine external radiation
dose; and
C) records of the results of surveys used to evaluate the
release of radioactive effluents to the environment.
3) Records of disposal of licensed material made pursuant to Sec-
tions 340.3020, 340.3030, 340.3040, 340.3050, 340.3060 and 32
Ill. Adm. Code 601 are to be maintained until the Department
authorizes their disposition.
4) Records which must be maintained pursuant to this Part may be
the original or either a high quality copy or microform
provided that such reproduced copy or microform is duly
authenticated by authorized personnel and the microform is
capable of producing a legible copy after storage for the
period specified by 32 Ill. Adm. Code 310, 320, 330, 331, 341,
350, 351 and 601.
5) If there is a conflict between the Department's regulations in
this Part, license condition, or other written Department
approval or authorization pertaining to the retention period
for the same type of record, the retention period specified in
the regulations in this Part for such records shall apply
unless the Department, pursuant to 32 Ill. Adm. Code 310.30
(a), has granted a specific exemption from the record reten-
tion requirements specified in the regulations in this Part.
d) The discontinuance of, or curtailment of, activities does not
relieve the licensee or registrant of responsibility for retaining
all records required by Section 340.4010. A licensee or registrant
may, however, request the Department to accept such records. The
acceptance of the records by the Department relieves the licensee
or registrant of subsequent responsibility only in respect to their
preservation as required in Section 340.4010.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4020 Reports of Theft or Loss of Sources of Radiation
Each licensee or registrant shall report to the Department by telephone and
telegraph the theft or loss of any source of radiation immediately after such
occurrence becomes known.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4030 Notification of Incidents
a) Immediate Notification. Each licensee or registrant shall immedi-
ately notify the Department by telephone and telegraph of any
incident involving any source of radiation possessed by him and
which may have caused or threatens to cause:
1) a dose to the whole body of any individual of 25 rems (250
mSv) or more of radiation; a dose to the skin of the whole
body of any individual of 150 rems (1.50 Sv) or more of
radiation; or a dose to the feet, ankles, hands, or forearms
of any individual of 375 rems (3.75 Sv) or more of radiation;
or
2) the release of radioactive material in concentrations which,
if averaged over a period of 24 hours, would exceed 5,000
times the limits specified for such materials in Appendix A,
Table II of this Part; or
3) a loss of 1 working week or more of the operation of any
facilities affected; or
4) damage to property in excess of $200,000.
b) Twenty-four Hour Notification. Each licensee or registrant shall
within 24 hours notify the Department by telephone and telegraph of
any incident involving any source of radiation possessed by him and
which may have caused or threatens to cause:
1) a dose to the whole body of any individual of 5 rems (50 mSv)
or more of radiation; a dose to the skin of the whole body of
any individual of 30 rems (300 mSv) or more of radiation; or a
dose to the feet, ankles, hands, or forearms of 75 rems (750
mSv) or more of radiation; or
2) the release of radioactive material in concentrations which,
if averaged over a period of 24 hours, would exceed 500 times
the limits specified for such materials in Appendix A, Table
II of this Part; or
3) a loss of 1 day or more of the operation of any facilities
affected; or
4) damage to property in excess of $2,000.
c) In addition to the Immediate Notification and Twenty-Four Hour
Notification required by subsections (a) and (b), each licensee or
registrant shall file a written report with the Department in
accordance with Section 340.4050.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4040 Reports to Former Employees and Others of Exposure to
Radiation (Repealed)
(Source: Repealed at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4050 Reports of Overexposures and Excessive Levels and
Concentrations
a) In addition to any notification required by Section 340.4030, each
licensee or registrant shall make a report in writing within 30
days to the Department of:
1) each exposure of an individual to radiation in excess of the
applicable standards in Sections 340.1010, 340.1040(a), or the
license;
2) each exposure of an individual to radioactive material in
excess of the applicable limits in Sections 340.1030(a)(1),
340.1030(a) (2), 340.1040(b) or the license;
3) levels of radiation or concentrations of radioactive material
in a restricted area in excess of any other applicable limit
in the license;
4) any incident for which notification is required by Section
340.4030; and
5) levels of radiation or concentrations of radioactive material,
whether or not involving excessive exposure of any individual,
in an unrestricted area in excess of 10 times any applicable
limit set forth in this Part or in the license.
b) Each report required under Section 340.4050(a) shall describe the
extent of exposure of individuals to radiation or to radioactive
material, including estimates of each individual's exposure as
required by Section 340.4050(c); levels of radiation and
concentrations of radioactive material involved; the cause of the
exposure, levels, or concentrations; and corrective steps taken or
planned to assure against a recurrence.
c) Any report filed with the Department pursuant to Section 340.4050
shall include for each individual exposed the name, social security
number, and date of birth, and an estimate of the individual's
dose. The report shall be prepared so that this information is
stated in a separate part of the report.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4060 Notice to Employees and Others of Exposure to Radiation
(Repealed)
(Source: Repealed at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4070 Vacating Premises
Each specific licensee or registrant shall, no less than 30 days before
vacating or relinquishing possession or control of premises which may have
been contaminated with radioactive material as a result of his activities,
notify the Department in writing of intent to vacate. When deemed necessary
by the Department, the licensee shall decontaminate the premises in such a
manner as the Department may specify.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4080 Notifications and Reports to Individuals
a) Requirements for notification and reports to individuals of
exposure to radiation of radioactive material are specified in 32
Ill. Adm. Code 400.130.
b) When a licensee or registrant is required pursuant to Section
340.4050 to report to the Department any exposure of an individual
to radiation or radioactive material, the licensee or registrant
shall also notify the individual. Such notice shall be transmitted
at a time not later than the transmittal to the Department, and
shall comply with the provisions of 32 Ill. Adm. Code 400.130(a).
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
Section 340.4090 Removal of Radioactive Contamination
a) Notwithstanding any exemptions contained in this Part, any person
who uses, possesses, or stores radioactive material in such a
manner as to cause uncontrolled contamination of any area shall,
upon order of the Department, remove or provide for the removal of
such contaminants at his own expense through the use of an
authorized transferee and shall decontaminate the installation to
the lowest practicable level. The values specified in Appendix C,
of this Part, may be used as guidelines for this purpose. These
values, however, may be modified at specific installations at the
discretion of the Director.
b) In the event that a person fails to comply with the provisions of
subparagraph (a) of this Section, the Department may seize and
remove the radioactive contaminant and, if necessary, decontaminate
the installation to the values specified in Appendix C, of this
Part, and shall be reimbursed for the expense thereof by the person
failing to comply with the provisions of subparagraph (a) of this
Section. If such person is a corporation, the officers and agents
who knowingly permit the corporation to violate the provisions of
subparagraph (a) of this Section shall be responsible for such
exposure.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
SECTION 340. APPENDIX A
CONCENTRATION IN AIR AND WATER ABOVE Natural BACKGROUND
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Actinium (89) Ac-227 S 2X1O-12 6X10-5 8X1O-14 2X1O-6
I 3X10-11 9X10-3 9X10-13 3X1O-4
Ac-228 S 8X1O-8 3X1O-3 3X1O-9 9X1O-5
I 2X1O-8 3X1O-3 6X1O-10 9X1O-5
Americium (95) Am-241 S 6X1O-12 1X10-4 2X10-13 4X10-6
I 1X1O-10 8X1O-4 4X1O-12 3X10-5
Am-242m S 6X1O-12 1X1O-4 2X1O-13 4X1O-6
I 3X1O-10 3X1O-3 9X1O-12 9X1O-5
Am-242 S 4X1O-8 4X1O-3 1X1O-9 1X1O-4
I 5X1O-8 4X1O-3 2X1O-9 1X1O-4
Am-243 S 6X1O-12 1X1O-4 2X1O-13 4X1O-6
I 1X1O-10 8X1O-4 4X1O-12 3X1O-5
Am-244 S 4X1O-6 1X1O-1 1X1O-7 5X1O-3
I 2X1O-5 1X1O-1 8X1O-7 5X1O-3
Antimony (51) Sb-122 S 2X1O-7 8X10-4 6X1O-9 3X10-5
I 1X1O-7 8X1O-4 5X1O-9 3X1O-5
Sb-124 S 2X1O-7 7X1O-4 5X1O-9 2X1O-5
I 2X1O-8 7X1O-4 7X1O-10 2X1O-5
Sb-125 S 5X1O-7 3X1O-3 2X1O-8 1X1O-4
I 3X1O-8 3X1O-3 9X1O-10 1X1O-4
Cerium (58) Ce-141 S 4X1O-7 3X10-3 2X10-8 9X10-5
I 2X1O-7 3X1O-3 5X1O-9 9X1O-5
Ce-143 S 3X1O-7 1X1O-3 9X1O-9 4X1O-5
I 2X1O-7 1X1O-3 7X1O-9 4X1O-5
Ce-144 S 1X1O-8 3X1O-4 3X1O-10 1X1O-5
I 6X1O-9 3X1O-4 2X1O-10 1X1O-5
Cesium (55) Cs-131 S 1X1O-5 7X1O-2 4X10-7 2X10-3
I 3X1O-6 3X1O-2 1X1O-7 9X1O-4
Cs-134m S 4X1O-5 2X10-1 1X10-6 6X1O-3
I 6X1O-6 3X1O-2 2X1O-7 1X1O-3
Cs-134 S 4X1O-8 3X1O-4 1X1O-9 9X1O-6
I 1X1O-8 1X1O-3 4X1O-10 4X1O-5
Cs-135 S 5X1O-7 3X1O-3 2X1O-8 1X1O-4
I 9X1O-8 7X1O-3 3X1O-9 2X1O-4
Cs-136 S 4X1O-7 2X1O-3 1X1O-8 9X1O-5
I 2X1O-7 2X1O-3 6X1O-9 6X1O-5
Cs-137 S 6X1O-8 4X1O-4 2X1O-9 2X1O-5
I 1X1O-8 1X1O-3 5X1O-10 4X1O-5
Chlorine (17) Cl-36 S 4X1O-7 2X1O-3 1X1O-8 8X1O-5
I 2X1O-8 2X1O-3 8X10-10 6X1O-5
Cl-38 S 3X1O-6 1X1O-2 9X1O-8 4X1O-4
I 2X1O-6 1X1O-2 7X1O-8 4X1O-4
Chromium (24) Cr-51 S 1X1O-5 5X10-2 4X1O-7 2X1O-3
I 2X1O-6 5X1O-2 8X10-8 2X10-3
Cobalt (27) Co-57 S 3X1O-6 2X1O-2 1X1O-7 5X1O-4
I 2X1O-7 1X10-2 6X10-9 4X10-4
Co-58m S 2X1O-5 8X1O-2 6X1O-7 3X1O-3
I 9X1O-6 6X1O-2 3X1O-7 2X1O-3
Co-58 S 8X1O-7 4X1O-3 3X1O-8 1X1O-4
I 5X1O-8 3X1O-3 2X1O-9 9X1O-5
Co-60 S 3X1O-7 1X1O-3 1X1O-8 5X1O-5
I 9X1O-9 1X1O-3 3X1O-10 3X1O-5
Copper (29) Cu-64 S 2X1O-6 1X10-2 7X10-8 3X1O-4
I 1X1O-6 6X1O-3 4X1O-8 2X1O-4
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Curium (96) Cm-242 S 1X1O-10 7X10-4 4X10-12 2X10-5
I 2X1O-10 7X10-4 6X1O-12 2X1O-5
Cm-243 S 6X1O-12 1X1O-4 2X1O-13 5X1O-6
I 1X1O-10 7X1O-4 3X1O-12 2X10-5
Cm-244 S 9X1O-12 2X1O-4 3X1O-13 7X1O-6
I 1X1O-10 8X1O-4 3X1O-12 3X1O-5
Cm-245 S 5X1O-12 1X1O-4 2X1O-13 4X1O-6
I 1X1O-10 8X1O-4 4X1O-12 3X1O-5
Cm-246 S 5X1O-12 1X1O-4 2X1O-13 4X1O-6
I 1X1O-10 8X1O-4 4X1O-12 3X1O-5
Cm-247 S 5X1O-12 1X1O-4 2X1O-13 4X1O-6
I 1X1O-10 6X1O-4 4X1O-12 2X1O-5
Cm-248 S 6X1O-13 1X1O-5 2X1O-14 4X1O-7
I 1X1O-11 4X1O-5 4X1O-13 1X1O-6
Cm-249 S 1X1O-5 6X1O-2 4X1O-7 2X1O-3
I 1X1O-5 6X1O-2 4X1O-7 2X1O-3
Dysprosium (66) Dy-165 S 3X1O-6 1X1O-2 9X10-8
4X10-4
I 2X1O-6 1X1O-2 7X1O-8 4X1O-4
Dy-166 S 2X1O-7 1X10-3 8X10-9 4X10-5
I 2X1O-7 1X1O-3 7X1O-9 4X1O-5
Einsteinium (99) Es-253 S 8X1O-10 7X1O-4 3X1O-11
2X1O-5
I 6X1O-10 7X10-4 2X10-11 2X10-5
Es-254m S 5X1O-9 5X1O-4 2X1O-10 2X1O-5
I 6X1O-9 5X1O-4 2X1O-10 2X1O-5
Es-254 S 2X1O-11 4X1O-4 6X1O-13 1X1O-5
I 1X1O-10 4X1O-4 4X1O-12 1X1O-5
Es-255 S 5X1O-10 8X1O-4 2X1O-11 3X1O-5
I 4X1O-10 8X1O-4 1X1O-11 3X1O-5
Erbium (68) Er-169 S 6X1O-7 3X1O-3 2X1O-8 9X1O-5
I 4X1O-7 3X10-3 1X10-8 9X1O-5
Er-171 S 7X1O-7 3X1O-3 2X1O-8 1X10-4
I 6X1O-7 3X1O-3 2X1O-8 1X1O-4
Europium (63) Eu-152 S 4X1O-7 2X10-3 1X10-8 6X1O-5
(T r= 9.2 hrs) I 3X1O-7 2X1O-3 1X1O-8
6X1O-5
Eu-152 S 1X1O-8 2X1O-3 4X1O-10 8X1O-5
(T = 13 yrs) I 2X1O-8 2X1O-3 6X1O-10
8X1O-5
Eu-154 S 4X1O-9 6X1O-4 1X1O-10 2X1O-5
I 7X1O-9 6X1O-4 2X1O-10 2X1O-5
Eu-155 S 9X1O-8 6X1O-3 3X1O-9 2X1O-4
I 7X1O-8 6X1O-3 3X1O-9 2X1O-4
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Fermium (100) Fm-254 S 6X1O-8 4X10-3 2X10-9 1X1O-4
I 7X1O-8 4X1O-3 2X10-9 1X1O-4
Fm-255 S 2X1O-8 1X1O-3 6X1O-10 3X1O-5
I 1X1O-8 1X1O-3 4X1O-10 3X1O-5
Fm-256 S 3X1O-9 3X1O-5 1X1O-10 9X1O-7
I 2X1O-9 3X1O-5 6X1O-11 9X1O-7
Fluorine (9) F-18 S 5X1O-6 2X10-2 2X10-7 8X10-4
I 3X1O-6 1X1O-2 9X1O-8 5X1O-4
Gadolinium (64) Gd-153 S 2X1O-7 6X10-3 8X10-9
2X10-4
I 9X1O-8 6X1O-3 3X1O-9 2X1O-4
Gd-159 S 5X1O-7 2X1O-3 2X1O-8 8X1O-5
I 4X1O-7 2X1O-3 1X1O-8 8X1O-5
Gallium (31) Ga-72 S 2X1O-7 1X10-3 8X10-9 4X10-5
I 2X1O-7 1X1O-3 6X1O-9 4X1O-5
Germanium (32) Ge-68 S 4X1O-6 2X10-2 1X10-7 8X10-4
I 1X1O-8 ------ 5X1O-10 ------
Ge-71 S 1X1O-5 5X1O-2 4X1O-7 2X1O-3
I 6X1O-6 5X1O-2 2X1O-7 2X1O-3
Gold (79) Au-195 S 8X1O-6 4X1O-2 3X1O-7 1X10-3
I 6X1O-8 6X1O-3 2X1O-9 2X1O-4
Au-196 S 1X1O-6 5X1O-3 4X1O-8 2X1O-4
I 6X1O-7 4X10-3 2X10-8 1X10-4
Au-198 S 3X1O-7 2X1O-3 1X1O-8 5X1O-5
I 2X1O-7 1X1O-3 8X1O-9 5X1O-5
Au-199 S 1X1O-6 5X1O-3 4X1O-8 2X1O-4
I 8X1O-7 4X1O-3 3X1O-8 2X1O-4
Hafnium (72) Hf-181 S 4X1O-8 2X1O-3 1X1O-9 7X1O-5
I 7X1O-8 2X1O-3 3X1O-9 7X1O-5
Holmium (67) Ho-166 S 2X1O-7 9X10-4 7X1O-9 3X1O-5
I 2X1O-7 9X1O-4 6X1O-9 3X1O-5
Hydrogen (1) H-3 S 5X1O-6 1X1O-1 2X1O-7 3X1O-3
I 5X1O-6 1X10-1 2X10-7 3X10-3
Sub2 2X1O-3 ------ 4X1O-5 ------
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Indium (49) In-113m S 8X1O-6 4X1O-2 3X1O-7 1X1O-3
I 7X1O-6 4X1O-2 2X1O-7 1X1O-3
In-114m S 1X1O-7 5X10-4 4X10-9 2X10-5
I 2X1O-8 5X1O-4 7X1O-10 2X10-5
In-115m S 2X1O-6 1X1O-2 8X1O-8 4X1O-4
I 2X1O-6 1X1O-2 6X1O-8 4X1O-4
In-115 S 2X1O-7 3X1O-3 9X1O-9 9X1O-5
I 3X1O-8 3X1O-3 1X1O-9 9X1O-5
Iodine (53) I-125 S 5X1O-9 4X1O-5 8X1O-11 2X10-7
I 2X1O-7 6X10-3 6X10-9 2X1O-4
I-126 S 8X1O-9 5X1O-5 9X1O-11 3X1O-7
I 3X1O-7 3X1O-3 1X1O-8 9X1O-5
I-129 S 2X1O-9 1X1O-5 2X1O-11 6X1O-8
I 7X1O-8 6X1O-3 2X1O-9 2X1O-4
I-131 S 9X1O-9 6X1O-5 1X1O-10 3X1O-7
I 3X1O-7 2X1O-3 1X1O-8 6X1O-5
I-132 S 2X1O-7 2X1O-3 3X1O-9 8X1O-6
I 9X1O-7 5X1O-3 3X1O-8 2X1O-4
I-133 S 3X1O-8 2X1O-4 4X1O-10 1X1O-6
I 2X1O-7 1X1O-3 7X1O-9 4X1O-5
I-134 S 5X1O-7 4X1O-3 6X1O-9 2X1O-5
I 3X1O-6 2X1O-2 1X1O-7 6X1O-4
I-135 S 1X1O-7 7X1O-4 1X1O-9 4X1O-6
I 4X1O-7 2X1O-3 1X1O-8 7X1O-5
Iridium (77) Ir-190 S 1X1O-6 6X10-3 4X10-8 2X10-4
I 4X1O-7 5X1O-3 1X1O-8 2X10-4
Ir-192 S 1X1O-7 1X1O-3 4X10-9 4X10-5
I 3X1O-8 1X1O-3 9X1O-10 4X1O-5
Ir-194 S 2X1O-7 1X1O-3 8X1O-9 3X1O-5
I 2X1O-7 9X1O-4 5X1O-9 3X1O-5
Iron (26) Fe-55 S 9X1O-7 2X10-2 3X1O-8 8X1O-4
I 1X1O-6 7X10-2 3X10-8 2X10-3
Fe-59 S 1X1O-7 2X1O-3 5X1O-9 6X1O-5
I 5X1O-8 2X1O-3 2X1O-9 5X1O-5
Krypton (36) Kr-85m Sub2 6X1O-6 ------ 1X1O-7 ----
--
Kr-85 Sub 1X1O-5 ------ 3X1O-7 ------
Kr-87 Sub 1X1O-6 ------ 2X1O-8 ------
Kr-88 Sub 1X1O-6 ------ 2X10-8 ------
Lanthanum (57) La-140 S 2X1O-7 7X1O-4 5X10-9 2X10-5
I 1X1O-7 7X1O-4 4X1O-9 2X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Lead (82) Pb-203 S 3X1O-6 1X10-2 9X10-8 4X1O-4
I 2X1O-6 1X1O-2 6X10-8 4X1O-4
Pb-210 S 1X1O-10 4X1O-6 4X1O-12 1X1O-7
I 2X1O-10 5X1O-3 8X1O-12 2X1O-4
Pb-212 S 2X1O-8 6X1O-4 6X1O-10 2X1O-5
I 2X1O-8 5X10-4 7X1O-10 2X1O-5
Lutetium (71) Lu-177 S 6X1O-7 3X1O-3 2X1O-8 1X1O-4
I 5X1O-7 3X1O-3 2X1O-8 1X1O-4
Manganese (25) Mu-52 S 2X1O-7 1X10-3 7X1O-9 3X1O-5
I 1X1O-7 9X10-4 5X1O-9 3X1O-5
Mn-54 S 4X1O-7 4X1O-3 1X1O-8 1X1O-4
I 4X1O-8 3X1O-3 1X1O-9 1X1O-4
Mn-56 S 8X1O-7 4X1O-3 3X1O-8 1X1O-4
I 5X1O-7 3X1O-3 2X1O-8 1X1O-4
Mercury (80) Hg-197m S 7X1O-7 6X1O-3 3X10-8 2X1O-4
I 8X1O-7 5X10-3 3X10-8 2X10-4
Hg-197 S 1X1O-6 9X1O-3 4X1O-8 3X1O-4
I 3X1O-6 1X1O-2 9X1O-8 5X1O-4
Hg-203 S 7X1O-8 5X1O-4 2X1O-9 2X1O-5
I 1X1O-7 3X1O-3 4X1O-9 1X1O-4
Molybdenum (42) Mo-99 S 7X1O-7 5X1O-3 3X1O-8
2X1O-4
I 2X1O-7 1X1O-3 7X1O-9 4X1O-5
Neodymium (60) Nd-144 S 8X1O-11 2X1O-3 3X1O-12 7X1O-5
I 3X1O-10 2X1O-3 1X1O-11 8X1O-5
Nd-147 S 4X1O-7 2X1O-3 1X1O-8 6X1O-5
I 2X1O-7 2X10-3 8X10-9 6X10-5
Nd-149 S 2X1O-6 8X1O-3 6X1O-8 3X1O-4
I 1X1O-6 8X1O-3 5X1O-8 3X1O-4
Neptunium (93) Np-237 S 4X1O-12 9X10-5 1X10-13 3X10-6
I 1X1O-10 9X1O-4 4X1O-12 3X1O-5
Np-239 S 8X1O-7 4X1O-3 3X1O-8 1X1O-4
I 7X1O-7 4X1O-3 2X1O-8 1X1O-4
Nickel (28) Ni-59 S 5X1O-7 6X10-3 2X10-8 2X1O-4
I 8X1O-7 6X1O-2 3X1O-8 2X1O-3
Ni-63 S 6X1O-8 8X10-4 2X10-9 3X10-5
I 3X1O-7 2X1O-2 1X1O-8 7X1O-4
Ni-65 S 9X1O-7 4X1O-3 3X1O-8 1X1O-4
I 5X1O-7 3X1O-3 2X1O-8 1X1O-4
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column 2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Niobium (41) Nb-93m S 1X1O-7 1X1O-2 4X10-9 4X1O-4
I 2X1O-7 1X10-2 5X10-9 4X10-4
Nb-95 S 5X1O-7 3X1O-3 2X1O-8 1X1O-4
I 1X1O-7 3X1O-3 3X1O-9 1X1O-4
Nb-97 S 6X1O-6 3X1O-2 2X1O-7 9X1O-4
I 5X1O-6 3X1O-2 2X1O-7 9X1O-4
Osmium (76) Os-185 S 5X1O-7 2X1O-3 2X1O-8 7X1O-5
I 5X1O-8 2X10-3 2X1O-9 7X1O-5
Os-191m S 2X1O-5 7X1O-2 6X1O-7 3X1O-3
I 9X1O-6 7X10-2 3X1O-7 2X1O-3
Os-191 S 1X1O-6 5X1O-3 4X1O-8 2X1O-4
I 4X1O-7 5X10-3 1X10-8 2X10-4
Os-193 S 4X1O-7 2X1O-3 1X1O-8 6X1O-5
I 3X1O-7 2X1O-3 9X1O-9 5X1O-5
Palladium (46) Pd-103 S 1X1O-6 1X10-2 5X10-8 3X1O-4
I 7X1O-7 8X1O-3 3X10-8 3X1O-4
Pd-109 S 6X1O-7 3X1O-3 2X1O-8 9X1O-5
I 4X1O-7 2X1O-3 1X1O-8 7X1O-5
Phosphorus (15) P-32 S 7X1O-8 5X10-4 2X1O-9
2X1O-5
I 8X1O-8 7X1O-4 3X10-9 2X10-5
Platinum (78) Pt-191 S 8X1O-7 4X1O-3 3X1O-8 1X1O-4
I 6X1O-7 3X1O-3 2X1O-8 1X1O-4
Pt-193m S 7X1O-6 3X10-2 2X10-7 1X10-3
I 5X1O-6 3X1O-2 2X1O-7 1X10-3
Pt-193 S 1X1O-6 3X1O-2 4X1O-8 9X1O-4
I 3X1O-7 5X1O-2 1X1O-8 2X1O-3
Pt-197m S 6X1O-6 3X1O-2 2X1O-7 1X1O-3
I 5X1O-6 3X1O-2 2X1O-7 9X1O-4
Pt-197 S 8X1O-7 4X1O-3 3X1O-8 1X1O-4
I 6X1O-7 3X1O-3 2X1O-8 1X1O-4
Plutonium (94) Pu-238 S 2X1O-12 1X1O-4 7X10-14
5X10-6
I 3X1O-11 8X10-4 1X10-12
3X10-5
Pu-239 S 2X1O-12 1X1O-4 6X1O-14
5X1O-6
I 4X1O-11 8X1O-4 1X1O-12
3X1O-5
Pu-240 S 2X1O-12 1X1O-4 6X1O-14
5X1O-6
I 4X1O-11 8X1O-4 1X1O-12
3X1O-5
Pu-241 S 9X1O-11 7X1O-3 3X1O-12
2X1O-4
I 4X1O-8 4X1O-2 1X1O-9
1X1O-3
Pu-242 S 2X1O-12 1X1O-4 6X1O-14
5X1O-6
I 4X1O-11 9X1O-4 1X1O-12
3X1O-5
Pu-243 S 2X1O-6 1X1O-2 6X1O-8
3X1O-4
I 2X1O-6 1X1O-2 8X1O-8
3X1O-4
Pu-244 S 2X1O-12 1X1O-4 6X1O-14
4X10-6
I 3X1O-11 3X1O-4 1X1O-12
1X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Polonium (84) Po-210 S 5X1O-10 2X1O-5 2X1O-11
7X1O-7
I 2X1O-10 8X1O-4 7X1O-12
3X1O-5
Potassium (19) K-42 S 2X1O-6 9X10-3 7X1O-8
3X10-4
I 1X1O-7 6X1O-4 4X1O-9
2X1O-5
Praseodymium (59) Pr-142 S 2X1O-7 9X1O-4 7X10-9
3X1O-5
I 2X1O-7 9X1O-4 5X1O-9
3X1O-5
Pr-143 S 3X1O-7 1X1O-3 1X1O-8
5X1O-5
I 2X1O-7 1X1O-3 6X1O-9
5X1O-5
Promethium (61) Pm-147 S 6X1O-8 6X10-3 2X10-9
2X1O-4
I 1X1O-7 6X1O-3 3X10-9
2X10-4
Pm-149 S 3X1O-7 1X1O-3 1X1O-8
4X1O-5
I 2X1O-7 1X1O-3 8X1O-9
4X1O-5
Protactinium(91) Pa-230 S 2X1O-9 7X1O-3 6X1O-11
2X10-4
I 8X1O-10 7X1O-3 3X1O-11
2X1O-4
Pa-231 S 1X1O-12 3X10-5 4X10-14
9X1O-7
I 1X1O-10 8X1O-4 4X1O-12
2X1O-5
Pa-233 S 6X1O-7 4X1O-3 2X1O-8
1X1O-4
I 2X1O-7 3X1O-3 6X1O-9
1X1O-4
Radium (88) Ra-223 S 2X1O-9 2X10-5 6X1O-11
7X10-7
I 2X1O-10 1X1O-4 8X1O-12
4X1O-6
Ra-224 S 5X1O-9 7X1O-5 2X1O-10
2X1O-6
I 7X1O-10 2X1O-4 2X1O-11
5X1O-6
Ra-226 S 3X1O-11 4X1O-7 3X1O-12
3X1O-8
I 5X1O-11 9X1O-4 2X1O-12
3X1O-5
Ra-228 S 7X1O-11 8X1O-7 2X1O-12
3X1O-8
I 4X1O-11 7X1O-4 1X1O-12
3X1O-5
Radon (86) Ru-2203 S 3X1O-7 ------ 1X10-8 ----
--
Rn-222 S 3X1O-8 ------ 3X1O-9 ----
--
Rhenium (75) Re-183 S 3X1O-6 2X10-2 9X10-8
6X10-4
I 2X1O-7 8X1O-3 5X1O-9
3X1O-4
Re-186 S 6X1O-7 3X1O-3 2X1O-8
9X1O-5
I 2X1O-7 1X1O-3 8X1O-9
5X1O-5
Re-187 S 9X1O-6 7X1O-2 3X1O-7
3X1O-3
I 5X1O-7 4X1O-2 2X1O-8
2X1O-3
Re-188 S 4X1O-7 2X1O-3 1X1O-8
6X1O-5
I 2X1O-7 9X1O-4 6X1O-9
3X1O-5
Rhodium (45) Rh-103m S 8X1O-5 4X1O-1 3X1O-6
1X10-2
I 6X1O-5 3X10-1 2X10-6
1X10-2
Rh-105 S 8X1O-7 4X1O-3 3X1O-8
1X1O-4
I 5X1O-7 3X1O-3 2X1O-8
1X1O-4
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Rubidium (37) Rb-86 S 3X1O-7 2X10-3 1X1O-8
7X10-5
I 7X1O-8 7X1O-4 2X1O-9
2X1O-5
Rb-87 S 5X1O-7 3X1O-3 2X1O-8
1X1O-4
I 7X1O-8 5X1O-3 2X1O-9
2X1O-4
Ruthenium (44) Ru-97 S 2X1O-6 1X1O-2 8X10-8
4X1O-4
I 2X1O-6 1X10-2 6X10-8
3X10-4
Ru-103 S 5X1O-7 2X1O-3 2X1O-8
8X1O-5
I 8X1O-8 2X1O-3 3X1O-9
8X1O-5
Ru-105 S 7X1O-7 3X1O-3 2X1O-8
1X1O-4
I 5X1O-7 3X1O-3 2X1O-8
1X1O-4
Ru-106 S 8X1O-8 4X10-4 3X10-9
1X10-5
I 6X1O-9 3X1O-4 2X1O-10
1X1O-5
Samarium (62) Sm-147 S 7X1O-11 2X10-3 2X10-12
6X1O-5
I 3X1O-10 2X1O-3 9X1O-12
7X10-5
Sm-151 S 6X1O-8 1X10-2 2X10-9
4X10-4
I 1X1O-7 1X1O-2 5X1O-9
4X1O-4
Sm-153 S 5X1O-7 2X1O-3 2X1O-8
8X1O-5
I 4X1O-7 2X1O-3 1X1O-8
8X1O-5
Scandium (21) Sc-46 S 2X1O-7 1X10-3 8X10-9
4X1O-5
I 2X1O-8 1X1O-3 8X1O-10
4X1O-5
Sc-47 S 6X1O-7 3X1O-3 2X1O-8
9X1O-5
I 5X1O-7 3X1O-3 2X1O-8
9X1O-5
Sc-48 S 2X1O-7 8X1O-4 6X1O-9
3X1O-5
I 1X1O-7 8X1O-4 5X1O-9
3X1O-5
Selenium (34) Se-75 S 1X1O-6 9X10-3 4X1O-8
3X10-4
I 1X1O-7 8X1O-3 4X1O-9
3X1O-4
Silicon (14) Si-31 S 6X1O-6 3X10-2 2X10-7
9X10-4
I 1X1O-6 6X1O-3 3X1O-8
2X1O-4
Silver (47) Ag-105 S 6X1O-7 3X1O-3 2X10-8
1X10-4
I 8X1O-8 3X1O-3 3X1O-9
1X10-4
Ag-110m S 2X1O-7 9X10-4 7X10-9
3X10-5
I 1X1O-8 9X1O-4 3X1O-10
3X1O-5
Ag-111 S 3X1O-7 1X1O-3 1X1O-8
4X1O-5
I 2X1O-7 1X1O-3 8X1O-9
4X1O-5
Sodium (11) Na-22 S 2X1O-7 1X1O-3 6X10-9
4X1O-5
I 9X1O-9 9X10-4 3X10-10
3X10-5
Na-24 S 1X1O-6 6X1O-3 4X1O-8
2X1O-4
I 1X1O-7 8X1O-4 5X1O-9
3X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Strontium (38) Sr-85m S 4X1O-5 2X1O-1 1X10-6
7X10-3
I 3X1O-5 2X10-1 1X1O-6
7X10-3
Sr-85 S 2X1O-7 3X1O-3 8X1O-9
1X1O-4
I 1X1O-7 5X1O-3 4X1O-9
2X1O-4
Sr-89 S 3X1O-8 3X1O-4 3X1O-10
3X1O-6
I 4X1O-8 8X1O-4 1X1O-9
3X1O-5
Sr-90 S 1X1O-9 1X10-5 3X10-11
3X10-7
I 5X1O-9 1X1O-3 2X1O-10
4X1O-5
Sr-91 S 4X1O-7 2X10-3 2X1O-8
7X1O-5
I 3X1O-7 1X1O-3 9X1O-9
5X1O-5
Sr-92 S 4X1O-7 2X1O-3 2X1O-8
7X1O-5
I 3X1O-7 2X1O-3 1X1O-8
6X1O-5
Sulfur (16) S-35 S 3X1O-7 2X10-3 9X10-9
6X1O-5
I 3X1O-7 8X1O-3 9X1O-9
3X1O-4
Tantalum (73) Ta-182 S 4X1O-8 1X10-3 1X10-9
4X10-5
I 2X1O-8 1X1O-3 7X10-10
4X1O-5
Technetium (43) Tc-96m S 8X1O-5 4X1O-1 3X10-6
1X10-2
I 3X1O-5 3X10-1 1X1O-6
1X1O-2
Tc-96 S 6X1O-7 3X10-3 2X10-8
1X10-4
I 2X1O-7 1X1O-3 8X1O-9
5X1O-5
Tc-97m S 2X1O-6 1X1O-2 8X1O-8
4X1O-4
I 2X1O-7 5X1O-3 5X1O-9
2X1O-4
Tc-97 S 1X1O-5 5X1O-2 4X1O-7
2X1O-3
I 3X1O-7 2X1O-2 1X1O-8
8X1O-4
Tc-99m S 4X1O-5 2X1O-1 1X1O-6
6X1O-3
I 1X1O-5 8X1O-2 5X1O-7
3X1O-3
Tc-99 S 2X1O-6 1X1O-2 7X1O-8
3X1O-4
I 6X1O-8 5X1O-3 2X1O-9
2X1O-4
Tellurium (52) Te-125m S 4X1O-7 5X1O-3 1X1O-8
2X1O-4
I 1X1O-7 3X10-3 4X1O-9
1X10-4
Te-127m S 1X1O-7 2X1O-3 5X10-9
6X10-5
I 4X1O-8 2X1O-3 1X1O-9
5X1O-5
Te-127 S 2X1O-6 8X1O-3 6X1O-8
3X1O-4
I 9X1O-7 5X1O-3 3X1O-8
2X1O-4
Te-129m S 8X1O-8 1X1O-3 3X1O-9
3X1O-5
I 3X1O-8 6X1O-4 1X1O-9
2X1O-5
Te-129 S 5X1O-6 2X1O-2 2X1O-7
8X1O-4
I 4X1O-6 2X1O-2 1X1O-7
8X1O-4
Te-131m S 4X1O-7 2X1O-3 1X1O-8
6X1O-5
I 2X1O-7 1X1O-3 6X1O-9
4X1O-5
Te-132 S 2X1O-7 9X1O-4 7X1O-9
3X1O-5
I 1X1O-7 6X1O-4 4X1O-9
2X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Terbium (65) Tb-160 S 1X1O-7 1X1O-3 3X1O-9
4X10-5
I 3X1O-8 1X1O-3 1X1O-9
4X1O-5
Thallium (81) Tl-200 S 3X1O-6 1X10-2 9X10-8
4X1O-4
I 1X1O-6 7X1O-3 4X10-8
2X1O-4
Tl-201 S 2X1O-6 9X1O-3 7X1O-8
3X1O-4
I 9X1O-7 5X1O-3 3X1O-8
2X1O-4
Tl-202 S 8X1O-7 4X1O-3 3X1O-8
1X1O-4
I 2X1O-7 2X1O-3 8X1O-9
7X1O-5
Tl-204 S 6X1O-7 3X1O-3 2X1O-8
1X1O-4
I 3X1O-8 2X1O-3 9X1O-10
6X1O-5
Thorium (90) Th-227 S 3X1O-10 5X1O-4 1X10-11
2X10-5
I 2X1O-10 5X1O-4 6X10-12
2X10-5
Th-228 S 9X1O-12 2X1O-4 3X1O-13
7X1O-6
I 6X1O-12 4X1O-4 2X1O-13
1X1O-5
Th-230 S 2X1O-12 5X1O-5 8X1O-14
2X1O-6
I 1X1O-11 9X1O-4 3X1O-13
3X1O-5
Th-231 S 1X1O-6 7X1O-3 5X1O-8
2X1O-4
I 1X1O-6 7X1O-3 4X1O-8
2X1O-4
Th-232 S 3X1O-11 5X1O-5 1X1O-12
2X1O-6
I 3X1O-11 1X1O-3 1X1O-12
4X1O-5
Th-nat-
ura1 S 6X1O-11 6X10-5 2X1O-12
2X10-6
I 6X1O-11 6X1O-4 2X1O-12
2X1O-5
Th-234 S 6X1O-8 5X1O-4 2X1O-9
2X1O-5
I 3X1O-8 5X1O-4 1X1O-9
2X1O-5
Thulium (69) Tm-170 S 4X1O-8 1X10-3 1X10-9
5X10-5
I 3X1O-8 1X1O-3 1X1O-9
5X1O-5
Tm-171 S 1X1O-7 1X1O-2 4X1O-9
5X1O-4
I 2X1O-7 1X1O-2 8X1O-9
5X1O-4
Tin (50) Sn-113 S 4X1O-7 2X10-3 1X10-8
9X10-5
I 5X1O-8 2X1O-3 2X1O-9
8X1O-5
Sn-125 S 1X1O-7 5X1O-4 4X1O-9
2X1O-5
I 8X1O-8 5X1O-4 3X1O-9
2X1O-5
Tungsten (74) W-181 S 2X1O-6 1X1O-2 8X1O-8
4X10-4
I 1X1O-7 1X1O-2 4X1O-9
3X1O-4
W-185 S 8X1O-7 4X1O-3 3X1O-8
1X1O-4
I 1X1O-7 3X1O-3 4X10-9
1X10-4
W-187 S 4X1O-7 2X1O-3 2X10-8
7X1O-5
I 3X1O-7 2X1O-3 1X1O-8
6X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Uranium (92) U-230 S 3X1O-10 1X1O-4 1X10-11
5X1O-6
I 1X1O-10 1X10-4 4X1O-12
5X10-6
U-232 S 1X1O-10 8X1O-4 3X1O-12
3X1O-5
I 3X1O-11 8X1O-4 9X1O-13
3X1O-5
U-233 S 5X1O-10 9X1O-4 2X1O-11
3X1O-5
I 1X1O-10 9X1O-4 4X1O-12
3X1O-5
U-234 S4 6X1O-10 9X1O-4 2X1O-11
3X1O-5
I 1X1O-10 9X1O-4 4X1O-12
3X1O-5
U-235 S4 5X1O-10 8X1O-4 2X1O-11
3X1O-5
I 1X1O-10 8X1O-4 4X1O-12
3X1O-5
U-236 S 6X1O-10 1X1O-3 2X1O-11
3X1O-5
I 1X1O-10 1X1O-3 4X1O-12
3X1O-5
U-238 S4 7X1O-11 1X1O-3 3X1O-12
4X1O-5
I 1X1O-10 1X1O-3 5X1O-12
4X1O-5
U-240 S 2X1O-7 1X1O-3 8X1O-9
3X1O-5
I 2X1O-7 1X1O-3 6X1O-9
3X1O-5
U-nat-
ura1 S4 1X1O-10 1X10-3 5X1O-12
3X1O-5
I 1X1O-10 1X1O-3 5X10-12
3X1O-5
Vanadium (23) V-48 S 2X1O-7 9X1O-4 6X10-9
3X1O-5
I 6X1O-8 8X1O-4 2X1O-9
3X1O-5
Xenon (54) Xe-131m Sub2 2X1O-5 ------ 4X1O-7 ----
--
Xe-133 Sub 1X1O-5 ------ 3X10-7 ----
--
Xe-133m Sub 1X1O-5 ------ 3X1O-7 ----
--
Xe-135 Sub 4X1O-6 ------ 1X1O-7 ----
--
Ytterbium (70) Yb-175 S 7X1O-7 3X1O-3 2X1O-8
1X1O-4
I 6X1O-7 3X1O-3 2X1O-8
1X1O-4
Yttrium (39) Y-88 S 3X1O-7 2X1O-3 6X1O-9
7X1O-5
I 5X1O-8 3X1O-3 2X10-9
9X1O-5
Y-90 S 1X1O-7 6X10-4 4X10-9
2X10-5
I 1X1O-7 6X1O-4 3X1O-9
2X1O-5
Y-91m S 2X1O-5 1X1O-1 8X1O-7
3X1O-3
I 2X1O-5 1X1O-1 6X1O-7
3X1O-3
Y-91 S 4X1O-8 8X1O-4 1X1O-9
3X1O-5
I 3X1O-8 8X1O-4 1X1O-9
3X1O-5
Y-92 S 4X1O-7 2X1O-3 1X1O-8
6X1O-5
I 3X1O-7 2X1O-3 1X1O-8
6X1O-5
Y-93 S 2X1O-7 8X1O-4 6X1O-9
3X1O-5
I 1X1O-7 8X1O-4 5X1O-9
3X1O-5
Table I Table II
Element Isotope1 Column 1 Column 2 Column 1 Column
2
(atomic Air Water Air Water
number) (uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
Zinc (30) Zn-65 S 1X1O-7 3X10-3 4X1O-9
1X1O-4
I 6X1O-8 5X10-3 2X1O-9
2X1O-4
Zn-69m S 4X1O-7 2X1O-3 1X1O-8
7X1O-5
I 3X1O-7 2X1O-3 1X1O-8
6X1O-5
Zn-69 S 7X1O-6 5X10-2 2X10-7
2X10-3
I 9X1O-6 5X1O-2 3X1O-7
2X1O-3
Zirconium (40) Zr-93 S 1X1O-7 2X10-2 4X10-9
8X1O-4
I 3X1O-7 2X1O-2 1X1O-8
8X1O-4
Zr-95 S 1X1O-7 2X1O-3 4X1O-9
6X1O-5
I 3X1O-8 2X1O-3 1X1O-9
6X1O-5
Zr-97 S 1X1O-7 5X1O-4 4X1O-9
2X1O-5
I 9X1O-8 5X1O-4 3X1O-9
2X1O-5
Any sing1e radio- Sub2 1X1O-6 ------ 3X1O-8 ----
--
nuclide not listed
above with decay
mode other than
alpha emission or
spontaneous fission
and with radioactive
half-life less than
2 hours.
Any single radio- 3X1O-9 9X1O-5 1X1O-10
3X1O-6
nuclide not listed
above with decay
mode other than
alpha emission or
spontaneous fission
and with radioactive
half-life greater than
2 hours.
Any single radio- 6X1O-13 4X1O-7 2X1O-14
3X1O-8
nuclide not listed
above, which decays
by alpha emission or
spontaneous fission.
1 Soluble (S); Insoluble (I).
2 "Sub" means that values given are for submersion in a semi-spherical
infinite cloud of airborne material.
3 These radon concentrations are appropriate for protection from radon-222
combined with its short-lived daughters. Alternatively, the value in Table I
may be replaced by one-third (1/3) "working level". (A "working level" is
defined as any combination of short-lived radon-222 daughters, polonium-218,
lead-214, bismuth-214, and polonium-214, in 1 liter of air, without regard to
the degree of equilibrium, that will result in the ultimate emission of 1.3 X
105 MeV of alpha particle energy.) The Table II value may be replaced by one
thirtieth (1/30) of a "working level". The limit on radon-222 concentrations
in restricted areas may be based on an annual average.
4 For soluble mixtures of U-238, U-234 and U-235 in air, chemical toxicity may
be the limiting factor. If the percent by weight (enrichment ) of U-235 is
less than 5, the concentration value for a 40-hour workweek, Table I, is 0.2
milligrams uranium per cubic meter of air average. For any enrichment, the
product of the average concentration and time of exposure during a 40-hour
workweek shall not exceed 8 X 10-3 SA uCi-hr/ml, where SA is the specific
activity of the uranium inhaled. The concentration value for Table II is
0.007 milligrams uranium per cubic meter of air. The specific activity for
natural uranium is 6.77 X 10-7 curies per gram uranium. The specific activity
for other mixtures of U-238, U-235 and U-234, if not known, sha11 be:
SA = 3.6X1O-7 curies/gram U2 (U-depleted)
SA = (0.4 + 0.38E + 0.0034E) X 10-6, E lesser than or equal to 0.72,
where E is the percentage by weight of U-235, expressed as percent.
NOTE: In any case where there is a mixture in air or water of more than one
radionuclide, the limiting values for purposes of this Appendix should
be determined as follows:
1) If the identity and concentration of each radionuclide in the
mixture are known, the limiting values should be derived as
follows: Deter-mine, for each radionuclide in the mixture, the
ratio between the quantity present in the mixture and the limit
otherwise established in Appendix "A" for the specific
radionuclide when not in a mixture. The sum of such ratios for
all the radionuclides in the mixture may not exceed "1" (i.e.,
"unity").
EXAMPLE: If radionuclides (a), (b), and (c) are present in
concentrations Ca, Cb, and Cc, and if the applicable maximum
permissible concentrations (MPC's) are MPCa, MPCb, and MPCc
respectively, then the concentrations shall be limited so
that the following relationship exists:
Ca Cb Cc lesser than
+ + or
MPCa MPCb MPCc equal to 1
2) If either the identity or the concentration of any radionuclide in
the mixture is not known, the limiting values for purposes of
Appendix "A" shall be:
a) For purposes of Table I, Column 1 . . . . . . 6X1O-13
b) For purposes of Table I, Column 2 . . . . . . 4X1O-7
c) For purposes of Table II, Column 1 . . . . . . 2X1O-14
d) For purposes of Table II, Column 2 . . . . . . 3X1O-8
3) If any of the conditions specified be1ow are met, the
corresponding values specified below may be used in lieu of those
specified in paragraph 2 above.
a) If the identity of each radionuclide in the mixture is known
but the concentration of one or more of the radionuclides in
the mixture is not known, the concentration limit for the
mixture is the limit specified in Appendix "A" for the
radionuclide in the mixture having the lowest concentration
limit; or
b) If the identity of each radionuclide in the mixture is not
known, but it is known that certain radionuclides specified
in Appendix "A" are not present in the mixture, the
concentration limit for the mixture is the lowest
concentration limit specified in Appendix "A" for any
radionuclide which is not known to be absent from the
mixture; or
Table I Table II
c) Radionuclide Column 1 Column 2 Column 1 Column 2
Air Water Air Water
(uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
If it is known
that Sr-90, I-125,
I-126, I-129, I-131,
(I-133 Table II
only), Pb-210,
Po-210, At-211,
Ra-223, Ra-224,
Ra-226, Ac-227,
Ra-228, Th-230,
Pa-231, Th-232,
Th-nat, Cm-248,
Cf-254, and
Fm-256 are not
present ------------- ------- 9X1O-5 ------ 3X1O-6
Table I Table II
c) Radionuclide Column 1 Column 2 Column 1 Column 2
Air Water Air Water
(uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
If it is known
that Sr-90, I-125,
I-126, I-129,
(I-131, I-133,
Table II on1y),
Pb-210, Po-210,
Ra-223, Ra-226,
Ra-228, Pa-231,
Th-nat, Cm-248,
Cf-254, and
Fm-256 are not
present ------- ------- 6X1O-5 ------ 2x1O-6
If it is known
that Sr-90, I-129,
(I-125, I-126,
I-131, Table II
on1y), Pb-210,
Ra-226, Ra-228,
Cm-248, and
Cf-254 are not
present ------- ------ 2X1O-5 ------ 6X1O-7
If it is known
that (I-129,
Table II on1y),
Ra-226, and
Ra-228 are not
present ------- ------ 3X1O-6 ------ 1X1O-7
If it is known
that alpha-
emitters and
Sr-90, I-129,
Pb-210, Ac-227,
Ra-228, Pa-230,
Pu-241, and
Bk-249 are not
present ------- 3X1O-9 ------ 1X1O-10 ------
If it is known
that alpha-
emitters and
Pb-210, Ac-227,
Ra-228, and
Pu-241 are not
present ------- 3X1O-10 ------ 1X10-11 ------
Table I Table II
c) Radionuclide Column 1 Column 2 Column 1 Column 2
Air Water Air Water
(uCi/ml) (uCi/ml) (uCi/ml) (uCi/ml)
If it is known
that alpha-
emitters and
Ac-227 are not
present ------- 3X1O-11 ------ 1X1O-12 ------
If it is known
that Ac-227,
Th-230, Pa-231,
Pu-238, Pu-239,
Pu-240, Pu-242,
Pu-244, Cm-248,
Cf-249 and Cf-251
are not
present ------ 3X1O-12 ------ 1X1O-13 ------
4) If a mixture of radionuclides consists of Uranium and its
daughters in ore dust prior to chemical separation of the Uranium
from the ore, the values specified be1ow may be used for uranium
and its daughters through radium-226, instead of those from
paragraph 1, 2, or 3 above.
a) For purposes of Table I, Column 1, 1X10-10 uCi/ml gross
alpha activity; or 5X1O-11 uCi/ml natural Uranium; or 75
micrograms per cubic meter of air natural Uranium.
b) For purposes of Table II, Column 1, 3X1O-12 uCi/ml gross
alpha activity; 2X10-12 uCi/ml natural Uranium; or 3
micrograms per cubic meter of air natural Uranium.
5) For purposes of this note, a radionuclide may be considered as not
present in a mixture if:
(a) The ratio of the concentration of that radionuclide in the
mixture (Ca) to the concentration limit for that
radionuclide specified in Table II of Appendix "A" (MPCa)
does not exceed 1/10, (i.e., Ca/MPCa is lesser than or equal
to 1/10); and
(b) The sum of such ratios for all radionuclides considered as
not present in the mixture does not exceed 1/4, (i.e.,
Ca/MPCa + Cb/MPCb +........is lesser than or equal to 1/4).
NOTE: To convert uCi/ml to SI units of megabecquerels per liter multiply
the above values by 37.
EXAMPLE: Zirconium (40) Zr-97 S (Table I, Column 1-Air) (1X1O-7
uCi/ml multiplied by 37 is equivalent to 37X1O-7 MBq/l.)
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
SECTION 340.APPENDIX B Quantities for use with 340.2030 and 340.3030
Material and Microcuries
*AGENCY NOTE 1: Based on alpha disintegration rate of Th-232, Th-230 and
their daughter products.
**AGENCY NOTE 2: Based on alpha disintegration rate of U-238, U-234, and U-
235.
Material Microcuries
Any alpha emitting
radionuclide not listed
above or mixtures of
alpha emitters of
unknown composition 0.01
Any radionuclide other
than alpha emitting
radionuclides, not
listed above or
mixtures of beta
emitters of unknown
composition 0.1
NOTE: For purposes of Sections 340.2030 and 340.3030, where there is
involved a combination of isotopes in known amounts, the limit for
the combination should be derived as follows: Determine, for each
isotope in the combination, the ratio between the quantity present
in the combination and the limit otherwise established for the
specific isotope when not in combination. The sum of such ratios
for all the isotopes in the combination may not exceed "1" (i.e.,
"unity").
NOTE: To convert microcuries (uCi) to SI units of kilobecquerels (KBq),
multiply the above values by 37.
EXAMPLE: Zirconium-97 (10 uCi) (37) = 370 kBq.
(10 uCi multiplied by 37 is equivalent to 370 kBq.)
(Source: Amended at 10 Ill. Reg. ______, effective _________________________)
SECTION 340.APPENDIX C *
DECONTAMINATION GUIDES
a) Surface Contamination Guide
Alpha Emitters
Removable 15 pCi per 100 cm2 = average
33 dpm per 100 cm2 over any
one surface
45 pCi per 100 cm2 = maximum
100 dpm per 100 cm2
Total 450 pCi per 100 cm2 = average
(fixed) 1,000 dpm per 100 cm2 over any
one surface
2,250 pCi per 100 cm2 maximum
5,000 dpm per 100 cm2
0.25 mRem per hour at 1 cm
Beta-Gamma Emitters
Removable 100 pCi per 100 cm2 average
(all beta-gamma over any
emitters except one surface
Hydrogen 3)
500 pCi per 100 cm2 maximum
Removable 1,000 pCi per 100 cm2 average
(Hydrogen 3) over any
one surface
5,000 pCi per 100 cm2 maximum
Total 0.25 mRem per hour at 1 cm
(fixed) from surface
b) Concentration in air and water: Appendix A, Table II of Part 340.
c) Concentrations in soil and other materials except water:
1) Radioactive material except source materials: Appendix A,
Column II of 32 Ill. Adm. Code 330.
2) Source material: 0.05 percent by weight.
*AGENCY NOTE: This Appendix shall be used only as a guide. The
Department may require lower values in specific instances,
depending upon radionuclides, type of surface, intended present and
future use, etc.
(Source: Amended at 10 Ill. Reg. 17538, effective September 25, 1986)
