doc_fn: oldord/5480/o548011.html
DocType: ArcOld
ID: DOE O 5480.11
Title: Radiation Protection for Occupational Workers
Summary:
Org:
Date_Issue: 12/21/1988
Date_Close: 09/29/1995
VdkVgwKey: oldord-9
Directive: 5480.11
Text:
U.S. Department of Energy ORDER
Washington, D.C. DOE 5480.11
12-21-88
Chg 3: 6-17-92
SUBJECT: RADIATION PROTECTION FOR OCCUPATIONAL WORKERS
1. PURPOSE. To establish radiation protection standards and program
requirements for the Department of Energy (DOE) and DOE contractor
operations with respect to the protection of the worker from ionizing
radiation.
2. SCOPE. The provisions of this Order apply to all Departmental Elements
and contractors performing work for the Department as provided by law
and/or contract and as implemented by the appropriate contracting
officer.
3. SUPERCESSION. This Order supercedes DOE 5480.1A, ENVIRONMENTAL
PROTECTION, SAFETY AND HEALTH PROTECTION PROGRAM FOR DOE OPERATIONS, of
8-13-81, Chapter XI, "Requirements for Radiation Protection," except
areas pertaining to radiation protection standards for the public and
the environment.
4. EFFECTIVE DATE. 1-1-89.
5. POLICY.
a. It is the policy of DOE to implement radiation protection standards
that are consistent with the Presidential approved guidance to
Federal Agencies promulgated by the Environmental Protection Agency
(EPA) and based on the recommendations by authoritative
organizations, e.g., the National Council on Radiation Protection
and Measurements (NCRP), and the International Commission on
Radiological Protection (ICRP).
b. It is the policy of DOE to operate its facilities and conduct its
activities so that radiation exposures are maintained within the
limits promulgated by this Order and as far below the limits of this
Order as reasonably achievable. This policy applies to annual,
committed, and cumulative dose equivalents.
c. It is the policy of DOE that a Radiological Control Program be
established that implements by 12-1-92 the provisions set forth in
the DOE Radiological Control (RadCon) Manual, except to the extent
the Program Secretarial Officer (PSO) responsible for a site,
facility or program approves an implementation plan that includes a
schedule for implementation of a specific provision after 12-1-92.
6. REFERENCES. The following documents provide useful information for
implementing and/or a basis for the requirements of this Order.
a. DOE 1324.2A, RECORDS DISPOSITION, of 9-13-88, which prescribes
policies, procedures, standards, and guidelines for the orderly
disposition of records of the DOE and its operating contractors.
b. DOE 5000.3A, OCCURRENCE REPORTING AND PROCESSING OF OPERATIONS
INFORMATION, of 5-30-90, which establishes a DOE system for
identification, categorization, notification, analysis, reporting,
followup, and closeout of occurrences.
c. DOE 5480.1B, ENVIRONMENT, SAFETY, AND HEALTH PROGRAM FOR DEPARTMENT
OF ENERGY OPERATIONS, of 9-23-86, which outlines environmental,
safety, and health protection policies and responsibilities.
d. DOE 5480.4, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
STANDARDS, of 5-15-84, which identifies mandatory and recommended
environment, safety, and health standards.
e. DOE 5480.5, SAFETY OF NUCLEAR FACILITIES, of 9-23-86, which
establishes DOE's nonreactor nuclear facility safety program.
f. DOE 5480.6, SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS,
of 9-23-86, which establishes DOE reactor safety program.
g. DOE 5480.15, DEPARTMENT OF ENERGY LABORATORY ACCREDITATION PROGRAM
FOR PERSONNEL DOSIMETRY, of 12-14-87, which defines requirements for
participation in the DOE Laboratory Accreditation Program.
h. DOE 5482.1B, ENVIRONMENT, SAFETY, AND HEALTH APPRAISAL PROGRAM, of
9-23-86, which establishes the DOE environmental protection, safety,
and health protection appraisal program.
i. DOE 5484.1, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
INFORMATION REPORTING REQUIREMENTS, of 2-24-81, which establish
procedures for investigation of accidents having environmental
protection, safety, or health protection significance.
j. DOE Orders in the 5500 series that outline responsibilities for
emergency preparedness.
k. DOE 5700.6C, QUALITY ASSURANCE, of 8-21-91, which sets forth actions
for establishing, implementing, and maintaining actions to assure
quality achievement in DOE programs.
l. DOE 6430.1A, GENERAL DESIGN CRITERIA, of 4-6-89, which provides
general design criteria for the acquisition of DOE facilities.
m. DOE publication DOE/EH-0026, "Handbook for the Department of Energy
Laboratory Accreditation Program for Personnel Dosimetry Systems,"
which provides operating procedures for the program and is available
from the National Technical Information Service.
n. DOE publication DOE/EH-0027, "Department of Energy Standard for the
Testing of Personnel Dosimetry Systems," which provides the
performance testing criteria used to accredit personnel dosimeters
and is available from the National Technical Information Service.
o. DOE publication PNL-6577, "Health Physics Manual of Good Practices
for Reducing Radiation Exposure to Levels that are As Low As
Reasonably Achievable (ALARA)," of 7-88, that provides contractor
personnel with general guidance regarding programs and techniques to
reduce radiation exposure to as low as reasonably achievable. This
document may be purchased from the National Technical Information
Service.
p. DOE publication DOE/EH-0070, "External Dose-Rate Conversion Factors
for Calculation of Dose to the Public," of 7-88, which provides
conversion factors for use in calculating dose from radionuclides
external to the body and is available from the National Technical
Information Service.
q. DOE publication DOE/EH-0071, "Internal Dose Conversion Factors for
Calculation of Dose to the Public," of 7-88, which provides
conversion factors for use in calculating dose from radionuclides in
the body and is available from the National Technical Information
Service.
r. Nuclear Energy Agency report, "Assessment and Recording of Radiation
Dose to Workers," of 1986, which provides recommended technical
procedures for a unified approach for dose assessment and recording.
This document is available from the Organization for the Economic
Cooperation and Development, Paris, France.
s. The following reports of the National Council on Radiation
Protection and Measurements (NCRP) available from the National
Council on Radiation Protection and Measurements, Bethesda,
Maryland.
(1) NCRP Report 84, "General Concepts for the Dosimetry of
Internally Deposited Radionuclides."
(2) NCRP Report 87, "Use of Bioassay Procedures for Assessment of
Internal Radionuclide Deposition."
(3) NCRP Report 91, "Recommendations on Limits for Exposure to
Ionizing Radiation."
t. The following International Commission on Radiological Protection
(ICRP) publications available from Pergamon Press, Elmsford, New
York.
(1) ICRP Publication 23, "Reference Man Anatomical Physiological
and Metabolic Characteristics."
(2) ICRP Publication 26, "Recommendations of the International
Commission on Radiological Protection."
(3) ICRP Publication 30, "Limits for Intakes of Radionuclides by
Workers."
(4) ICRP Publication 32, "Limits for Inhalation of Radon Daughters
by Workers."
(5) ICRP Publication 37, "Cost-Benefit Analysis in the Optimization
of Radiation Protection."
(6) ICRP Publication 48, "The Metabolism of Plutonium and Related
Elements."
u. Environmental Protection Agency standards:
(1) "Radiation Protection Guidance to the Federal Agencies for
Occupational Exposure," Federal Register, Vol 52, No. 17, 1987.
(2) Title 40 CFR Part 141, "National Interim Primary Drinking Water
Regulations (Safe Drinking Water Act)," which prescribes
radionuclide concentration limits for public drinking water.
v. The following American National Standards Institute (ANSI) standards
available from American National Standards Institute, New York, New
York.
(1) N2.1-1971, "Radiation Symbol."
(2) N2.3-1979, "Immediate Evacuation Signal for Use in Industrial
Installations Where Radiation Exposures May Occur."
(3) N8.3-1979, "Criticality Accident Alarm."
(4) N12.1-1971, "Fissile Material Symbol."
(5) N13.1-1982, "Guide to Sampling Airborne Radioactive Materials
in a Nuclear Facility."
(6) N13.2-1982, "Administrative Practices in Radiation Monitoring
(A Guide for Management)."
(7) N13.3-1981, "Dosimetry for Criticality Accidents."
(8) N13.4-1983, "Specifications of Portable X- or Gamma Radiation
Survey Instruments."
(9) N13.5-1982, "Performance Specifications for Direct Reading and
Indirect Reading Pocket Dosimeters for X- and Gamma Radiation."
(10) N13.6-1972, "Practice for Occupational Radiation Exposure
Record Systems." (Reaffirmed in 1982)
(11) N13.15-1981, "Performance of Personnel Thermoluminescence
Dosimetry Systems."
(12) N317-1985, "Performance Criteria for Instrumentation Used for
Inplant Plutonium Monitoring."
(13) N319-1984, "Personnel Neutron Dosimeters (Neutron Energies Less
Than 20 MeV)."
(14) N320-1985, "Performance Specifications for Reactor Emergency
Radiological Monitoring Instrumentation."
(15) N322-1983, "Inspection and Test Specifications for Direct and
Indirect Reading Quartz Fiber Pocket Dosimeters."
(16) N323-1983, "Radiation Protection Instrumentation Test and
Calibrations."
(17) N510-1980, "Testing of Nuclear Air Cleaning Systems."
(18) Z88.2-1980, "Practices for Respiratory Protection."
w. Executive Order 12344, "Naval Nuclear Propulsion Program," of
2-1-82, which establishes the responsibilities of the Director,
Naval Nuclear Propulsion Program for the joint DOE/Navy Naval
Nuclear Propulsion Program.
7. RESPONSIBILITIES AND AUTHORITIES.
a. The Secretary. Many provisions in this Order permit and/or
necessitate the exercise of discretion and/or judgment in carrying
out the requirements of the Order. In those instances, the
determination of whether, in the exercise of such discretion and/or
judgment, the requirements of this Order were complied with, rests
initially with the relevant Departmental authority and ultimately,
with the Secretary. The Secretary retains the sole and final
authority to determine what acts are necessary to comply with this
Order. This authority may be delegated by the Secretary as
appropriate.
b. In addition to those responsibilities and authorities contained in
DOE 5480.1B, the following responsibilities and authorities are
assigned, as follows:
(1) Assistant Secretary for Environment, Safety and Health (EH-1):
(a) Develops DOE radiation protection policy and requirements;
and
(b) Approves, if warranted, requests for specific exceptions
to this Order.
(2) Program Assistant Secretaries. Implement DOE radiation
protection policy and requirements in programs and facilities
for which they have programmatic or custodial responsibility
and through the DOE contractors for which they have contract
administration.
(3) Heads of Field Organizations.
(a) Implement the provisions of this Order for activities for
which they have direct or custodial responsibility and
through the DOE contractors for which they have contract
administration.
(b) Process specific requests for exceptions to this Order
[See paragraph 7b(1)(b)].
(c) In emergency situations, where immediate decisions and
actions are required, approve, if warranted, requests for
exceptions from the requirements of this Order and report
such action in accordance with DOE 5484.1.
(d) Temporarily suspend the requirements of this Order when
doing so is, in their judgment, necessary to minimize
danger to life or property or to protect public health or
safety. Whenever this provision is invoked, such
suspension and the reason therefore is to be reported to
EH-1 at the earliest practicable time.
(4) Deputy Assistant Secretary for Naval Reactors. Executive Order
12344, statutorily prescribed by PL 98-525 (42 USC 7158 note),
establishes the responsibilities of the Director, Naval Nuclear
Propulsion Program for the joint DOE/Navy Naval Nuclear
Propulsion Program. Within the Department, the Director (who
is also the Deputy Assistant Secretary for Naval Reactors) is
responsible for prescribing and enforcing standards and
regulations for control of radiation and radioactivity as they
affect the safety and health of workers, operators, and the
general public for Naval Reactors facilities and activities.
Accordingly, the provisions of this Order do not apply to Naval
Reactors facilities and activities except as determined by the
Director.
8. DEFINITIONS.
a. Annual Limit on Intake (ALI). The quantity of a single radionuclide
which, if inhaled or ingested in 1 year, would irradiate a person,
represented by reference man (ICRP Publication 23) to the limiting
value for control of the workplace (paragraph 9j(2)).
b. As Low As Reasonably Achievable (ALARA). An approach to radiation
protection to control or manage exposures (both individual and
collective to the workforce and general public) as low as social,
technical, economic, practical, and public policy considerations
permit. As used in this Order, ALARA is not a dose limit but a
process, which has the objective of dose levels as far below
applicable limits of the Order as reasonably achievable.
c. Area Terms.
(1) Controlled Area. Any area to which access is controlled in
order to protect individuals from exposure to radiation and
radioactive materials.
(2) Radiological Area. Any area within a controlled area where an
individual can receive a dose equivalent greater than 5 mrem
(50 microsieverts) in 1 hour at 30 cm from the radiation source
or any surface through which the radiation penetrates, or where
airborne radioactive concentrations greater than 1/10 of the
derived air concentrations are present (or are likely to be),
or where surface contamination levels greater than those
specified in Attachment 2 of this Order are present.
d. Derived Air Concentration (DAC). Quantity obtained by dividing the
ALI for any given radionuclide by the volume of air breathed by an
average worker during a working year (2.4 x 10/3 m/3).
e. Dose Terms.
(1) Absorbed Dose (D). The energy imparted to matter by ionizing
radiation per unit mass of irradiated material at the place of
interest in that material. The absorbed dose is expressed in
units of rad (or gray) (1 rad = 0.01 gray).
(2) Dose Equivalent (H). The product of absorbed dose (a) in rads
(or gray) in tissue, a quality factor (Q), and other modifying
factors (N). Dose equivalent (H) is expressed in units of rem
(or sievert).
(3) Annual Dose Equivalent. The dose equivalent received in a
year. Annual dose equivalent is expressed in units of rem (or
sievert).
(4) Shallow, Deep, and Lens of Eve Dose Equivalent. The dose
equivalent at the respective depths of 0.007 cm, 1.0 cm, and
0.3 cm in tissue.
(5) Effective Dose Equivalent (HE). The sum over specified tissues
of the products of the dose equivalent in a tissue (Ht) and the
weighting factor (Wt) for that tissue, i.e., HE = Wt Ht. The
effective dose equivalent is expressed in units of rem (or
sievert).
(6) Annual Effective Dose Equivalent. The effective dose
equivalent received in a year. The annual effective dose
equivalent is expressed in units of rem (or sievert).
(7) Committed Dose Equivalent. The calculated dose equivalent
projected to be received by a tissue or organ over a 50-year
period after an intake of radionuclide into the body. It does
not include contributions from external dose. Committed dose
equivalent is expressed in units of rem (or sievert).
(8) Committed Effective Dose Equivalent (HE, 50) The sum of the
committed dose equivalents to various tissues in the body, each
multiplied by its weighting factor. It does not include
contributions from external dose. Committed effective dose
equivalent is expressed in units of rem (or sievert).
(9) Collective Dose Equivalent. The sum of the dose equivalents of
all individuals in an exposed population. Collective dose
equivalent is expressed in units of person-rem (or
person-sievert).
(10) Collective Effective Dose Equivalent. The sum of the effective
dose equivalents of all individuals in an exposed population.
Collective effective dose equivalent is expressed in units of
person-rem (or person-sievert).
(11) Cumulative Annual Effective Dose Equivalent. The sum of the
annual effective dose equivalents recorded for an individual
for each year of employment at a DOE or DOE contractor facility
since the effective date of this Order.
(12) Weighting Factor (Wt). Is used in the calculation of annual
and committed effective dose equivalent to equate the risk
arising from the irradiation of tissue T to the total risk when
the whole body is uniformly irradiated. The weighting factors
as defined in ICRP Publication 26 and NCRP Report 91 are:
Organs or Tissues Weighting Factor
Gonads 0.25
Breasts 0.15
Red Bone Marrow 0.12
Lungs 0.12
Thyroid 0.03
Bone Surf 0.03
Remainder \1 0.30
-----------------------
\1 "Remainder" means the five other organs or tissue with
the highest dose (e.g., liver, kidney, spleen, thymus,
adrenal, pancreas, stomach, small intestine, upper large
intestine or lower large intestine). The weighting
factor for each remainder organ or tissue is 0.06. The
extremities, skin, and lens of the eye are excluded from
the "remainder" organs or tissue for assessment of
effective dose equivalent.
f. Extremity. Extremity includes hands and arms below the elbow or
feet and legs below the knee.
g. Monitoring. Actions intended to detect and evaluate radiological
conditions.
h. Non-Stochastic Effects. Effects such as the opacity of the lens of
the eye for which the severity of the effect varies with the dose,
and for which a threshold may exist.
i. Occupational Worker. An individual who is either a DOE or DOE
contractor employee; an employee of a subcontractor to a DOE
contractor; or an individual who visits to perform work for or in
conjunction with DOE or utilizes DOE facilities.
j. Quality Factor (Q). A modifying factor that is employed to derive
dose equivalent from absorbed dose (paragraph 9f(5)).
k. Radiation Worker. An occupational worker whose job assignment
requires work on, with, or in the proximity of radiation producing
machines or radioactive materials, and/or who has the potential of
being routinely exposed above 0.1 rem (0.001 sievert) per year,
which is the sum of the annual effective dose equivalent from
external irradiation and the committed effective dose equivalent
from internal irradiation.
l. Stochastic Effects. Malignant and hereditary disease for which the
probability of an effect occurring, rather than its severity, is
regarded as a function of dose without a threshold for radiation
protection purposes.
9. REQUIREMENTS FOR RADIATION PROTECTION OF OCCUPATIONAL WORKERS, UNBORN
CHILD, STUDENTS, MINORS, AND ONSITE MEMBERS OF THE PUBLIC.
a. Maintaining Radiation Exposures As Low As Reasonably Achievable
(ALARA). It is DOE's policy that exposures to radiation resulting
from DOE operations be maintained within limiting values given in
paragraph 9 and as far below all limiting values as reasonably
achievable. This policy applies to annual, committed, and
cumulative dose equivalents. Plans and programs used to assure that
occupational radiation exposures are maintained ALARA shall be
documented. The DOE publication PNL-6577, "Health Physics Manual of
Good Practices for Reducing Radiation Exposure to Levels that are As
Low As Reasonably Achievable (ALARA)," presents a guide on useful
practices for achieving the objective of the ALARA process.
b. Radiation Protection Standards for Internal and External Exposure
for Occupational Workers. The exposure of an Occupational worker to
radiation resulting from routine DOE activities shall not cause the
limiting values for assessed dose specified herein and summarized in
Figure 1 to be exceeded. Continued exposure of any worker over a
substantial portion of a working lifetime at or near the limiting
values for assessed dose to individual workers should be avoided.
(Note: Natural background and therapeutic and diagnostic medical
exposures are not to be included in dose records or in assessment of
dose against limiting values.)
(1) Stochastic Effects. The limiting value of annual effective
dose equivalent from both internal and external sources
received in any year by an occupational worker is 5 rem (0.05
sievert).
(2) Non-Stochastic Effects. The limiting value of annual dose
equivalent received in any year by an Occupational worker, for
individual organs and tissue is 15 rem (0.15 sievert) to the
lens of the eye or 50 rem (0.5 sievert) to any other organ,
tissue (including the skin of the whole body), or extremity of
the body.
(3) Unborn Child. The limiting value of annual dose equivalent
received by the unborn child from the period of conception to
birth (entire gestation period) as a result of occupational
exposure of a female occupational worker, who has notified her
employer in writing that she is pregnant, is 0.5 rem (0.005
sievert). Efforts should be made to avoid substantial
variation above the uniform monthly exposure rate that would
satisfy this limiting value. If the dose to the unborn child
is determined to have already exceeded 0.5 rem (0.005 sievert)
by the time a worker notifies her employer in writing of her
pregnancy, the worker shall not be assigned to tasks where
additional occupational exposure is likely. The limiting value
of dose equivalent to the unborn and the assignment of female
workers (who have declared pregnancy in writing to their
employer) to tasks where additional occupational exposure is
not likely does not create a basis for discrimination and
should be achieved in conformance with the provisions of Title
VII of the Civil Rights Act of 1964 [See Environmental
Protection Agency (1) - pages 2829 and 2832 of Federal
Register, Vol. 52, No. 17, 1987].
c. Planned Special Exposure. Planned special exposures (non-emergency)
that would result in an individual exceeding the annual effective
dose equivalent limit are allowed in highly unusual situations where
alternatives which would avoid higher exposures are unavailable or
impractical. Such planned special exposures, together with the
annual occupational dose received or anticipated to be received in
that year, shall not exceed 2 times the annual effective dose
equivalent limit specified in paragraph 9b(1). Planned special
exposures require the approval of the Head of the DOE Field
Organization. A second planned special exposure to the same
individual at any time requires the approval of the Assistant
Secretary for Environment, Safety, and Health (EH-1). Documentation
of planned special exposures shall be maintained in an individual's
occupational exposure history.
d. Radiation Protection Standards for Internal and External Exposure to
Minors and Students.
(1) Minors. An individual under age 18 shall neither be employed
in, nor allowed to enter, controlled areas in such a manner
that he or she exceeds a limiting value of 0.1 rem (0.001
sievert) per year from the sum of the committed effective dose
equivalent from internal irradiation and the annual effective
dose equivalent from external irradiation.
(2) Students. Students under age 18 shall not be exposed to
radiation during individually authorized educational activities
such that he or she exceeds a limiting value of 0.1 rem (0.001
sievert) per year from the sum of the committed effective dose
equivalent from internal irradiations and the annual effective
dose equivalent from external irradiation. This exposure shall
be considered a part of the limit for workers under age 18 and
not supplemental to it [i.e., where individuals underage 18 are
exposed to radiation both as a student and as a minor in a
year, their exposure as a student shall be added to their
exposure as a minor and the total is not to exceed the single
limiting value of 0.1 rem for minors].
___________________________________________________________________________
| |
| Stochastic Effects 5 rem (annual effective dose |
| ------------------ equivalent |
| |
| Non-Stochastic Effects |
| ---------------------- |
| Lens of eye 15 rem (annual dose equivalent) |
| |
| Extremity 50 rem (annual dose equivalent) |
| |
| Skin of the whole body 50 rem (annual dose equivalent) |
| |
| Organ or tissue 50 rem (annual dose equivalent) |
| |
| Unborn Child |
| ------------ |
| Entire gestation period 0.5 rem (annual dose equivalent) |
| |
|_________________________________________________________________________|
Figure 1
Radiation Protection Standards
Limiting Values for Assessed Dose from Exposure of
Occupational Workers to Radiation
e. Radiation Protection Standards for Public Entering a Controlled
Area. The effective dose equivalent received by any member of the
public resulting from exposure during direct onsite access at a DOE
facility shall not exceed a limiting value of 0.1 rem (0.001
sievert) per year from the committed effective dose equivalent from
internal irradiation plus the effective dose equivalent from any
external irradiation. In addition, exposures shall not cause a dose
equivalent to any tissue (including the skin and the lens of the
eye) to exceed 5 rem (0.05 sievert) per year for any member of the
public. Guidance for entry during emergency conditions is provided
in paragraph 9p of this Order.
f. Procedural Requirements.
(1) Combining Internal and External Dose Equivalent. The annual
effective dose equivalent to an individual shall be determined
by summing the annual effective dose equivalents from
internally deposited radionuclides and from external exposure
to radioactive material and/or radiation generating devices
resulting from DOE activities. When in-vivo and/or in-vitro
measurements confirm the retention of radionuclides in the
body, with respect to evaluating conformance with the limiting
value for occupational exposure, the annual effective dose
equivalent due to all radionuclides retained in the body from
these intakes shall be assessed for as long as the annual
effective dose equivalent is 10 mrem or greater. Exposures to
the skin, extremities, and lens of the eye are not included in
the determination of the annual effective dose equivalent. For
uniform external irradiation of the whole body, a weighting
factor (Wt) equal to one may be used. This whole body dose is
to be measured in accordance with the provisions in paragraph
9g(1). Non-uniform external and internal irradiation values of
Wt for organs and tissues are defined in paragraph 8e(12).
(2) Non-Uniform Exposure to Skin. For non-uniform exposures to
skin from x rays, beta radiation, or skin contamination, one of
the following assessments shall be made and recorded:
(a) When the area of skin exposed is >100 cm/2 the maximum
value of dose averaged over any area of 100 cm/2 is to be
assessed, recorded, and included in the annual skin
(shallow) dose equivalent.
(b) When the area of skin exposed is >10 cm/2 but <100 cm/2
the dose equivalent to that tissue is to be determined by:
H = fD
where: D is the maximum dose averaged over a 1 cm/2 of
skin and f is the fraction of skin exposed compared to 100
cm/2. In no case shall an "f" of <0.1 be used. This
value of dose is to be recorded and included in the annual
skin (shallow) dose equivalent.
(c) When the area of skin exposed is <10 cm/2 the maximum
value of dose averaged over any 1 cm/2 is to be assessed
and recorded in the individual's occupational exposure
history as a special entry but is not to be included in
the annual skin (shallow) dose equivalent.
(3) Emergency or Accidental Exposures. When an occupational worker
has been exposed to radiation in excess of the limits specified
in this Order as a result of an unplanned or accidental
situation, the decision to allow the worker to return to work
in a radiological area shall be made by operating management
based on advice from health physics and medical personnel and
the concurrence of the worker and shall be subject to the
approval of the DOE field organization manager. The dose
received in an unplanned or accidental situation is to be
documented in the radiation exposure record of the exposed
individual pursuant to paragraph 9m(2) and reported pursuant to
DOE 5484.1. The operating contractor is to verify to the head
of the responsible field organization that the conditions under
which the emergency or accidental exposures were received have
been eliminated. The resumption of operations following an
emergency or accidental exposure in excess of the occupational
limits specified in this Order shall be subject to the approval
of the head of the responsible field organization.
Investigations and reporting shall be conducted pursuant to DOE
5484.1 and DOE 5000.3.
(4) Air and Water Concentration Guides.
(a) Air. Derived air concentration (DAC) values for control
of the workplace are given in Attachment 1. They were
derived from the ICRP Publication 30 values for committed
effective dose equivalent values, translated to
conventional U.S. units of rem and curie. The ICRP
Publication 23 recommended annual inhalation volume for
male workers (40 hr/wk, 50 wk/yr) was assumed to be 2400
m/3. The DAC values or other air concentration values shall
not be used for the calculation of internal dose
equivalent received by a worker except for unusual
circumstances where bioassay data is unavailable or
inadequate.
(b) Water. Concentrations of radionuclides in drinking water
in controlled areas shall not exceed the standards given
in 40 CFR Part 141.
(5) Quality Factors. The dose equivalent limits specified in this
chapter are expressed in terms of rem; this requires that the
absorbed dose (expressed in rads) be multiplied by an
appropriate quality factor (Q). The quality factors to be used
for determining dose equivalent in rem are shown in Figures 2
and 3.
_________________________________________________________________________
| RADIATION TYPE QUALITY FACTOR (Q)* |
|-----------------------------------------------------------------------|
| X-rays, gamma rays, positrons, 1 |
| electrons (including tritium beta particles) |
| |
| Neutrons, <= 10 keV 3 |
| |
| Neutrons, > 10 keV 10 |
| |
| Protons and singly-charged particles 10 |
| of unknown energy with rest mass |
| greater than one atomic mass unit |
| |
| Alpha particles and multiple-charged 20 |
| particles (and particles of unknown |
| charge) of unknown energy |
| |
| -------------------- |
| |
| * Where spectral data is sufficient to identify the energy of the |
| neutrons, the Q values in Figure 3 may be used. |
|_______________________________________________________________________|
Figure 2
Quality Factors
_________________________________________________________________________
| _ NEUTRON |
| NEUTRON ENERGY Q FLUX DENSITY |
|-----------------------------------------------------------------------|
| MeV cm-2 s-1 |
| |
| 2.5 x 10-8 (thermal) 2 680 |
| 1 x 10-7 2 680 |
| 1 x 10-6 2 560 |
| 1 x 10-5 2 560 |
| 1 X 10-4 2 580 |
| 1 x 10-3 2 680 |
| 1 x 10-2 2.5 700 |
| 1 x 10-1 7.5 115 |
| 5 x 10-1 11 27 |
| 1 11 19 |
| 2.5 9 20 |
| 5 8 16 |
| 7 7 17 |
| 10 6.5 17 |
| 14 7.5 12 |
| 20 8 11 |
| 40 7 10 |
| 60 5.5 11 |
| 1 x 10 2 4 14 |
| 2 x 10 2 3.5 13 |
| 3 x 10 2 3.5 11 |
| 4 x 10 2 3.5 10 |
| |
| _ * __ |
| Mean quality factors, Q, and values of neutron flux density which, |
| in 40 hours, result in a maximum dose equivalent of 100 mrem. |
| |
| * Maximum value of Q in a 30-cm dosimetry phantom. |
|_______________________________________________________________________|
Figure 3
Quality Factors for Neutrons
g. Monitoring. Occupational workers shall be monitored, as
appropriate, to demonstrate compliance with the radiation protection
standards in paragraph 9b and to estimate the dose equivalents
received from external and internal sources of radiation.
Workplaces shall be routinely monitored, as appropriate, for
identification and control of potential exposure sources.
(1) External Radiation. Personnel dosimetry programs shall be
adequate to demonstrate compliance with the radiation
protection standards provided in paragraph 9b. Personnel
dosimeters shall be routinely calibrated and maintained and
shall meet the requirements of the DOE Laboratory Accreditation
Program for Personnel Dosimetry as specified in DOE 5480.15.
Personnel dosimetry shall be provided to radiation workers who
have the potential to exceed in a year any one of the following
from external sources:
(a) One hundred mrem (0.001 sievert) annual effective dose
equivalent to the whole body.
(b) Five rem (0.05 sievert) annual dose equivalent to the
skin.
(c) Five rem (0.05 sievert) annual dose equivalent to any
extremity.
(d) One and a half rem (0.015 sievert) annual dose equivalent
to the lens of the eye.
(2) Internal Radiation. Internal dose evaluation programs
(including routine bioassay programs) shall be adequate to
demonstrate compliance with the radiation protection standards
in paragraph 9b. Such programs are required for radiation
workers exposed to surface or airborne radioactive
contamination where the worker could receive 0.1 rem (0.001
sievert) annual effective dose equivalent from all intakes of
all radionuclides from occupational sources, or if any organ or
tissue dose equivalent could exceed 5 rem (0.05 sievert) annual
dose equivalent.
(3) Workplace.
(a) Air Monitoring. Ambient air monitoring shall be performed
in occupied areas with the potential to exceed 10 percent
of any derived air concentration values given in
Attachment 1. Representative ambient air monitoring
samples should be taken in strategic locations to detect
and evaluate airborne radioactive material at work
locations. Data obtained from air monitoring shall be
used for assessing the control of airborne radioactive
material in the workplace; it should not normally be used
to evaluate the dose equivalent to radiation workers. Air
monitors shall be routinely calibrated and maintained, and
should be capable of measuring one DAC when averaged over
8 hours (8 DAC-hours).
(b) Radiation Monitoring. Appropriate stationary (area)
and/or portable radiation instruments shall be available
and used to measure dose rates for the purpose of
controlling exposure to radiation. These instruments
shall be routinely calibrated and maintained. The
combination of instruments used shall provide capability
to measure types of radiation (neutron, gamma, beta, or
x-radiation) and dose rates characteristic of that which
could be encountered at that facility.
(4) Contamination Control and Monitoring. Appropriate instruments
and techniques shall be used to provide contamination
monitoring and control as described below:
(a) Workplace Surfaces Outside Radiological Areas should be
maintained essentially free of removable contamination but
in any case contamination shall not exceed the levels
defined in Attachment 2. Acceptable levels for total
(fixed plus removable) contamination are also listed in
Attachment 2.
(b) Workplace Surfaces in Radiological Areas shall be posted
(paragraph 9k) and controlled, as appropriate. The degree
of control from simple (e.g., shoe covers and lab coat) to
complex (e.g., multiple layers of protective clothing and
respiratory protection) should be based on the specific
contaminants present and the level of contamination.
(c) Personnel and Personal Property Contamination Monitoring
shall be provided, as appropriate, and used immediately
prior to or after exits from radiological areas
established to control surface or airborne radioactive
contamination. If monitoring is performed after the exit,
appropriate controls shall be implemented to prevent the
loss of control of contamination. Detectable
contamination on personnel and personal property should be
removed by appropriate decontamination methods.
h. Methods of Estimating Dose Equivalent. Methods of estimating the
dose equivalent from external and internal sources of radiation are
to be appropriate to the workplace conditions and consistent with
the recommendations of NCRP, ICRP, and EPA.
i. Releases of Materials and Equipment from Radiological Areas. The
following requirements apply for the release of materials and
equipment from radiological areas for conditional use in controlled
areas. In all cases, contaminated property shall be cleaned as
thoroughly as practical before release. These requirements are not
applicable to the release of materials or equipment for unrestricted
use since such use could result in exposure to the general public.
(NOTE: Requirements contained in this Order do not pertain to
either induced radioactivity or decontamination and decommissioning
release limits.)
(1) Material and equipment in radiological areas established to
control surface or airborne radioactive material shall be
treated as radioactive material and shall not be released from
radiological areas to controlled areas if any of the following
conditions exist:
(a) Measurements of accessible surfaces show that either the
total or removable contamination levels exceed the guides
specified in Attachment 2; or
(b) Prior use suggests that the contamination levels on
inaccessible surfaces are likely to exceed the guides
specified in Attachment 2.
(2) Material and equipment exceeding the total and removable
contamination levels specified in Attachment 2 shall be
conditionally released for movement onsite from one
radiological area for immediate placement in another
radiological area only if appropriate monitoring and control
procedures are established and exercised.
(3) Under exceptional conditions, material and equipment with fixed
contamination that exceed the limits specified in Attachment 2
may be released for use in controlled areas outside
radiological areas. As a condition of such release, the
materials shall be routinely monitored, clearly labeled and/or
tagged to alert personnel of the contaminated status, and have
appropriate administrative procedures established and exercised
to maintain control of these items.
(4) The records for release of potentially contaminated material
and equipment shall describe the property, the date of the last
monitoring operation, the identity of the individual who
performed the monitoring operation, the type and identification
number of the monitoring instrument used, and the results of
the monitoring operation.
j. Design and Control. Radiation exposure rates in controlled
workplace areas should be reduced to as low as reasonably achievable
levels by proper facility design and control. The primary means for
maintaining exposures as low as reasonably achievable are to be
through physical controls, e.g., confinement, ventilation, remote
handling, and shielding. Administrative controls and procedural
requirements are to be considered supplemental means to achieve
control.
(1) Design. During the design of facilities, the following
objectives shall be applied:
(a) Optimization. Optimization principles, as discussed in
ICRP Publication 37, are to be utilized in developing and
justifying facility design and physical controls.
(b) External Radiation Exposure. The design objectives for
personnel exposure from external sources of radiation in
continuously occupied controlled areas are ALARA and not
exceeding 0.5 mrem (5 microsieverts) per hour on average.
The design objectives for exposure rates for potential
exposure to a radiation worker where occupancy is
generally not continuous are ALARA and not exceeding 20
percent of the applicable standard in paragraphs 9b(1) and
(2).
(c) Internal Radiation Exposure. As a design objective,
exposure of personnel to inhalation of airborne
radioactive materials is to be avoided under normal
operating conditions to the extent reasonably achievable.
This will normally be accomplished by confinement and
ventilation.
(d) Maintenance. Decontamination, and Decommissioning. Ease
of maintenance and decontamination and decommissioning is
to be considered in facility design and selection of
materials.
(2) Control. During routine operations, the combination of design
and control procedures shall provide that, with respect to the
radiological workplace, the anticipated magnitude of the
prospective committed effective dose equivalent from intakes
plus any effective dose equivalent from external exposure will
not exceed 5 rem (0.05 sievert) in a year, and the anticipated
magnitude of the committed dose equivalent to any organ or
tissue from intakes plus any dose equivalent from external
exposure will not exceed 50 rems (0.5 sievert) in a year.
Compliance with these requirements shall be demonstrated
through appropriate workplace monitoring pursuant to the
provisions of paragraph 9g(3).
k. Posting and Labeling. Areas in DOE nuclear facilities shall be
posted in accordance with the provisions given below. Radioactive
material and/or its container shall be individually labeled where
normal posting of the area and control of the material would not
provide adequate protection. The design of signs, labels, and the
radiation symbol shall conform to ANSI N12.1-1971 and ANSI
N2.1-1971. The background color is to be yellow; the symbol color
may be black or magenta.
(1) Controlled Area. The access to any controlled area where
radioactive materials or elevated radiation fields may be
present shall be clearly and conspicuously posted as a
controlled area. The type of sign used may be selected by
the contractor with the approval of the field organization
to avoid conflict with local security requirements.
(2) Radiological Area.
(a) Posting for External Radiation. The access to any area
where an individual can at anytime during normal
operations receive a dose equivalent greater than 5 mrem
(50 microsieverts) in 1 hour at 30 centimeters from the
radiation source or any surface through which radiation
penetrates shall be posted as below. In addition, the
anticipated dose rate or range of dose rates shall be
included on or in conjunction with each of the signs, as
appropriate.
1 "Radiation Area" for any area within a controlled area
where an individual can receive a dose equivalent
greater than 5 mrem (50 microsieverts) but less than
100 mrem (1 millisievert) in 1 hr at 30 cm from the
radiation source or from any surface through which the
radiation penetrates,
2 "High Radiation Area" for any area within a controlled
area where an individual can receive a dose equivalent
of 100 mrem or greater (0.001 sievert) but less than 5
rem (0.05 sievert) in 1 hr at 30 cm from the radiation
source or from any surface through which the radiation
penetrates, and
3 "Very High Radiation Area" for any area within a
controlled area where an individual can receive a dose
of 5 rem (0.05 sievert) or greater in 1 hour at 30 cm
from the radiation source or from any surface through
which the radiation penetrates.
(b) Posting for Airborne Radioactive Material. The access to
any area where airborne radioactive material
concentrations greater than 1/10 of the derived air
concentrations (Attachment 1) are present shall be clearly
and conspicuously posted with a sign that identifies the
radiological conditions which exist (e.g., "Airborne
Radioactivity Area"). The type of sign used shall be
consistent with the radiation protection control policies
established at the facility and may be selected by the
contractor with the approval of the field organization.
(c) Posting for Surface Contamination. The access to any area
where surface contamination levels greater than 10 times
those specified in Attachment 2 are present shall be
clearly and conspicuously posted with a sign that
identifies the radiological conditions which exist (e.g.,
"Contamination Area"). The type of sign used shall be
consistent with the radiation control policies established
at the facility and may be selected by the contractor with
the approval of the field organization.
l. Entry Control Program. An appropriate entry control program shall
be established for radiological areas. This should include a buffer
area prior to entry to a radiological area where appropriate. The
level of control should be consistent with the degree of hazard.
Signs and barricades, control devices on entrances, conspicuous
visual and/or audible alarms, locked entrance ways, and/or
administrative procedures should be used as appropriate to ensure
that personnel entry into radiological areas is controlled.
Step-off pads and protective clothing shall be required for entry to
contaminated areas. For very high radiation areas, the entry
control program shall include at a minimum one of the following:
(1) Control devices on each entrance or access point which function
automatically to prevent entry when a very high radiation area
exists; permit entry only after the radiation level is reduced
below 0.1 rem (0.001 sievert) per hour; and prevent use or
operation of the radiation source, thereby preventing the
existence of a very high radiation area, while an individual is
in the area.
(2) A control device which energizes a conspicuous visible or
audible alarm signal so that the individual entering the very
high radiation area through a failed control device is aware of
the radiation level and radiation protection personnel are
aware of the entry. Administrative procedures shall define the
required actions of personnel when alarms are activated.
(3) Locked entry ways, except during periods when access to the
area is required, with positive control over and radiation
surveys made for the initial entry and periodically as
necessary.
(4) Control devices that will automatically generate audible and
visible alarm signals to alert personnel in the area before use
or operation of the radiation source and in sufficient time to
permit evacuation of the area or the activation of a secondary
control device which will prevent use or operation of the
source.
m. Records. As a minimum, the records specified below of the radiation
protection program and dosimetry records for all individuals for
whom monitoring is provided shall be generated and maintained,
commencing with the effective date of this Order. Information and
data developed pursuant to this Order shall be retained consistent
with the requirements of DOE 1324.2A, RECORDS DISPOSITION.
(1) ALARA. Records of ALARA programs shall be maintained by field
organizations and operating contractors to demonstrate the
adequacy of the ALARA plans and programs and their
implementation.
(2) Individual Occupational Dose Records. Individual occupational
internal and external dose records and records of the programs
used to assess individual doses shall be generated and
maintained sufficient to provide appropriate reports to the
employee, management, and those required by DOE 5484.1.
Efforts should be made to obtain records of occupational
exposure received prior to employment at the site. Records
should be readily available for all current employees. As a
minimum, the following data shall be recorded and retained for
individuals for whom monitoring, as appropriate, was provided.
(a) Internal Exposure.
1 Annual effective dose equivalent received during the
year from radioactive material deposited in the body;
2 Annual dose equivalent to organ or tissue of concern
received during the year from radioactive material
deposited in the body;
3 Committed effective dose equivalent from intakes
occurring during the year;
4 Committed dose equivalent to organ or tissue of concern
from intakes occurring during the year.
(b) External Exposure.
1 Annual effective dose equivalent from external sources
of radiation received during the year.
2 Annual dose equivalent to the lens of the eye.
3 Annual dose equivalent to the skin.
4 Annual dose equivalent to the extremities received
during the year, including: (1) hands and forearm
below the elbow and (2) feet and legs below the knee.
(c) Summation of Internal and External Dose Equivalents.
1 Summation of the annual effective dose equivalents
received from external and internal sources during the
year.
2 Cumulative annual effective dose equivalent received
from external and internal sources while employed at
the facility, since the effective date of this Order.
(d) Programs to Determine Individual Exposures. Data
necessary to support or re-calculate doses at a later date
shall be maintained pursuant to Section 4 of ANSI
N13.6-1972.
(3) Monitoring and Area Control Records. Records that establish
the conditions under which individuals were exposed, such as
facility radiological conditions (as generated by the
monitoring programs) and surveys for the release of personal
property and workplace surfaces, shall be kept to provide a
chronological, historical record pursuant to Section 5 of ANSI
N13.6-1972.
(4) Monitoring Methods Records. Records shall be kept to document
the appropriateness, quality, and accuracy of monitoring
methods, techniques, and procedures in use during any given
period pursuant to Section 6 of ANSI N13.6-1972. Changes in
equipment, techniques, and procedures are to be documented and
the documents maintained.
(5) Training Records. Training records of plant employees,
radiation workers, and radiation safety personnel shall be
retained to document the level of understanding and proficiency
of personnel who work with radioactive materials.
Certification of successful completion of training programs and
performance records should also be retained.
n. Reports to Employees. Records of exposure should be made available
to all occupational workers on an individual basis and should be
provided to terminated employees as soon as the data is available
but within 90 days of termination. A summary of annual, cumulative,
and committed effective dose equivalent shall be provided to each
radiation worker on an annual basis. The cumulative effective dose
equivalent is the sum of the annual effective dose equivalents
recorded for each year of employment since the effective date of the
Order. Detailed information concerning a worker's exposure shall be
made available to the worker upon the request of the worker,
consistent with the provisions of the Privacy Act (5 USC 552a).
o. Radiation Safety Training.
(1) All Employees. All occupational workers who may enter a
controlled area at a DOE facility shall receive an orientation
in radiation safety within 1 month of their initial assignment
to and prior to potential exposure to radiation at that
facility. Retraining shall be provided when there are
significant changes to radiation protection policies and
procedures which affect general plant employees and should be
provided every 2 years. Generic training (not specific to a
facility) in all or some of the topics listed below may be
waived provided: this training has been received at another
DOE facility; there is provision of proof-of-training in the
form of a certification document containing the individual's
name, date of training, and specific topics covered; and an
appropriate official has certified the training of the
individual. The level of training is to be commensurate with
the employee's job assignment with the initial orientation
including, but not limited to:
(a) The risk of low-level occupational radiation exposure,
including cancer and genetic effects;
(b) The risk of prenatal radiation exposure;
(c) Basic radiation protection concepts;
(d) DOE and company radiation protection policies and
procedures;
(e) Employee and management responsibilities for radiation
safety;
(f) Emergency procedures.
(2) Radiation Workers. Radiation worker training programs and
retraining shall be established and conducted at a sufficient
frequency (not to exceed a period of 2 years) to familiarize
the worker with the fundamentals of radiation protection and
the ALARA process. Training should include both classroom and
applied training. The training shall be concurrent with
assignment as a radiation worker only if the worker is
accompanied by and under the direct supervision of a trained
radiation worker; otherwise, the training shall precede
assignment as a radiation worker.worker. Generic training (not
specific to a facility) in all or some of the topics listed
below may be waived provided: this training has been received
at another DOE facility; there is provision of
proof-of-training in the form of a certification document
containing the individual's name, date of training, and
specific topics covered; and an appropriate official has
certified the training of the individual. The knowledge of
radiation safety fundamentals possessed by radiation workers
should be certified by examination prior to an unsupervised
assignment. The training should emphasize procedures specific
to an individual's job assignment. Additionally, the level of
training in the following topics is to be commensurate with
each worker's assignment:
(a) Radioactivity and radioactive decay;
(b) Characteristics of ionizing radiation;
(c) Man-made radiation sources;
(d) Acute effects of exposure to radiation;
(e) Risks associated with occupational radiation exposures;
(f) Special considerations in the exposure of women of
reproductive age;
(g) Dose-equivalent limits;
(h) Mode of exposure--internal and external;
(i) Dose-equivalent determinations;
(j) Basic protective measures--time, distance, shielding;
(k) Specific plant procedures for maintaining exposure as low
as is reasonably achievable;
(l) Radiation survey instrumentation--calibration and
limitations;
(m) Radiation monitoring programs and procedures;
(n) Contamination control, including protective clothing and
equipment and workplace design;
(o) Personnel decontamination;
(p) Emergency procedures;
(q) Warning signs and alarms;
(r) Responsibilities of employees and management;
(s) Interaction with radiation protection staff;
(t) Operational procedures associated with specific job
assignments (e.g., radiation generating machines, glove
boxes).
(3) Radiation Protection Technician. Radiation protection
technician training and retraining programs shall be
established and conducted at a sufficient frequency, not to
exceed every 2 years, to familiarize technicians with the
fundamentals of radiation protection and the proper procedures
for maintaining exposures ALARA. This program shall include
both classroom and applied training and shall precede or be
concurrent with assignment as a radiation protection technician
while under the supervision of a trained individual. The
knowledge of radiation safety fundamentals possessed by
radiation protection technicians should be certified by
examination prior to an unsupervised work assignment. The
training program should include the topics listed in the
paragraph (2) above and should emphasize procedures specific to
the facility where the technician is assigned. The level of
training in each topic is to be commensurate with the
technician's assignment.
p. Guidance and Requirements for Emergency Exposure During Rescue and
Recovery Activities.
(1) Purpose. This paragraph provides emergency action guidance for
determining appropriate actions for the rescue and recovery of
persons and the protection of health and property in the event
of an emergency.
(2) General Considerations.
(a) Controlling exposure to radiation during rescue and
recovery actions is extremely complex. Multiple hazards
and alternate methods are to be taken into account; and
prompt, sound judgment and flexibility of action are
crucial to the success of any emergency actions. The risk
of injury to those persons involved in the rescue and
recovery activities should be minimized, to the extent
practical. However, the control of radiation exposures
should be consistent with the immediate objectives of
saving human life, recovering deceased victims, and/or
protection of health and property.
(b) To avoid unnecessarily restricting action, a rigid upper
limit of exposure for lifesaving action is not specified;
rather, judgment is left up to the officials in charge to
evaluate any proposed action involving further radiation
exposure. The evaluation should consider risk versus
benefit, i.e., weighing the risks of radiation insults,
actual or potential, against the benefits [social,
economic, etc.] to be gained. Essential elements in risk
determinations include potential exposure, biological
consequences related to the exposure, and the number of
people involved.
(c) These instructions also recognize that accident situations
involving the saving of lives will require different basis
for action than those required to recover deceased victims
or to protect property. In the latter instances, the
amount of exposure expected to be received by persons
should be controlled as much as possible within
occupational exposure limits.
(d) Any rescue action that might involve substantial personal
risk should be performed by volunteers. When feasible,
volunteers should be evaluated with respect to age and
previous exposure history. Each emergency worker should
be advised of the known or anticipated hazards prior to
participation by the person onsite having the emergency
action responsibility.
(3) Emergency Situations. Specific dose criteria and judgment
factors are set forth for the three types of emergency action:
Type 1, saving of human life; Type 2, recovery of deceased
victims; and Type 3, protection of health and property.
(a) Saving of Human Life.
1 Attempts to rescue victims of an incident should be
regarded in the same context as any other emergency
action involving the rescue of victims, regardless of
the type of hazard involved.
2 If the victim is considered to be alive, the course of
action should be determined by the person onsite having
the emergency action responsibility.
3 The potential amount of exposure to rescue personnel
for each specific Type 1 emergency action shall be
evaluated by the person onsite having the emergency
action responsibility. The emergency situation should
be immediately evaluated and an exposure objective
should be established for the rescue mission. The
evaluation of the inherent risks should consider:
a The reliability of the prediction of radiation
injury from measured/estimated dose rates. In this
context, consideration should be given to the
uncertainties associated with the specific
instruments and techniques used to estimate the dose
rate. This is especially crucial when the estimated
dose approximates 100 rad (1 gray) or more.
b The effects of acute external and/or internal
exposure.
c The capability to reduce risk through physical
mechanisms such as the use of protective equipment,
remote manipulation equipment, or similar means.
d The probability of success of the rescue action.
(b) Recovery of Deceased Victims.
1 The recovery of deceased victims should be well
planned. Except as provided in subparagraph 3 below,
the amount of radiation exposure received by persons in
recovery operations shall be controlled within existing
occupational exposure limits.
2 When fatalities are located in inaccessible areas due
to high direct radiation fields, and when the recovery
mission would result in exposure in excess of
occupational exposure limits specified in this chapter,
special remote recovery devices should be used to
retrieve bodies, as appropriate.
3 When it is not feasible to recover bodies without
personnel entering the area, the official in charge may
determine it necessary to exceed the occupational
exposure limits specified in this chapter. The planned
exposure of an individual participating in the recovery
should not exceed 10 rem (0.1 sievert) per year.
(c) Protection of Health and Property. When the risk
(probability and magnitude) of the radiation hazard either
bears significantly on the state of health of people, or
may result in loss of property, so that immediate remedial
action is needed, the following criteria should apply:
1 When the official in charge deems it essential to
reduce a potential hazard to protect health or prevent
a substantial loss of property, a planned exposure
objective not to exceed 10 rem (0.1 sievert) per year
may be permitted for individuals participating in the
operation. However, under special circumstances, the
official in charge of emergency action at the incident
may elect to permit volunteers an emergency exposure
objective not to exceed 25 rem (0.25 sievert) in any
year.
2 When the risk of radiation following the incident is
such that life might be in jeopardy, or that there
might be severe effects on health or the public or loss
of property inimical to the public safety, the criteria
for saving of human life shall apply.
q. Nuclear Accident Dosimetry. These requirements are applicable to
DOE contractor installations possessing sufficient quantities and
kinds of fissile material to potentially constitute a critical mass
as defined in DOE 5480.5, and where the excessive exposure of
personnel to radiation from a nuclear accident is possible.
(1) Basic Elements. The basic elements of nuclear accident
dosimetry shall include:
(a) A method to conduct initial "screening" of personnel
involved in nuclear accidents to determine if they have
received a significant radiation exposure.
(b) Methods for analysis of biological materials (including
sodium-24 activity in blood and phosphorus-32 activity in
hair).
(c) A system of fixed units capable of yielding estimated
radiation dose and the approximate neutron spectrum at
their locations.
(d) Personnel dosimeters capable of furnishing sufficient
information to determine neutron and gamma dose and/or
dose equivalent.
(e) Counting facilities to evaluate fixed and/or personnel
dosimeters, sodium in blood, and phosphorus in hair.
(2) Fixed Nuclear Accident Dosimeter Units.
(a) The fixed unit shall be capable of determining neutron
dose in rad (gray) with an accuracy of +/- 25 percent.
(b) The fixed unit shall be capable of providing the
approximate neutron spectrum to permit the conversion of
rad to rem.
(c) The dose range capability of the neutron components of the
fixed unit shill extend from 10 rad (0.1 gray) to about
10,000 rad (100 gray).
(d) The gamma ray components of the fixed unit shall be
capable of measuring fission gamma radiation in the
presence of neutrons with an accuracy of approximately +/-
20 percent.
(e) The dose range capability of the gamma components shall
extend from 10 rem (0.10 sievert) to about 10,000 rem (100
sievert).
(f) The number of dosimeter units needed and their placement
will depend on the nature of the operation, structural
design of the facility, and accessibility of areas to
personnel. Consideration should be given to the need for
remote retrieval mechanisms. The number and placement of
dosimeters shall be periodically re-evaluated, as
appropriate, to ensure that modifications to facility
design and use have not affected performance. An analysis
that demonstrates that the dosimeters and their placement
will satisfy the performance criteria contained in
paragraph q shall be documented. The analysis shall
include the number of units, their location, and effect of
intervening shielding. Ease of recovery after a
criticality event should be considered in the placement of
the fixed units.
(3) Personnel Nuclear Accident Dosimeter Units.
(a) Personnel Nuclear Accident Dosimeter Units shall be worn
by all personnel who enter a controlled area that contains
locations requiring an installed criticality alarm system
as given in paragraph 11c(3)(g) of DOE 5480.5.
(b) Dosimeters worn by the worker should be capable of
determining gamma dose from 10 rad (0.1 gray) to 1000 rad
(10 gray) with an accuracy of +/- 20 percent and neutron
dose from 1.0 rad (0.01 gray) to 1000 rad (10 gray) with
an accuracy of +/- 30 percent without dependence upon
fixed unit data.
r. Contractor Internal Audits.
(1) Contractor internal audits of all functional elements of the
radiation protection program shall be conducted as often as
necessary but no less frequently than every 3 years. The audit
should include, but is not limited to:
(a) External dosimetry;
(b) Internal dosimetry;
(c) Portable and fixed instrumentation;
(d) Respirators;
(e) Contamination control;
(f) Radiological monitoring;
(g) ALARA program;
(h) Nuclear accident dosimetry;
(i) Source material control;
(j) X-ray protection;
(k) Training;
(l) Posting;
(m) Records.
(2) In conducting such audits, the guidelines set forth in DOE
5482.1 shall be followed.
BY ORDER OF THE SECRETARY OF ENERGY:
LAWRENCE F. DAVENPORT
Assistant Secretary
Management and Administration
DERIVED AIR CONCENTRATIONS FOR CONTROLLING
RADIATION EXPOSURE TO WORKERS AT DOE FACILITIES
The derived air concentrations (DAC) for limiting radiation exposures
through inhalation of radionuclides by workers are listed in Attachment 1,
page 4, Figure 1. The values are based on either a stochastic (committed
effective dose equivalent) dose limit of 5 rem (0.05 Sv) or a nonstochastic
(organ) dose limit of 50 rem (0.5 Sv) per year, whichever is more limiting.
(Note: the 15 rem [0.15 Sv] dose limit for the lens of the eye does not
appear as a critical organ dose limit.)
Table 1 contains five columns of information: (1) radionuclide; (2) inhaled
air DAC for lung retention class D (microCi/mL); (3) inhaled air DAC for
lung retention class W (microCi/mL); (4) inhaled air DAC for lung retention
class Y (microCi/mL); and (5) an indication of whether or not the DAC for
each class is controlled by the stochastic (effective dose equivalent) or
nonstochastic (tissue) dose. The classes D, W, and Y have been established
by the International Commission on Radiological Protection (ICRP) to
describe the clearance of inhaled radionuclides from the lung. This
classification refers to the approximate length of retention in the
pulmonary region. Thus, the range of half-times is less than 10 days for
class D (days), from 10 to 100 days for class W (weeks), and greater than
100 days for class Y (years). The DACs in Table 1 are listed by
radionuclide, in order of increasing atomic mass, and are based on the
assumption that the particle size distribution of the inhaled material is
unknown. For this situation, the ICRP recommends that an assumed particle
size distribution of 1 micro m be used. For situations where the particle
size distribution is known to differ significantly from 1 micro m,
appropriate corrections (as described in the DOE report Internal Dose
Conversion Factors for Calculation of Dose to the Public) 1/ can be made to
both the estimated dose to workers and the DACs.
Alternative absorption factors and lung retention classes for specific
compounds are listed by element in Table 2 for cross-referencing with the
inhalation DACs in Table 1. The data shown in Figure 2 are listed by
element in alphabetical order.
The following assumptions and procedures were used in calculating these DAC
values for inhalation by workers:
(1) The worker is assumed to inhale 2,400 m/3 of air during a 2000-hour
work year, as defined by the ICRP in its Publication No. 23. 2/
____________________
1/ U.S. Department of Energy (DOE). 1988. Internal Dose Conversion
Factors for Calculation of Dose to the Public. Washington, D.C.
2/ International Commission on Radiological Protection (ICRP). 1975.
ICRP Publication 23: Report of the Task Group on Reference Man.
Pergamon Press, New York, New York.
(2) The internal dose factors used in calculating the DAC values
were taken from the report Internal Dose Conversion Factors for
Calculation of Dose to the Public. 1/ These factors are based on the
metabolic data and dosimetry models recommended by the ICRP in its
Publication No. 30. 3/
The air immersion DAC values shown in Table 3 are based on a stochastic
limit of 5 rem (0.05 Sv) per year or a nonstochastic (organ) dose limit of
50 rem (0.5 Sv) per year. Figure 3 contains three columns of information:
(1) radionuclide; (2) half-life in units of seconds (s), minutes (min),
hours (h), days (d), or years (y); and (3) air immersion DAC (micro Ci/mL).
The data in Table 3 are listed by radionuclide in order of increasing atomic
mass. The air immersion DACs were calculated for a continuous, nonshielded
exposure via immersion in a semi-infinite atmospheric cloud. The dose
conversion factors used to calculate the DAC values for air immersion were
taken from the DOE report External Dose-Rate Conversion Factors for
Calculation of Dose to the Public. 4/ The DAC value for air immersion
listed in Table 3 for a given radionuclide is determined either by a limit
on annual effective dose equivalent, which provides a limit on stochastic
radiation effects, or by a limit on annual dose equivalent to any organ,
which provides a limit on nonstochastic radiation effects. For most of the
radionuclides listed in Table 3, the DAC value is determined by the limit on
annual effective dose equivalent. Thus, the few cases where the DAC value
is determined by the limit on annual dose equivalent to skin are indicated
in the figure by an appropriate footnote. Again, the DACs listed in Figure
3 account only for immersion in a semi-infinite cloud and do not account for
inhalation or ingestion exposures. Three classes of radionuclides are
included in the air immersion DACs given in Figure 3, as described below.
(1) Class 1. The first class of radionuclides includes selected noble
gases and short-lived activation products that occur in gaseous form.
For these radionuclides, inhalation doses are negligible compared to
the external dose from immersion in an atmospheric cloud.
(2) Class 2. The second class of radionuclides includes those for which a
DAC value for inhalation has been calculated (using the ICRP inhalation
dose equivalent factors), but for which the DAC value for external
exposure to a contaminated atmospheric cloud is more restrictive (i.e.,
results in a lower DAC value). These radionuclides generally have
half-lives of a few hours or less, or are eliminated from the body
following inhalation sufficiently rapidly to limit the inhalation dose.
____________________
3/ International Commission on Radiological Protection (ICRP). 1979-1982.
ICRP Publication 30: Limits for Intakes of Radionuclides by Workers.
Parts 1 to 3 and Supplements 2(3/4) through 8(4), Pergamon Press, New
York, New York.
4/ U.S. Department of Energy (DOE). 1988. External Dose-Rate Conversion
Factors for Calculation of Dose to the Public. Washington, D.C.
(3) Class 3. The third class of radionuclides includes selected isotopes
with relatively short half-lives that were not considered in ICRP
Publication 30. These radionuclides typically have half-lives that are
less than 10 minutes, they do not occur as a decay product of a
longer-lived radionuclide, or they lack sufficient decay data to permit
internal dose calculations. These radionuclides are also typified by a
radioactive emission of highly intense, high-energy photons and rapid
removal from the body following inhalation.
The DAC values are given for individual radionuclides. For known mixtures
of radionuclides, the sum of the ratio of the observed concentration of a
particular radionuclide and its corresponding DAC for all radionuclides in
the mixture must not exceed 1.0.
Table 1
Derived Air Concentrations (DAC) for Controlling Radiation Exposures to
Workers at DOE Facilities
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D / W / Y)
--------------- ------------ ------------ ------------ -----------
H-3 (Water) 2/ 2.E-05 2.E-05 2.E-05 St/St/St
H-3 (Elemental) 2/ 5.E-01 5.E-01 5.E-01 St/St/St
Be-7 - 3/ 9.E-06 8.E-06 /St/St
Be-10 - 6.E-08 6.E-09 /St/St
C-11 (Org) 2/ 2.E-04 2.E-04 2.E-04 St/St/St
C-11 (CO) 2/ 5.E-04 5.E-04 5.E-04 St/St/St
C-11 (CO2) 2/ 3.E-04 3.E-04 3.E-04 St/St/St
C-14 (Org) 2/ 1.E-06 1.E-06 1.E-06 St/St/St
C-14 (CO) 2/ 7.E-04 7.E-04 7.E-04 St/St/St
C-14 (CO2) 2/ 9.E-05 9.E-05 9.E-05 St/St/St
F-18 3.E-05 4.E-05 3.E-05 St/St/St
Na-22 3.E-07 - - St/ /
Na-24 2.E-06 - - St/ /
Mg-28 7.E-07 5.E-07 - St/St/
Al-26 3.E-08 3.E-08 - St/St/
Si-31 1.E-05 1.E-05 1.E-05 St/St/St
Si-32 1.E-07 5.E-08 2.E-09 St/St/St
P-32 4.E-07 2.E-07 - St/St/
P-33 3.E-06 1.E-06 - St/St/
S-35 7.E-06 9.E-07 - St/St/
S-35 (Gas) 6.E-06 - /St/
Cl-36 1.E-06 J.E-07 - St/St/
Cl-38 2.E-05 2.E-05 - St/St/
Cl-39 2.E-05 2.E-05 - St/St/
K-40 2.E-07 - - St/ /
K-42 2.E-06 - - St/ /
K-43 4.E-06 - - St/ /
K-44 3.E-05 - - St/ /
K-45 5.E-05 - - St/ /
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D / W / Y)
--------------- ------------ ------------ ------------ -----------
Ca-41 - 2.E-06 - /E /
Ca-45 - 3.E-07 - /St/
Ca-47 - 4.E-07 - /St/
Sc-43 - - 1.E-05 / /St
Sc-44m - - 3.E-07 / /St
Sc-44 - - 5.E-06 / /St
Sc-46 - - 1.E-07 / /St
Sc-47 - - 1.E-06 / /St
Sc-48 - - 6.E-07 / /St
Sc-49 - - 2.E-05 / /St
Ti-44 5.E-09 1.E-08 2.E-09 St/St/St
Ti-45 1.E-05 1.E-05 1.E-05 St/St/St
V-47 4.E-05 4.E-05 - St/St/
V-48 4.E-07 3.E-07 - St/St/
V-49 1.E-05 7.E-06 - BS/St/
Cr-48 5.E-06 3.E-06 3.E-06 St/St/St
Cr-49 3.E-05 4.E-05 4.E-05 St/St/St
Cr-51 2.E-05 1.E-05 8.E-06 St/St/St
Mn-51 2.E-05 2.E-05 - St/St/
Mn-52m 4.E-05 4.E-05 - St/St/
Mn-52 5.E-07 4.E-07 - St/St/
Mn-53 5.E-06 5.E-06 - BS/St/
Mn-54 4.E-07 3.E-07 - St/St/
Mn-56 6.E-06 9.E-06 - St/St/
Fe-52 1.E-06 1.E-06 - St/St/
Fe-55 8.E-07 2.E-06 - St/St/
Fe-59 1.E-07 2.E-07 - St/St/
Fe-60 3.E-09 8.E-09 - St/St/
Co-55 - 1.E-06 1.E-06 /St/St
Co-56 - 1.E-07 8.E-08 /St/St
Co-57 - 1.E-06 3.E-07 /St/St
Co-58m - 4.E-05 3.E-05 /St/St
Co-58 - 5.E-07 3.E-07 /St/St
Co-60m - 2.E-03 1.E-03 /St/St
Co-60 - 7.E-08 1.E-08 /St/St
Co-61 - 3.E-05 2.E-05 /St/St
Co-62m - 7.E-05 7.E-05 /St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Ni-56 (Inorg) 8.E-07 5.E-07 - St/St/
Ni-56 (Vapor) - 5.E-07 - /St/
Ni-57 (Inorg) 2.E-06 1.E-06 - St/St/
Ni-57 (Vapor) - 3.E-06 - /St/
Ni-59 (Inorg) 2.E-06 3.E-06 - St/St/
Ni-59 (Vapor) - 8.E-07 - /St/
Ni-63 (Inorg) 7.E-07 1.E-06 - St/St/
Ni-63 (Vapor) - 3.E-07 - /St/
Nl-65 (Inorg) 1.E-05 1.E-05 - St/St/
Ni-65 (Vapor) - 7.E-06 - /St/
Ni-66 (Inorg) 7.E-07 3.E-07 - St/St/
Ni-66 (Vapor) - 1.E-06 - /St/
Cu-60 4.E-05 5.E-05 4.E-05 St/St/St
Cu-61 1.E-05 2.E-05 1.E-05 St/St/St
Cu-64 1.E-05 1.E-05 9.E-06 St/St/St
Cu-67 3.E-06 2.E-06 2.E-06 St/St/St
Zn-62 - - 1.E-06 / /St
Zn-63 - - 3.E-05 / /St
Zn-65 - - 1.E-07 / /St
Zn-69m - - 3.E-06 / /St
Zn-69 - - 6.E-05 / /St
Zn-71m - - 7.E-06 / /St
Zn-72 - - 5.E-07 / /St
Ga-65 7.E-05 8.E-05 - St/St/
Ga-66 1.E-06 1.E-06 - St/St/
Ga-67 6.E-06 4.E-06 - St/St/
Ga-68 2.E-05 2.E-05 - St/St/
Ga-70 7.E-05 8.E-05 - St/St/
Ga-72 2.E-06 1.E-06 - St/St/
Ga-73 6.E-06 6.E-06 - St/St/
Ge-66 1.E-05 8.E-06 - St/St/
Ge-67 4.E-05 4.E-05 - St/St/
Ge-68 2.E-06 4.E-08 - St/St/
Ge-69 6.E-06 3.E-06 - St/St/
Ge-71 2.E-04 2.E-05 - St/St/
Ge-75 3.E-05 3.E-05 - St/St/
Ge-77 4.E-06 2.E-06 - St/St/
Ge-78 9.E-06 9.E-06 - St/St/
As-69 - 5.E-05 - /St/
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
As-70 - 2.E-05 - /St/
As-71 - 2.E-06 - /St/
As-72 - 6.E-07 - /St/
As-73 - 7.E-07 - /St/
As-74 - 3.E-07 - /St/
As-76 - 6.E-07 - /St/
As-77 - 2.E-06 - /St/
As-78 - 9.E-06 - /St/
Se-70 1.E-05 2.E-05 - St/St/
Se-73m 6.E-05 6.E-05 - St/St/
Se-73 6.E-06 7.E-06 - St/St/
Se-75 3.E-07 3.E-07 - St/St/
Se-79 3.E-07 2.E-07 - St/St/
Se-81m 3.E-05 3.E-05 - St/St/
Se-81 9.E-05 1.E-04 - St/St/
Se-83 5.E-05 5.E-05 - St/St/
Br-74m 1.E-05 2.E-05 - St/St/
Br-74 3.E-05 3.E-05 - St/St/
Br-75 2.E-05 2.E-05 - St/St/
Br-76 2.E-06 2.E-06 - St/St/
Br-77 1.E-05 8.E-06 - St/St/
Br-80m 7.E-06 6.E-06 - St/St/
Sr-80 8.E-05 9.E-05 - St/St/
Br-82 2.E-06 2.E-06 - St/St/
Br-83 3.E-05 3.E-05 - St/St/
Br-84 2.E-05 3.E-05 - St/St/
Rb-79 5.E-05 - - St/ /
Rb-81m 1.E-04 - - St/ /
Rb-81 2.E-05 - - St/ /
Rb-82m 7.E-06 - - St/ /
Rb-83 4.E-07 - - St/ /
Rb-84 3.E-07 - - St/ /
Rb-86 3.E-07 - - St/ /
Rb-87 6.E-07 - - St/ /
Rb-88 3.E-05 - - St/ /
Rb-89 6.E-05 - - St/ /
Sr-80 5.E-06 - 5.E-06 St/ /St
Sr-81 3.E-05 - 3.E-05 St/ /St
Sr-83 3.E-06 - 2.E-06 St/ /St
Sr-85m 3.E-04 - 3.E-04 St/ /St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Sr-85 1.E-06 - 7.E-07 St/ /St
Sr-87m 5.E-05 - 6.E-05 St/ /St
Sr-89 3.E-07 - 6.E-08 St/ /St
Sr-90 8.E-09 - 2.E-09 St/ /St
Sr-91 2.E-06 - 1.E-06 St/ /St
Sr-92 4.E-06 - 3.E-06 St/ /St
Y-86m - 2.E-05 2.E-05 /St/St
Y-86 - 1.E-06 1.E-06 /St/St
Y-87 - 1.E-06 1.E-06 /St/St
Y-88 - 1.E-07 1.E-07 /St/St
Y-90m - 5.E-06 5.E-06 /St/St
Y-90 - 3.E-07 3.E-07 /St/St
Y-91m - 1.E-04 7.E-05 /St/St
Y-91 - 7.E-08 5.E-08 /St/St
Y-92 - 3.E-06 3.E-06 /St/St
Y-93 - 1.E-06 1.E-06 /St/St
Y-94 - 3.E-05 3.E-05 /St/St
Y-95 - 6.E-05 6.E-05 /St/St
Zr-86 2.E-06 1.E-06 1.E-06 St/St/St
Zr-88 9.E-08 2.E-07 1.E-07 St/St/St
Zr-89 2.E-06 1.E-06 1.E-06 St/St/St
Zr-93 3.E-09 1.E-08 2.E-08 BS/BS/BS
Zr-95 6.E-08 2.E-07 1.E-07 BS/St/St
Zr-97 8.E-07 6.E-07 5.E-07 St/St/St
Nb-88 - 1.E-04 9.E-05 /St/St
Nb-89 (66 min) - 2.E-05 2.E-05 /St/St
Nb-89 (122 min) - 8.E-06 7.E-06 /St/St
Nb-90 - 1.E-06 1.E-06 /St/St
Nb-93m - 5.E-07 7.E-08 /St/St
Nb-94 - 8.E-08 6.E-09 /St/St
Nb-95m - 1.E-06 9.E-07 /St/St
Nb-95 - 5.E-07 5.E-07 /St/St
Nb-96 - 1.E-06 1.E-06 /St/St
Nb-97 - 3.E-05 3.E-05 /St/St
Nb-98 - 2.E-05 2.E-05 /St/St
Mo-90 3.E-06 - 2.E-06 St/ /St
Mo-93m 7.E-06 - 6.E-06 St/ /St
Mo-93 2.E-06 - 7.E-08 St/ /St
Mo-99 1.E-06 - 6.E-07 St/ /St
Mo-101 6.E-05 - 6.E-05 St/ /St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Tc-93m 7.E-05 1.E-04 - St/St/
Tc-93 3.E-05 4.E-05 - St/St/
Tc-94m 2.E-05 2.E-05 - St/St/
Tc-94 8.E-06 1.E-05 - St/St/
Tc-96m 1.E-04 1.E-04 - St/St/
Tc-96 1.E-06 9.E-07 - St/St/
Tc-97m 3.E-06 5.E-07 - SW/St/
Tc-97 2.E-05 2.E-06 - St/St/
Tc-98 7.E-07 1.E-07 - St/St/
Tc-99m 6.E-05 1.E-04 - St/St/
Tc-99 2.E-06 3.E-07 - SW/St/
Tc-101 1.E-04 2.E-04 - St/St/
Tc-104 3.E-05 4.E-05 - St/St/
Ru-94 2.E-05 3.E-05 2.E-05 St/St/St
Ru-97 8.E-06 5.E-06 5.E-06 St/St/St
Ru-103 7.E-07 4.E-07 3.E-07 St/St/St
Ru-105 6.E-06 6.E-06 5.E-06 St/St/St
Ru-106 4.E-08 2.E-08 5.E-09 St/St/St
Rh-99m 2.E-05 3.E-05 3.E-05 St/St/St
Rh-99 1.E-06 9.E-07 8.E-07 St/St/St
Rh-100 2.E-06 2.E-06 2.E-06 St/St/St
Rh-101m 5.E-06 3.E-06 3.E-06 St/St/St
Rh-101 2.E-07 3.E-07 7.E-08 St/St/St
Rh-102m 2.E-07 2.E-07 5.E-08 St/St/St
Rh-102 4.E-08 7.E-08 2.E-08 St/St/St
Rh-103m 4.E-04 5.E-04 5.E-04 St/St/St
Rh-105 5.E-06 3.E-06 2.E-06 St/St/St
Rh-106m 1.E-05 1.E-05 1.E-05 St/St/St
Rh-107 1.E-04 1.E-04 1.E-04 St/St/St
Pd-100 6.E-07 5.E-07 6.E-07 St/St/St
Pd-101 1.E-05 1.E-05 1.E-05 St/St/St
Pd-103 3.E-06 2.E-06 1.E-06 St/St/St
Pd-107 9.E-06 3.E-06 2.E-07 K /St/St
Pd-109 3.E-06 2.E-06 2.E-06 St/St/St
Ag-102 8.E-05 9.E-05 8.E-05 St/St/St
Ag-103 4.E-05 6.E-05 5.E-05 St/St/St
Ag-104m 4.E-05 5.E-05 5.E-05 St/St/St
Ag-104 3.E-05 6.E-05 6.E-05 St/St/St
Ag-105 4.E-07 7.E-07 7.E-07 St/St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Ag-106m 3.E-07 4.E-07 4.E-07 St/St/St
Ag-106 7.E-07 9.E-05 8.E-05 St/St/St
Ag-108m 8.E-08 1.E-07 1.E-08 St/St/St
Ag-110m 6.E-08 8.E-08 4.E-08 St/St/St
Ag-111 7.E-07 4.E-07 4.E-07 L /St/St
Ag-112 3.E-06 4.E-06 4.E-06 St/St/St
Ag-115 4.E-05 4.E-05 3.E-05 St/St/St
Cd-104 3.E-05 5.E-05 5.E-05 St/St/St
Cd-107 2.E-05 2.E-05 2.E-05 St/St/St
Cd-109 1.E-08 5.E-08 5.E-08 K /K /St
Cd-113m 1.E-08 4.E-09 5.E-09 K /K /St
Cd-113 9.E-07 3.E-09 6.E-09 K /K /St
Cd-115m 2.E-06 5.E-08 6.E-08 K /St/St
Cd-115 6.E-05 5.E-07 6.E-07 St/St/St
Cd-117m 5.E-06 7.E-06 6.E-06 St/St/St
Cd-117 5.E-06 7.E-06 6.E-06 St/St/St
In-109 2.E-05 3.E-05 - St/St/
In-110 (69 min) 2.E-05 2.E-05 - St/St/
In-110 (5 h) 7.E-06 8.E-06 - St/St/
In-111 3.E-06 3.E-06 - St/St/
In-112 3.E-04 3.E-04 - St/St/
In-113m 6.E-05 8.E-05 - St/St/
In-114m 3.E-08 4.E-08 - St/St/
In-115m 2.E-05 2.E-05 - St/St/
In-115 6.E-10 2.E-09 - St/St/
In-116m 3.E-05 5.E-05 - St/St/
In-117m 1.E-05 2.E-05 - St/St/
In-117 7.E-05 9.E-05 - St/St/
In-119m 5.E-05 6.E-05 - St/St/
Sn-110 5.E-06 5.E-06 - St/St/
Sn-111 9.E-05 2.E-04 - St/St/
Sn-113 5.E-07 2.E-07 - St/St/
Sn-117m 5.E-07 6.E-07 - BS/St/
Sn-119m 1.E-06 4.E-07 - St/St/
Sn-121m 4.E-07 2.E-07 - St/St/
Sn-121 6.E-06 5.E-06 - St/St/
Sn-123m 5.E-05 6.E-05 - St/St/
Sn-123 3.E-07 7.E-08 - St/St/
Sn-125 4.E-07 2.E-07 - St/St/
Sn-126 2.E-08 3.E-08 - St/St/
Sn-127 8.E-06 8.E-06 - St/St/
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Sn-128 1.E-05 1.E-05 - St/St/
Sb-115 1.E-04 1.E-04 - St/St/
Sb-116m 3.E-05 6.E-05 - St/St/
Sb-116 1.E-04 1.E-04 - St/St/
Sb-117 9.E-05 1.E-04 - St/St/
Sb-118m 8.E-06 9.E-06 - St/St/
Sb-119 2.E-05 1.E-05 - St/St/
Sb-120 (16 min) 2.E-04 2.E-04 - St/St/
Sb-120 (6 d) 9.E-07 6.E-07 - St/St/
Sb-122 1.E-06 4.E-07 - St/St/
Sb-124m 3.E-04 3.E-04 - St/St/
Sb-124 4.E-07 1.E-07 - St/St/
Sb-125 1.E-06 2.E-07 - St/St/
Sb-126m 8.E-05 8.E-05 - St/St/
Sb-126 4.E-07 2.E-07 - St/St/
Sb-127 9.E-07 4.E-07 - St/St/
Sb-128 (9 h) 2.E-06 1.E-06 - St/St/
Sb-126 (10 min) 2.E-04 2.E-04 - St/St/
Sb-129 4.E-06 4.E-06 - St/St/
Sb-130 3.E-05 3.E-05 - St/St/
Sb-13I 1.E-05 1.E-05 - T /T /
Te-116 9.E-06 1.E-05 - St/St/
Te-121m 8.E-08 2.E-07 - BS/St/
Te-121 2.E-06 1.E-06 - St/St/
Te-123m 9.E-08 2.E-07 - BS/St/
Te-123 8.E-08 2.E-07 - BS/05/
Te-125m 2.E-07 3.E-07 - BS/St/
Te-127m 1.E-07 1.E-07 - BS/St/
Te-127 9.E-06 7.E-06 - St/St/
Te-129m 3.E-07 1.E-07 - St/St/
Te-129 3.E-05 3.E-05 - St/St/
Te-131m 2.E-07 2.E-07 - T /T /
Te-131 2.E-06 2.E-06 - T /T /
Te-132 9.E-08 9.E-08 - T /T /
Te-133m 2.E-06 2.E-06 - T /T /
Te-133 9.E-06 9.E-06 - T /T /
Te-134 1.E-05 1.E-05 - T /T /
I-120m 9.E-06 - - St/ /
I-120 4.E-06 - - T / /
I-121 7.E-06 - - T / /
I-123 3.E-06 - - T / /
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
I-124 3.E-08 - - T / /
I-125 3.E-08 - - T / /
I-126 1.E-08 - - T / /
I-128 5.E-05 - - St/ /
I-129 4.E-09 - - T / /
I-130 3.E-07 - - T / /
I-131 2.E-08 - - T / /
I-132m 4.E-06 - - T / /
I-132 3.E-06 - - T / /
I-133 1.E-07 - - T / /
I-134 2.E-05 - - E / /
I-135 7.E-07 - - T / /
Cs-125 6.E-05 - - St/ /
Cs-127 4.E-05 - - St/ /
Cs-129 1.E-05 - - St/ /
Cs-130 8.E-05 - - St/ /
Cs-131 1.E-05 - - St/ /
Cs-132 2.E-06 - - St/ /
Cs-134m 6.E-05 - - St/ /
Cs-134 4.E-08 - - St/ /
Cs-135m 8.E-05 - - St/ /
Cs-135 5.E-07 - - St/ /
Cs-136 3.E-07 - - St/ /
Cs-137 7.E-08 - - St/ /
Cs-138 2.E-05 - - St/ /
Ba-126 6.E-06 - - St/ /
Ba-128 7.E-07 - - St/ /
Ba-131m 6.E-04 - - St/ /
Ba-131 3.E-06 - - St/ /
Ba-133m 4.E-06 - - St/ /
Ba-133 3.E-07 - - St/ /
Ba-135m 5.E-06 - - St/ /
Ba-139 1.E-05 - - St/ /
Ba-140 6.E-07 - - St/ /
Ba-141 3.E-05 - - St/ /
Ba-142 6.E-05 - - St/ /
La-131 5.E-05 7.E-05 - St/St/
La-132 4.E-06 5.E-06 - St/St/
La-135 4.E-05 4.E-05 - St/St/
La-137 3.E-08 1.E-07 - L /E /
La-138 2.E-09 6.E-09 - St/St/
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
La-140 6.E-07 5.E-07 - St/St/
La-141 4.E-06 5.E-06 - St/St/
La-142 9.E-06 1.E-05 - St/St/
La-143 4.E-05 4.E-05 - St/St/
Ce-134 - 3.E-07 3.E-07 /St/St
Ce-135 - 2.E-06 2.E-06 /St/St
Ce-137m - 2.E-06 2.E-06 /St/St
Ce-137 - 6.E-05 5.E-05 /St/St
Ce-139 - 3.E-07 3.E-07 /St/St
Ce-141 - 3.E-07 3.E-07 /St/St
Ce-143 - 8.E-07 7.E-07 /St/St
Ce-144 - 1.E-06 6.E-09 /St/St
Pr-136 - 1.E-04 9.E-05 /St/St
Pr-137 - 6.E-05 6.E-05 /St/St
Pr-138m - 2.E-05 2.E-05 /St/St
Pr-139 - 5.E-05 5.E-05 /St/St
Pr-142m - 7.E-05 6.E-05 /St/St
Pr-142 - 8.E-07 8.E-07 /St/St
Pr-143 - 3.E-07 3.E-07 /St/St
Pr-144 - 5.E-05 5.E-05 /St/St
Pr-145 - 4.E-06 3.E-06 /St/St
Pr-147 - 8.E-05 8.E-05 /St/St
Nd-136 - 2.E-05 2.E-05 /St/St
Nd-138 - 3.E-06 2.E-06 /St/St
Nd-139m - 7.E-06 6.E-06 /St/St
Nd-139 - 1.E-04 1.E-04 /St/St
Nd-141 - 3.E-04 3 E-04 /St/St
Nd-147 - 4.E-07 3.E-07 /St/St
Nd-149 - 1.E-05 1.E-05 /St/St
Nd-151 - 8.E-05 8.E-05 /St/St
Pm-141 - 8.E-05 7.E-05 /St/St
Pm-143 - 3.E-07 3.E-07 /St/St
Pm-144 - 5.E-08 5.E-08 /St/St
Pm-145 - 7.E-08 8.E-08 /BS/St
Pm-146 - 2.E-08 2.E-08 /St/St
Pm-147 - 6.E-08 6.E-08 /BS/St
Pm-148m - 1.E-07 1.E-07 /St/St
Pm-148 - 2.E-07 2.E-07 /St/St
Pm-149 - 8.E-07 8.E-07 /St/St
Pm-150 - 8.E-06 7.E-06 /St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Pm-151 - 2.E-06 1.E-06 /St/St
Sm-141m - 4.E-05 - /St/
Sm-141 - 7.E-05 - /St/
Sm-142 - 1.E-05 - /St/
Sm-145 - 2.E-07 - /St/
Sm-146 - 1.E-11 - /BS/
Sm-147 - 2.E-11 - /BS/
Sm-151 - 4.E-08 - /BS/
Sm-153 - 1.E-06 - /St/
Sm-155 - 9.E-05 - /St/
Sm-156 - 4.E-06 - /St/
Eu-145 - 8.E-07 - /St/
Eu-146 - 5.E-07 - /St/
Eu-147 - 7.E-07 - /St/
Eu-148 - 2.E-07 - /St/
Eu-149 - 1.E-06 - /St/
Eu-150 (12 h) - 3.E-06 - /St/
Eu-150 (34 yr) - 8.E-09 - /St/
Eu-152m - 3.E-06 - /St/
Eu-152 - 1.E-08 - /St/
Eu-154 - 8.E-09 - /St/
Eu-155 - 4.E-08 - /BS/
Eu-156 - 2.E-07 - /St/
Eu-157 - 2.E-06 - /St/
Eu-158 - 2.E-05 - /St/
Gd-145 7.E-05 7.E-05 - St/St/
Gd-146 5.E-08 1.E-07 - St/St/
Gd-147 2.E-06 2.E-06 - St/St/
Gd-148 3.E-12 1.E-11 - BS/BS/
Gd-149 9.E-07 1.E-06 - St/St/
Gd-151 2.E-07 5.E-07 - BS/St/
Gd-152 4.E-12 2.E-11 - BS/BS/
Gd-153 6.E-08 3.E-07 - BS/St/
Gd-159 3.E-06 2.E-06 - St/St/
Tb-147 - 1.E-05 - /St/
Tb-149 - 3.E-07 - /St/
Tb-150 - 9.E-06 - /St/
Tb-151 - 4.E-06 - /St/
Tb-153 - 3.E-06 - /St/
Tb-154 - 2.E-06 - /St/
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Tb-155 - 3.E-06 - /St/
Tb-156m (24 h) - 3.E-06 - /St/
Tb-156m (5 h) - 1.E-05 - /St/
Tb-156 - 6.E-07 - /St/
Tb-157 - 1.E-07 - /BS/
Tb-158 - 8.E-09 - /St/
Tb-160 - 1.E-07 - /St/
Tb-161 - 7.E-07 - /St/
Dy-155 - 1.E-05 - /St/
Dy-157 - 3.E-05 - /St/
Dy-159 - 1.E-06 - /St/
Dy-165 - 2.E-05 - /St/
Dy-166 - 3.E-07 - /St/
Ho-155 - 7.E-05 - /St/
Ho-157 - 6.E-04 - /St/
Ho-159 - 4.E-04 - /St/
Ho-161 - 2.E-04 - /St/
Ho-162m - 1.E-04 - /St/
Ho-162 - 1.E-03 - /St/
Ho-164m - 1.E-04 - /St/
Ho-164 - 3.E-04 - /St/
Ho-166m - 3.E-09 - /St/
Ho-166 - 7.E-07 - /St/
Ho-167 - 2.E-05 - /St/
Er-161 - 3.E-05 - /St/
Er-165 - 8.E-05 - /St/
Er-169 - 1.E-06 - /St/
Er-171 - 4.E-06 - /St/
Er-172 - 6.E-07 - /St/
Tm-162 - 1.E-04 - /St/
Tm-166 - 6.E-06 - /St/
Tm-167 - 8.E-07 - /St/
Tm-170 - 9.E-08 - /St/
Tm-171 - 1.E-07 - /BS/
Tm-172 - 5.E-07 - /St/
Tm-173 - 5.E-06 - /St/
Tm-175 - 1.E-04 - /St/
Yb-162 - 1.E-04 1.E-04 /St/St
Yb-166 - 8.E-07 8.E-07 /St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Yb-167 - 3.E-04 3.E-04 /St/St
Yb-169 - 3.E-07 3.E-07 /St/St
Yb-175 - 1.E-06 1.E-06 /St/St
Yb-177 - 2.E-05 2.E-05 /St/St
Yb-178 - 2.E-05 1.E-05 /St/St
Lu-169 - 2.E-06 2.E-06 /St/St
Lu-170 - 9.E-07 8.E-07 /St/St
Lu-171 - 8.E-07 8.E-07 /St/St
Lu-172 - 5.E-07 5.E-07 /St/St
Lu-173 - 1.E-07 1.E-07 /BS/St
Lu-174m - 1.E-07 9.E-08 /BS/St
Lu-174 - 5.E-08 7.E-08 /BS/St
Lu-176m - 1.E-05 1.E-05 /St/St
Lu-176 - 2.E-09 3.E-O9 /BS/St
Lu-177m - 5.E-08 3.E-08 /BS/St
Lu-177 - 9.E-07 9.E-07 /St/St
Lu-178m - 8.E-05 7.E-05 /St/St
Lu-178 - 5.E-05 5.E-05 /St/St
Lu-179 - 8.E-06 6.E-06 /St/St
Hf-170 2.E-06 2.E-06 - St/St/
Hf-172 4.E-09 2.E-08 - BS/BS/
Hf-173 5.E-06 5.E-06 - St/St/
Hf-175 4.E-07 5.E-07 - BS/St/
Hf-177m 2.E-05 4.E-05 - St/St/
Hf-178m 6.E-10 2.E-09 - BS/BS/
Hf-179m 1.E-07 3.E-07 - BS/St/
Hf-180m 9.E-06 1.E-05 - St/St/
Hf-181 7.E-08 2.E-07 - BS/St/
Hf-182m 4.E-05 6.E-05 - St/St/
Hf-182 3.E-10 1.E-09 - BS/BS/
Hf-183 2.E-05 2.E-05 - St/St/
Hf-184 3.E-06 3.E-06 - St/St/
Ta-172 - 5.E-05 4.E-05 /St/St
Ta-173 - 8.E-06 7.E-06 /St/St
Ta-174 - 4.E-05 4.E-05 /St/St
Ta-175 - 7.E-06 6.E-06 /St/St
Ta-176 - 5.E-06 5.E-06 /St/St
Ta-177 - 8.E-06 7.E-06 /St/St
Ta-178 - 4.E-05 3.E-05 /St/St
Ta-179 - 2.E-06 4.E-07 /St/St
Ta-180m - 3.E-05 2.E-05 /St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Ta-180 - 2.E-07 1.E-08 /St/St
Ta-182m - 2.E-04 2.E-04 /St/St
Ta-182 - 1.E-07 6.E-08 /St/St
Ta-183 - 5.E-07 4.E-07 /St/St
Ta-184 - 2.E-06 2.E-06 /St/St
Ta-185 - 3.E-05 3.E-05 /St/St
Ta-186 - 1.E-04 9.E-05 /St/St
W-176 2.E-05 - - St/ /
W-177 4.E-05 - - St/ /
W-178 8.E-06 - - St/ /
W-179 7.E-04 - - St/ /
W-181 1.E-05 - - St/ /
W-185 3.E-06 - - St/ /
W-187 4.E-06 - - St/ /
W-188 5.E-07 - - St/ /
Re-177 1.E-04 2.E-04 - St/St/
Re-178 1.E-04 1.E-04 - St/St/
Re-181 4.E-06 4.E-06 - St/St/
Re-182 (64 h) 1.E-06 9.E-07 - St/St/
Re-182 (12 h) 5.E-06 6.E-06 - St/St/
Re-184m 1.E-06 2.E-07 - St/St/
Re-184 2.E-06 6.E-07 - St/St/
Re-186m 7.E-07 6.E-08 - SW/St/
Re-186 1.E-06 7.E-07 - St/St/
Re-187 3.E-04 4.E-05 - SW/St/
Re-188m 6.E-05 6.E-05 - St/St/
Re-188 1.E-06 1.E-06 - St/St/
Re-189 2.E-06 2.E-06 - St/St/
Os-180 2.E-04 2.E-04 2.E-04 St/St/St
Os-181 2.E-05 2.E-05 2.E-05 St/St/St
Os-182 2.E-06 2.E-06 2.E-06 St/St/St
Os-185 2.E-07 3.E-07 3.E-07 St/St/St
Os-189m 1.E-04 9.E-05 7.E-05 St/St/St
Os-191m 1.E-06 9.E-06 7.E-06 St/St/St
Os-191 9.E-07 7.E-07 6.E-07 St/St/St
Os-193 2.E-06 1.E-06 1.E-06 St/St/St
Os-194 2.E-08 2.E-08 3.E-09 St/St/St
Ir-182 6.E-05 6.E-05 5.E-05 St/St/St
Ir-184 1.E-05 1.E-05 1.E-05 St/St/St
Ir-185 5.E-06 5.E-06 4.E-06 St/St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Ir-186 3.E-06 3.E-06 2.E-06 St/St/St
Ir-187 1.E-05 1.E-05 1.E-05 St/St/St
Ir-188 2.E-06 2.E-06 1.E-06 St/St/St
Ir-189 2.E-06 2.E-06 2.E-06 St/St/St
Ir-190m 8.E-05 9.E-05 8.E-05 St/St/St
Ir-190 4.E-07 4.E-07 4.E-07 St/St/St
Ir-192m 4.E-08 9.E-08 6.E-09 St/St/St
Ir-192 1.E-07 2.E-07 9.E-08 St/St/St
Ir-194m 4.E-08 7.E-08 4.E-08 St/St/St
Ir-194 1.E-06 8.E-07 8.E-07 St/St/St
Ir-195m 1.E-05 1.E-05 9.E-06 St/St/St
Ir-195 2.E-05 2.E-05 2.E-05 St/St/St
Pt-186 2.E-05 - - St/ /
Pt-188 7.E-07 - - St/ /
Pt-189 1.E-05 - - St/ /
Pt-191 3.E-06 - - St/ /
Pt-193m 2.E-06 - - St/ /
Pt-193 1.E-05 - - St/ /
Pt-l95m 2.E-06 - - St/ /
Pt-197m 2.E-05 - - St/ /
Pt-197 4.E-06 - - St/ /
Pt-199 6.E-05 - - St/ /
Pt-200 1.E-06 - - St/ /
Au-193 1.E-05 8.E-06 8.E-06 St/St/St
Au-194 3.E-06 2.E-06 2.E-06 St/St/St
Au-195 5.E-06 6.E-07 2.E-07 St/St/St
Au-198m 1.E-06 5.E-07 5.E-07 St/St/St
Au-198 2.E-06 7.E-07 7.E-07 St/St/St
Au-199 4.E-06 2.E-06 2.E-06 St/St/St
Au-200m 1.E-06 1.E-06 1.E-06 St/St/St
Au-200 3.E-05 3.E-05 3.E-05 St/St/St
Au-201 9.E-05 1.E-04 9.E-05 St/St/St
Hg-193m (Org) 6.E-06 - - St/ /
Hg-193m (Inorg) 4.E-06 3.E-06 - St/St/
Hg-193m (Vapor) - 4.E-06 - /St/
Hg-193 (Org) 3.E-05 - - St/ /
Hg-193 (Inorg) 2.E-05 2.E-05 - St/St/
Hg-193 (Vapor) - 1.E-05 - /St/
Hg-194 (Org) 1.E-08 - - St/ /
Hg-194 (Inorg) 2.E-08 5.E-08 - St/St/
Hg-194 (Vapor) - 1.E-08 - /St/
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Hg-195m (Org) 3.E-06 - - St/ /
Hg-195m (Inorg) 2.E-06 2.E-06 - St/St/
Hg-195m (Vapor) - 2.E-06 - /St/
Hg-195 (Org) 2.E-05 - - St/
Hg-195 (Inorg) 1.E-05 1.E-05 - St/St/
Hg-195 (Vapor) - 1.E-05 - /St/
Hg-197m (Org) 4.E-06 - - St/ /
Hg-197m (Inorg) 3.E-06 2.E-06 - St/St/
Hg-197m (Vapor) - 2.E-06 - /St/
Hg-197 (Org) 6.E-06 - - St/ /
Hg-197 (Inorg) 5.E-06 4.E-06 - St/St/
Hg-197 (Vapor) - 3.E-05 - /St/
Hg-199m (Org) 7.E-05 - - St/ /
Hg-199m (Inorg) 6.E-05 7.E-05 - St/St/
Hg-199m (Vapor) - 3.E-05 - /St/
Hg-203 (Org) 3.E-07 - - St/ /
Hg-203 (Inorg) 5.E-07 5.E-07 - St/St/
Hg-203 (Vapor) - 3.E-07 - /St/
Tl-194m 6.E-05 - - St/ /
Tl-194 3.E-04 - - St/ /
Tl-195 5.E-05 - - St/ /
Tl-197 5.E-05 - - St/ /
Tl-198m 2.E-05 - - St/ /
Tl-198 1.E-05 - - St/ /
Tl-199 3.E-05 - - St/ /
Tl-200 5.E-06 - - St/ /
Tl-201 9.E-06 - - St/ /
Tl-202 2.E-06 - - St/ /
Tl-204 9.E-07 - - St/ /
Pb-195m 8.E-05 - - St/ /
Pb-198 3.E-05 - - St/ /
Pb-199 3.E-05 - - St/ /
Pb-200 3.E-06 - - St/ /
Pb-201 9.E-06 - - St/ /
Pb-202m 1.E-05 - - St/ /
Pb-202 2.E-08 - - St/ /
Pb-203 4.E-06 - - St/ /
Pb-205 6.E-07 - - St/ /
Pb-209 2.E-05 - - St/ /
Pb-210 1.E-10 - - BS/ /
Pb-211 3.E-07 - - St/ /
Pb-212 1.E-08 - - St/ /
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Pb-214 3.E-07 - - St/ /
Bi-200 3.E-05 4.E-05 - St/St/
Bi-201 1.E-05 2.E-05 - St/St/
Bi-202 2.E-05 3.E-05 - St/St/
Bi-203 3.E-06 2.E-06 - St/St/
Bi-205 1.E-06 5.E-07 - St/St/
Bi-206 6.E-07 4.E-07 - St/St/
Bi-207 7.E-07 2.E-07 - St/St/
Bi-210m 2.E-09 3.E-10 - K /St/
Bi-210 1.E-07 1.E-08 - K /St/
Bi-212 1.E-07 1.E-07 - St/St/
Bi-213 1.E-07 2.E-07 - St/St/
Bi-214 3.E-07 4.E-07 - St/St/
Po-203 3.E-05 4.E-05 - St/St/
Po-205 2.E-05 3.E-05 - St/St/
Po-207 1.E-05 1.E-05 - St/St/
Po-210 3.E-10 3.E-10 - E /St/
At-207 1.E-06 9.E-07 - St/St/
At-211 3.E-08 2.E-08 - St/St/
Rn-220 8.E-09 4/ - 4/ - 4/ - 4/
Rn-222 3.E-08 4/ - 4/ - 4/ - 4/
Fr-222 2.E-07 - - St/ /
Fr-223 3.E-07 - - St/ /
Ra-223 - 3.E-10 - /St/
Ra-224 - 7.E-10 - /St/
Ra-225 - 3.E-10 - /St/
Ra-226 - 3.E-10 - /St/
Ra-227 - 6.E-06 - /BS/
Ra-228 - 5.E-10 - /St/
Ac-224 1.E-08 2.E-08 2.E-08 BS/St/St
Ac-225 1.E-10 3.E-10 3.E-10 BS/St/St
Ac-226 1.E-09 2.E-09 2.E-09 BS/St/St
Ac-227 2.E-13 7.E-13 2.E-12 BS/BS/St
Ac-228 4.E-09 2.E-08 2.E-08 BS/BS/St
Th-226 - 7.E-08 6.E-08 /St/St
Th-227 - 1.E-10 1.E-10 /St/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Th-228 - 4.E-12 7.E-12 /BS/St
Th-229 - 4.E-13 1.E-12 /BS/BS
Th-230 - 3.E-12 7.E-12 /BS/BS
Th-231 - 3.E-06 3.E-06 /St/St
Th-232 - 5.E-13 1.E-12 /BS/BS
Th-234 - 9.E-08 6.E-08 /St/St
Pa-227 - 5.E-08 4.E-08 /St/St
Pa-228 - 5.E-09 5.E-09 /BS/St
Pa-233 - 2.E-09 1.E-09 /St/St
Pa-231 - 7.E-13 2.E-12 /BS/BS
Pa-232 - 9.E-09 2.E-08 /BS/BS
Pa-233 - 3.E-07 2.E-07 /St/St
Pa-234 - 3.E-06 3.E-06 /St/St
U-230 2.E-10 1.E-10 1.E-10 BS/St/St
U-231 3.E-06 2.E-06 2.E-06 St/St/St
U-232 9.E-11 2.E-10 3.E-12 BS/St/St
U-233 5.E-I0 3.E-10 2.E-11 BS/St/St
U-234 5.E-10 3.E-10 2.E-11 BS/St/St
U-235 6.E-10 3.E-10 2.E-11 BS/St/St
U-236 6.E-10 3.E-10 2.E-11 BS/St/St
U-237 1.E-06 7.E-07 6.E-07 St/St/St
U-238 6.E-10 3.E-10 2.E-11 BS/St/St
U-239 8.E-05 7.E-05 6.E-05 St/St/St
U-240 2.E-06 1.E-06 1.E-06 St/St/St
Np-232 - 1.E-06 5/ - /BS/
Np-233 - 1.E-03 5/ - /St/
Np-234 - 1.E-06 5/ - /St/
Np-235 - 5.E-07 5/ - /BS/
Np-136 (1.E+05 yr) - 1.E-11 5/ - /BS/
Np-236 (22 h) - 2.E-08 5/ - /BS/
Np-237 - 2.E-12 5/ - /BS/
Np-238 - 4.E-08 5/ - /BS/
Np-239 - 1.E-06 5/ - /St/
Np-240 - 3.E-05 5/ - /St/
Pu-234 - 9.E-08 5/ 8.E-08 5/ /St/St
Pu-235 - 1.E-03 5/ 1.E-03 5/ /St/St
Pu-236 - 7.E-12 5/ 1.E-11 5/ /BS/St
Pu-237 - 1.E-06 5/ 1.E-06 5/ /St/St
Pu-238 - 3.E-12 5/ 7.E-12 5/ /BS/BS
Pu-239 - 2.E-12 5/ 6.E-12 5/ /BS/BS
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Pu-240 - 2.E-12 5/ 6.E-12 5/ /BS/BS
Pu-241 - 1.E-10 5/ 3.E-10 5/ /BS/BS
Pu-242 - 2.E-12 5/ 6.E-12 5/ /BS/BS
Pu-243 - 1.E-05 5/ 1.E-05 5/ /St/St
Pu-244 - 2.E-12 5/ 6.E-12 5/ /BS/BS
Pu-245 - 2.E-06 5/ 2.E-06 5/ /St/St
Am-237 - 1.E-04 5/ - /St/
Am-238 - 1.E-06 5/ - /BS/
Am-239 - 5.E-06 5/ - /St/
Am-240 - 1.E-06 5/ - /St/
Am-241 - 2.E-12 5/ - /BS/
Am-242m - 2.E-12 5/ - /BS/
Am-242 - 3.E-08 5/ - /BS/
Am-243 - 2.E-12 5/ - /BS/
Am-244m - 2.E-06 5/ - /BS/
Am-244 - 7.E-08 5/ - /BS/
Am-245 - 3.E-05 5/ - /St/
Am-246m - 7.E-05 5/ - /St/
Am-246 - 4.E-05 5/ - /St/
Cm-238 - 4.E-07 5/ - /St/
Cm-240 - 2.E-10 5/ - /BS/
Cm-241 - 9.E-09 5/ - /BS/
Cm-242 - 1.E-10 5/ - /BS/
Cm-243 - 3.E-12 5/ - /BS/
Cm-244 - 4.E-12 5/ - /BS/
Cm-245 - 2.E-12 5/ - /BS/
Cm-246 - 2.E-12 5/ - /BS/
Cm-247 - 2.E-12 5/ - /BS/
Cm-248 - 6.E-13 5/ - /BS/
Cm-249 - 6.E-06 5/ - /BS/
Bk-245 - 5.E-07 - /St/
Bk-246 - 1.E-06 - /St/
Bk-247 - 2.E-12 - /BS/
Bk-249 - 9.E-10 - /BS/
Bk-250 - 2.E-07 - /BS/
Cf-244 - 2.E-07 5/ 2.E-07 5/ /St/St
Cf-246 - 4.E-09 5/ 4.E-09 5/ /St/St
Cf-248 - 4.E-11 5/ 5.E-11 5/ /BS/St
Cf-249 - 2.E-12 5/ 6.E-12 5/ /BS/BS
Cf-250 - 5.E-12 5/ 1.E-11 5/ /BS/St
Inhaled Air - Lung Retention Class
-------------------------------------- Stochastic
D W Y or Organ 1/
Radionuclide (microCi/mL) (microCi/mL) (microCi/mL) (D /W /Y )
--------------- ------------ ------------ ------------ -----------
Cf-251 - 2.E-12 5/ 5.E-12 5/ /BS/BS
Cf-252 - 1.E-11 5/ 2.E-11 5/ /BS/St
Cf-253 - 8.E-10 5/ 7.E-10 5/ /St/St
Cf-254 - 9.E-12 5/ 7.E-12 5/ /St/St
Es-250 - 3.E-07 - /BS/
Es-251 - 4.E-07 - /BS/
Es-253 - 6.E-10 - /St/
Es-254m - 4.E-09 - /St/
Es-254 - 4.E-11 - /BS/
Fm-252 - 6.E-09 - /St/
Fm-253 - 4.E-09 - /St/
Fm-254 - 4.E-08 - /St/
Fm-255 - 9.E-09 - /St/
Fm-257 - 1.E-10 - /E /
Md-257 - 4.E-08 - /St/
Md-258 - 1.E-10 - /BS/
_____________
1/ A determination of whether the DACs are controlled by stochastic (St)
or nonstochastic (organ) dose, or if they both give the same result (E)
for each lung retention class is given in this column. The key to the
organ notation for nonstochastic dose is: BS Bone surface, K = Kidney,
L = Liver, Sin = Stomach wall, and T = Thyroid. A blank indicates that
no calculations are performed for the lung retention class shown.
2/ The ICRP identifies tritiated water and carbon as having immediate
uptake and distribution; therefore no solubility classes are
designated. For purposes of this table, the DAC values are shown as
being constant, independent of solubility class. For tritiated water,
the inhalation DAC values allow for an additional 50% absorption
through the skin, as described in ICRP Publication No. 30: Limits for
Intakes of Radionuclides by Workers. For elemental tritium, the DAC
values are based solely on consideration of the dose-equivalent rate
to the tissues of the lung from inhaled tritium gas contained within
the lung, without absorption in the tissues.
3/ A dash indicates no values given for this data category.
4/ These values are appropriate for protection from radon combined with
its short-lived daughters and are based on information given in ICRP
Publication 32: Limits for Inhalation of Radon Daughters by Workers
and Federal Guidance Report No. 11: Limiting Values of Radionuclide
Intake and Air Concentrations, and Dose Conversion Factors for
Inhalation, Submersion, and Ingestion (EPA 520/1-88-020). The values
given are for 100% equilibrium concentration conditions of the radon
daughters with the parent. To allow for an actual measured equilibrium
concentration or a demonstrated equilibrium concentration, the values
given in this table should be multiplied by the ratio (100%/actual %)
or (100%/demonstrated %), respectively. Alternatively, the DAC values
for Rn-220 and Rn-222 may be replaced by 1 WL* and 1/3 WL,*
respectively, for appropriate limiting of daughter concentrations.
Because of the dosimetric considerations for radon, no f1 or lung
clearance values are listed.
* A "Working Level" (WL) is any combination of short-lived radon
daughters, in one liter of air without regard to the degree of
equilibrium, that will result in the ultimate emission of 1.3 E+05 MeV
of alpha energy.
5/ For the calculations, f1 values were obtained from ICRP Publication 48:
The Metabolism of Plutonium and Related Elements. It is assumed that
the effective dose equivalents for inhalation are unchanged even though
the f1 values have changed. This is because the contribution to organ
dose from inhalation is dependent mainly on transfer from lung to blood
when f1 values are small. Also, the gastrointestinal tract dose would
be unchanged because the fraction of activity passing through the tract
is (1.0 - f1).
Table 2
Alternative Absorption Factors and Lung Retention Classes
for Specific Compounds
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Actinium/ 89 Oxides, hydroxides 1.E-t3 Y
Ac Halides, nitrates 1.E-03 W
All others 1.E-03 D
Aluminum/ 13 Oxides, hydroxides, 1.E-02 W
Al carbides, halides,
nitrates, elemental form
All others 1.E-02 D
Americium/ 95 All forms 1.E-03 W
Am
Antimony/ 51 Oxides, hydroxides, halides, 1.E-01 D
Sb sulphides, sulphates,
nitrates
All others 1.E-02 W
Arsenic/ 33 All forms 5.E-01 W
As
Astatine/ 85 All (as a halide) 1.E+00 W or D;
At dependent
upon
associated
element
Barium/ 56 All forms 1.E-01 D
Ba
Berkelium/ 97 All forms 5.E-04 W
Bk
Beryllium/ 4 Oxides, halides, nitrates 5.E-03 Y
Be All others 5.E-03 W
Bismuth/ 83 All except nitrates 5.E-02 W
Bi Nitrates 5.E-02 D
Bromine/ 35 Bromides 1.E+00 W or D;
Br dependent
upon
associated
element
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Cadmium/ 48 Oxides, hydroxides 5.E-02 Y
Cd Sulphates, halides 5.E-02 W
All others 5.E-02 D
Calcium/ 20 All forms 3.E-01 W
Ca
Californium/ 98 Oxides, hydroxides 1.E-03 Y
Cf All others 1.E-03 W
Carbon/ 6 Oxides 1/ D
C Organic (11C) 1.E+00 W
Organic (14C) 1.E+00 W
Cerium/ 58 Oxides, hydroxides, 3.E-04 Y
Ce fluorides
All others 3.E-04 W
Cesium/ 55 All forms 1.E+00 D
Cs
Chlorine/ 17 Chloride 1.E+00 W or D;
dependent
upon
associated
element
Chromium/ 24 Oxides, hydroxides 1.E-01 Y
Cr Halides, nitrates 1.E-01 W
All others 1.E-01 D
Ingestion 2/
Trivalent 1.E-02
Hexavalent 1.E-01
Cobalt/ 27 Oxides, hydroxides, halides, 5.E-02 Y
Co nitrates
All others 5.E-02 W
Ingestion only 2/ 3.E-01
Copper/ 29 Oxides, hydroxides 5.E-01 Y
Cu Sulphites, halides, nitrates 5.E-01 W
All others 5.E-01 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Curium/ 96 All forms 1.E-03 W
Cm
Dysprosium/ 66 All forms 3.E-04 W
Dy
Einsteinium/ 99 All forms 5.E-04 W
Es
Erbium/ 68 All forms 3.E-04 W
Er
Europium/ 63 All forms 1.E-03 W
Eu
Fermium/ 100 All forms 5.E-04 W
Fm
Fluorine/ 9 Fluoride 1.E+00 Y, W, or D;
F dependent
upon
associated
element
Francium/ 87 All forms 1.E+00 D
Fr
Gadolinium/ 64 Oxides, hydroxides, 3.E-04 W
Gd fluorides
All others 3.E-04
Gallium/ 31 Oxides, hydroxides, 1.E-03 W
Ga carbides, halides, nitrates
All others 1.E-03 D
Germanium/ 32 Oxides, sulphides, halides 1.E+00 W
Ge All others 1.E+00 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Gold/ 79 Oxides, hydroxides 1.E-01 Y
Au Halides, nitrates 1.E-01 W
All others 1.E-01 D
Hafnium/ 72 Oxides, hydroxides, halides, 2.E-03 W
Hf carbides, nitrates
All others 2.E-03 D
Holmiuin/ 67 All forms 3.E-04 W
Ho
Hydrogen/ 1 Water, elemental 1.E+00
H
Indium/ 49 Oxides, hydroxides, halides 2.E-02 W
In All others 2.E-02 D
Iodine/ 53 All forms 1.E+00 D
Iridium/ 77 Oxides, hydroxides 1.E-02 Y
Ir Halides, nitrates, 1.E-02 W
metallic form
All others 1.E-02 D
Iron/ 26 Oxides, hydroxides, halides 1.E-01 W
Fe All others 1.E-01 D
Lanthanum/ 57 Oxides, hydroxides 1.E-03 W
La All others 1.E-03 D
Lead/ 82 All forms 2.E-01 D
Pb
Lutetium/ 71 Oxides, hydroxides, 3.E-04 Y
Lu fluorides
All others 3.E-04 W
Magnesium/ 12 Oxides, hydroxides, 5.E-01 W
Mg carbides, halides, nitrates
All others 5.E-01 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Manganese/ 25 Oxides, hydroxides, halides, 1.E-01 W
Mn nitrates
All others 1.E-01 D
Mendelevium/ 101 All forms 5.E-04 W
Md
Mercury/ 80 Oxides, hydroxides, halides, 2.E-02 W
Hg nitrates, sulphites
Sulphates, elemental form 2.E-02 D
Organic forms 1.E+00 D
Vapor 1/ D
Molybdenum/ 42 Oxides, hydroxides, MoS2 5.E-02 Y
All others 8.E-01 D
Ingestion 2/
MoS2 5.E-02
All Others 8.E-01
Neodymium/ 60 Oxides, hydroxides, 3.E-04 W
Nd carbides, fluorides
All others 3.E-04 Y
Neptunium/ 93 All forms 1.E-03 W
Np
Nickel/ 28 Oxides, hydroxides 5.E-02 W
Ni All others (vapor) 1/ D
Niobium/ 41 Oxides, hydroxides 1.E-02 Y
Nb All others 1.E-02 W
Osmium/ 76 Oxides, hydroxides 1.E-02 Y
Os Halides, nitrates 1.E-02 W
All others 1.E-02 D
Palladium/ 46 Oxides, hydroxides 5.E-03 Y
Pd Nitrates 5.E-03 W
All others 5.E-03 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Phosphorus/ 15 Phosphates 8.E-01 W or D;
P dependent
upon
associated
element
Platinum/ 78 All forms 1.E-02 D
Pt
Plutonium/ 94 Oxides, hydroxides 1.E-05 Y
Pu Nitrates 1.E-04 W
All other 1.E-03 W
[Note: Use same
values for
ingestion]
Polonium/ 84 Oxides, hydroxides, nitrates 1.E-01 W
All others 1.E-01 D
Potassium/ 19 All forms 1.E+00 D
K
Praseodymium/ 59 Oxides, hydroxides, 3.E-04 Y
Pr carbides, fluorides
All others 3.E-04 W
Promethium/ 61 Oxides, hydroxides 3.E-04 Y
Pm carbides, fluorides
All others 3.E-04 W
Protactinium/ 91 Oxides, hydroxides 1.E-03 Y
Pa All others 1.E-03 W
Radium/ 88 All forms 2.E-01 W
Ra
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Rhenium/ 75 Oxides, hydroxides, 8.E-01 W
Re halides, nitrates
All others 8.E-01 D
Rhodium/ 45 Oxides, hydroxides 5.E-02 Y
Rh Halides 5.E-02 W
All others 5.E-02 D
Rubidium/ 37 All forms 1.E+00 D
Rb
Ruthenium/ 44 Oxides, hydroxides 5.E-02 Y
Ru Halides 5.E-02 W
All others 5.E-02 D
Samarium/ 62 All forms 3.E-04 W
Sm
Scandium/ 21 All forms 1.E-04 Y
Sc
Selenium/ 34 Oxides, hydroxides, carbides 8.E-01 W
All others 8.E-01 D
Ingestion only 2/ 5.E-02
Silicon/ 14 Ceramic forms 1.E-02 Y
Si Oxides, hydroxides, 1.E-02 W
carbides, nitrates
All others 1.E-02 D
Silver/ 47 Oxides, hydroxides 5.E-02 Y
Ag Nitrates, sulphides 5.E-02 W
All others, elemental form 5.E-02 D
Sodium/ 11 All forms 1.E+00 D
Na
Strontium/ 38 SrTiO3 1.E-02 Y
Sr All others (soluble) 3.E-01 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Sulfur/ 16 All Inorganic 8.E-01 D
Elemental Form 8.E-01 W
Gases 1.E+00 D
Ingestion 2/
All inorganic 1.E-01
Tantalum/ 73 Oxides, hydroxides, halides, 1.E-03 Y
Ta carbides, nitrates,
nitrides
All others 1.E-03 W
Technetium/ 43 Oxides, hydroxides, 8.E-01 W
Tc halides, nitrates
All others 8.E-01 D
Tellurium/ 52 Oxides, hydroxides, nitrates 2.E-01 W
Te All others 2.E-01 D
Terbium/ 65 All forms 3.E-04 W
Tb
Thallium/ 81 All forms 1.E+00 D
Tl
Thorium/ 90 Oxides, hydroxides 2.E-04 Y
Th All others 2.E-04 W
Thulium/ 69 All forms 3.E-04 W
Tm
Tin/ 05 Oxides, hydroxides, halides, 2.E-02 W
Sn nitrates, sulphides,
Sn3(PO4)4
All others 2.E-02 D
Titanium/ 22 SrTiO3 1.E-02 Y
Ti Oxides, hydroxides, 1.E-02 W
carbides, halides, nitrates
All others 1.E-02 D
Lung
Element/ Atomic Retention
Symbol Number Compound f1 Class
---------- ------ ----------------------- ------ ---------
Tungsten/ 74 Ingestion 2/
W Tungstic acid 1.E-02
All others 3.E-01
Uranium/ 92 UO2, U3O8 1.E-03 Y
U UO3, tetravalent compounds 5.E-02 W
UF6, uranyl compounds 5.E-02 D
Vanadium/ 23 Oxides, hydroxides, 1.E-02 W
V carbides, halides
All others 1.E-02 D
Ytterbium/ 70 Oxides, hydroxides, 3.E-04 Y
Yb fluorides
All others 3.E-04 W
Yttrium/ 39 Oxides, hydroxides 1.E-04 Y
Y All others 1.E-04 W
Zinc/ 30 All forms 5.E-01 Y
Zn
Zirconium/ 40 Carbides 2.E-03 Y
Oxides, hydroxides, 1.E-03 W
halides, nitrates
All others 1.E-03 D
______________
1/ A dash indicates no data for the value shown.
2/ For ingestion, no lung retention classes are listed.
Table 3
Derived Air Concentrations (DAC) for Workers from External Exposure
During Immersion in a Contaminated Atmospheric Cloud
Air Immersion
Radionuclide Half-Life DAC (microCi/mL)
------------ --------- ----------------
C-11 20.48 min 4.E-06
N-13 9.97 min 4.E-06
N-16 7.13 s 7.E-07
O-15 122.24 s 4.E-06
F-18 1/ 109.74 min 4.E-06
Na-24 1/ 15.00 h 9.E-07
Mg-27 2/ 9.458 min 5.E-06
Al-28 2/ 2.240 min 2.E-06
Cl-38 1/ 37.21 min 3.E-06
Ar-37 35.02 d 3.E-00
Ar-39 269 yr 2.E-04 3/
Ar-41 1.827 h 3.E-06
K-43 1/ 22.6 h 5.E-06
Ca-49 2/ 8.719 min 1.E-06
Sc-44 1/ 3.927 h 2.E-06
Sc-46m 2/ 18.72 s 5.E-05
Ti-45 1/ 3.08 h 5.E-06
Ti-51 2/ 5.752 min 1.E-05
V-52 2/ 3.75 min 3.E-06
Cr-49 1/ 42.09 min 5.E-06
Mn-52m 1/ 21.4 min 2.E-06
Mn-56 1/ 2.5785 h 2.E-06
Mn-57 2/ 1.47 min 6.E-05
Co-60m 1/ 10.47 min 1.E-03
Ni-57 1/, 4/ 36.08 h 2.E-06
Ni-65 1/, 5/ 2.520 h 8.E-06
Air Immersion
Radionuclide Half-Life DAC (microCi/mL)
------------ --------- ----------------
Cu-61 1/ 3.408 h 5.E-06
Cu-62 2/ 9.74 min 5.E-06
Ga-66 1/ 9.40 h 2.E-06
Ga-68 1/ 68.0 min 5.E-06
Ga-72 1/ 14.1 h 1.E-06
Se-73 1/ 7.15 h 4.E-06
Br-77 1/ 57.04 h 1.E-05 6/
Br-8O 1/ 17.4 min 5.E-05
Br-82 1/ 35.30 h 1.E-06
Br-84 1/ 31.80 min 2.E-06
Br-85 2/ 172 s 5.E-05
Kr-79 35.04 h 2.E-05
Kr-81 2.1E+05 yr 5.E-04
Kr-83m 1.83 h 5.E-02
Kr-85 10.72 yr 1.E-04 3/
Kr-85m 4.48 h 3.E-05
Kr-87 76.3 min 5.E-06
Kr-88 2.84 h 2.E-06
Kr-89 3.16 min 2.E-06
Kr-90 32.32 s 3.E-06
Rb-81 1/ 4.58 h 8.E-06
Rb-82 2/ 1.25 min 2.E-06
Rb-88 1/ 17.8 min 7.E-06
Rb-89 1/ 15.44 min 2.E-06
Rb-90 2/ 157 s 2.E-06
Rb-90m 2/ 258 s 1.E-06
Sr-85m 1/ 67.66 min 2.E-05
Sr-87m 1/ 2.805 h 6.E-05
Sr-92 1/ 1.71 h 3.E-06
Sr-93 2/ 7.3 min 2.E-06
Y-86 1/ 14.74 h 1.E-06
Y-90m 1/ 3.19 h 5.E-06 6/
Y-91m 1/ 49.71 min 9.E-06
Nb-90 1/ 14.60 h 1.E-07
Nb-94m 2/ 6.26 min 9.E-04
Air Immersion
Radionuclide Half-Life DAC (microCi/mL)
------------ --------- ----------------
Nb-97 1/ 72.1 min 7.E-06
Nb-97m 1/ 60 s 6.E-06
Mo-91 2/ 15.49 min 4.E-06
Mo-101 1/ 14.61 min 3.E-06
Tc-95 1/ 20.0 h 5.E-06
Tc-96m 1/ 51.5 min 1.E-04
Tc-99m 1/ 6.02 h 3.E-05
Tc-101 1/ 14.2 min 1.E-05
Ru-105 1/ 4.44 h 5.E-06
Rh-105m 2/ 45 s 1.E-04
Rh-106 2/ 29.92 s 2.E-05
Ag-108 2/ 2.37 min 2.E-04
Ag-109m 2/ 39.6 s 1.E-03
Ag-110 2/ 24.57 s 9.E-05
Cd-111m 2/ 48.7 min 1.E-05
Cd-117 1/ 2.49 h 4.E-06
Cd-117m 1/ 3.36 h 2.E-06
In-113m 1/ 1.658 h 2.E-05
In-114 2/ 71.9 s 1.E-04
In-116m 1/ 54.15 min 2.E-06
In-117 1/ 43.8 min 7.E-06
Sb-117 1/ 2.80 h 3.E-05
Sb-126m 1/ 19.0 min 3.E-06
Sb-129 1/ 4.40 h 3.E-06
Te-133 1/ 12.45 min 5.E-06
Te-133m 1/ 55.4 min 2.E-06
Te-134 1/ 41.8 min 5.E-06
I-122 2/ 3.62 min 5.E-06
I-128 1/ 24.99 min 5.E-05
I-132 1/ 2.30 h 2.E-06
I-134 1/ 52.6 min 1.E-06
I-135 1/ 6.61 h 7.E-07 6/
I-136 2/ 83 s 1.E-06
Air Immersion
Radionuclide Half-Life DAC (microCi/mL)
------------ --------- ----------------
Xe-122 20.1 h 8.E-05
Xe-123 2.14 h 7.E-06
Xe-125 16.8 h 2.E-05
Xe-127 36.406 d 1.E-05
Xe-129m 8.89 d 2.E-04
Xe-131m 11.84 d 5.E-04
Xe-133 5.245 d 1.E-04
Xe-133m 2.19 d 1.E-04
Xe-135 9.11 h 2.E-05
Xe-135m 15.36 min 1.E-05
Xe-137 3.83 min 2.E-05
Xe-138 14.13 min 4.E-06
Cs-126 2/ 1.64 min 4.E-06
Cs-129 1/ 32.06 h 1.E-05 6/
Cs-138 1/ 32.2 min 2.E-06
Cs-139 2/ 9.40 min 1.E-05
Ba-137m 2/ 2.552 min 7.E-06
Ba-141 1/ 18.27 min 5.E-06
Ba-142 1/ 10.70 min 5.E-06
La-142 1/ 95.4 min 1.E-06
Pr-144m 2/ 7.2 min 9.E-04
Nd-149 1/ 1.73 h 1.E-05
Gd-162 2/ 9.7 min 1.E-05
Td-162 2/ 7.76 min 4.E-06
Dy-157 1/ 8.06 h 1.E-05
Re-182m 1/ 12.7 h 4.E-06
Os-190m 2/ 9.9 min 3.E-06
Ir-190m 1/ 3.2 h 8.E-05 6/
Au-195m 2/ 30.6 s 2.E-05
Air Immersion
Radionuclide Half-Life DAC (microCi/mL)
------------ --------- ----------------
Tl-200 1/ 26.1 h 3.E-06
Tl-207 2/ 4.77 min 4.E-05 3/
Tl-208 2/ 3.053 min 1.E-06
Tl-209 2/ 2.20 min 2.E-06
Tl-210 2/ 1.30 min 1.E-06
Pb-204m 2/ 66.9 min 2.E-06
Bi-211 2/ 2.13 min 1.E-04
Po-211 2/ 0.516 s 5.E-04
Rn-220 55.61 s 8.E-09 6/
Rn-222 3.824 d 3.E-08 6/
Th-233 2/ 22.3 min 1.E-04
Pa-234 1/ 6.70 h 2.E-06
Pa-234m 2/ 1.17 min 4.E-05 3/
U-239 1/ 23.40 min 8.E-05 6/
Np-240 1/ 65 min 4.E-06
Np-240m 2/ 7.4 min 1.E-05
Am-246 1/ 25.0 min 4.E-06
______________
1/ Committed effective dose equivalent from inhalation is calculated in
ICRP Publication 30, but the DAC value for external exposure to a
contaminated atmospheric cloud is more restrictive than the DAC value
for inhalation.
2/ Committed effective dose equivalent from inhalation is not calculated in
ICRP Publication 30, but DAC value for external exposure to contaminated
cloud should be more restrictive than DAC value for inhalation due to
relatively short half-life of radionuclide.
3/ DAC value is determined by limit on annual dose equivalent to skin,
rather than limit on annual effective dose equivalent.
4/ DAC value applies to radionuclide in vapor form only; DAC value for
inhalation is more restrictive for radionuclide in inorganic form.
5/ DAC value applies to radionuclide in inorganic or vapor form.
6/ DAC value for exposure to contaminated atmospheric cloud is the same as
DAC value for inhalation. See footnote 4/ to Table 1 on page 24 of
Attachment 1.
SURFACE RADIOACTIVITY GUIDES
____________________________________________________________________________
TOTAL 2/ 3/
NUCLIDE 1/ REMOVABLE 2/4/ (FIXED PLUS REMOVABLE)
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U-nat, U-235, U-238, 1,000 dpm a/100 cm 2 5,000 dpm a/100 cm 2
and associated
decay products
Transuranics, 20 dpm/100 cm 2 300 dpm/100 cm 2
Ra-226, Ra-228,
Th-230, Th-228,
Pa-231, Ac-227,
I-125, I-129
Th-nat, Th-232, 200 dpm/100 cm 2 1,000 dpm/100 cm 2
Sr-90, Ra-223,
Ra-224, U-232,
I-126, I-131,
I-133
Beta-gamma emitters 1,000 dpm B-T/100 cm 2 5,000 dpm B-T/100 cm 2
(nuclides with
decay modes other
than alpha emission
or spontaneous
fission) except
Sr-90 and
others noted above. 5/
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1/ Where surface contamination by both alpha- and beta-gamma-emitting
nuclides exists, the limits established for alpha- and
beta-gamma-emitting nuclides should apply independently.
2/ As used in this table, dpm (disintegrations per minute) means the rate
of emission by radioactive material as determined by correcting the
counts per minute observed by an appropriate detector for background,
efficiency, and geometric factors associated with the instrumentation.
3/ The levels may be averaged over one square meter provided the maximum
surface activity in any area of 100 cm 2 is less than three times the
guide values. For purposes of averaging, any square meter of surface
shall be considered to be above the activity guide G if: (1) from
measurements of a representative number n of sections it is determined
that 1/n n Si > G, where Si is the dis/min-100 cm 2 determined from
measurement of section i; or (2) it is determined that the sum of the
activity of all isolated spots or particles in any 100 cm 2 area
exceeds 3G.
4/ The amount of removable radioactive material per 100 cm 2 of surface
area should be determined by wiping that area with dry filter or soft
absorbent paper, applying moderate pressure, and assessing the amount
of radioactive material on the wipe with an appropriate instrument of
known efficiency. (Note - The use of dry material may not be
appropriate for tritium.) When removable contamination on objects of
surface area less than 100 cm 2 is determined, the activity per unit
area should be based on the actual area and the entire surface should
be wiped. Except for transuranics and Ra-226, Ra-228, Ac-227, Th-228,
Th-230, and Pa-231 alpha emitters, it is not necessary to use wiping
techniques to measure removable contamination levels if direct scan
surveys indicate that the total residual surface contamination levels
are within the limits for removable contamination.
5/ This category of radionuclides includes mixed fission products,
including the SR-90 which is present in them. It does not apply to
SR-90 which has been separated from the other fission products or
mixtures where the SR-90 has been enriched.
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