The PDF version 
U.S. Department of Energy ORDER
Washington, D.C. DOE 5400.5
2-8-90
Change 2: 1-7-93
SUBJECT: RADIATION PROTECTION OF THE PUBLIC AND THE ENVIRONMENT
1. PURPOSE. To establish standards and requirements for operations of the
Department of Energy (DOE) and DOE contractors with respect to
protection of members of the public and the environment against undue
risk from radiation.
2. SUPERSESSION. DOE 5480.1A, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH
PROGRAM FOR DOE OPERATIONS, of 8-13-81, Chapter XI that addressed public
and environmental radiation protection standards and control practices.
3. 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.
4. IMPLEMENTING PROCEDURES AND REQUIREMENTS. This Order becomes effective
5-8-90. Within 2 months from the date of issuance of the Order
(2-8-90), the DOE Field Office Manager shall provide to the appropriate
Program Office, with copy to EH-1 for review and comment: a. a
certification for those areas covered by the Order for which field
elements are in compliance; and/or b. a request for exemption for areas
not yet in compliance that includes a Plan for achieving compliance.
Within 3 months of issuance, the appropriate Program Office will submit
to EH-1 the certification and/or the request for exemption(s). The
compliance plan accompanying the request for exemption shall include
schedules for activities which will lead to compliance with the
requirements of this Order.
5. POLICY. It is the policy of DOE to implement legally applicable
radiation protection standards and to consider and adopt, as
appropriate, recommendations by authoritative organizations, e.g., the
National Council on Radiation Protection and Measurements (NCRP) and
the International Commission on Radiological Protection (ICRP). It is
also the policy of DOE to adopt and implement standards generally
consistent with those of the Nuclear Regulatory Commission (NRC) for
DOE facilities and activities not subject to licensing authority.
6. OBJECTIVES.
a. Protecting the Public. It is DOE's objective to operate its
facilities and conduct its activities so that radiation exposures
to members of the public are maintained within the limits
established in this Order and to control radioactive contamination
through the management of real and personal property. It is also
a DOE objective that potential exposures to members of the public
be as far below the limits as is reasonably achievable (ALARA) and
that DOE facilities have the capabilities, consistent with the types
of operations conducted, to monitor routine and non-routine releases
and to assess doses to members of the public.
b. Protecting the Environment. In addition to providing protection to
members of the public, it is DOE's objective to protect the
environment from radioactive contamination to the extent practical.
7. LEGISLATIVE AUTHORITY. The Atomic Energy Act of 1954, as amended,
authorizes the Department to protect the health and safety of the public
against radiation in conducting the Department's programs.
8. REFERENCES.
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 5000.3B, OCCURRENCE REPORTING AND PROCESSING OF OPERATIONS
INFORMATION, of 1-19-93, which establishes a system for reporting
operations information related to DOE-owned or operated facilities
and processing of the information.
c. DOE 5400.1, GENERAL ENVIRONMENTAL PROTECTION PROGRAM REQUIREMENTS,
of 11-9-88, which establishes general environmental protection
requirements.
d. DOE 5400.2A ENVIRONMENT COMPLIANCE ISSUE COORDINATION, of 1-31-89,
which establishes requirements for coordination of significant
environmental compliance issues.
e. DOE 5400.4, COMPREHENSIVE ENVIRONMENTAL RESPONSE, COMPENSATION, AND
LIABILITY ACT PROGRAM, of 10-6-89, which establishes requirements
for hazardous waste cleanup and notification.
f. DOE 5440.1E, NATIONAL ENVIRONMENTAL POLICY ACT COMPLIANCE PROGRAM,
of 11-10-92, which establishes DOE policy for implementation of the
National Environmental Policy Act of 1969.
g. 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.
h. DOE 5480.4, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
STANDARDS, of 5-15-84, which identifies mandatory and reference
environmental, safety, and health standards.
i. DOE 5480.5, SAFETY OF NUCLEAR FACILITIES, of 9-23-86, which
establishes nuclear facility safety program requirements.
j. DOE 5480.6, SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS,
of 9-23-86, which establishes nuclear reactor safety program
requirements.
k. DOE 5480.11, RADIATION PROTECTION FOR OCCUPATIONAL WORKERS, of
12-21-88, which establishes radiation protection standards and
program requirements for workers.
l. DOE 5480.23, NUCLEAR SAFETY ANALYSIS REPORTS, of 4-10-92, which
establishes requirements for contractors to develop safety analyses
that establish and evaluate the adequacy of the safety bases of
nuclear facilities.
m. DOE 5482.1B, ENVIRONMENT, SAFETY, AND HEALTH APPRAISAL PROGRAM, of
9-23-86, which establishes the DOE environment, safety, and health
appraisal program.
n. DOE 5483.1A, OCCUPATIONAL SAFETY AND HEALTH PROGRAM FOR DOE
EMPLOYEES AT GOVERNMENT-OWNED, CONTRACTOR-OPERATED FACILITIES, of
6-22-83, which establishes requirements for the protection of the
health and safety of employees at DOE contractor-operated
facilities.
o. DOE 5484.1, ENVIRONMENTAL PROTECTION, SAFETY, AND HEALTH PROTECTION
INFORMATION REPORTING REQUIREMENTS, of 2-24-81, which establishes
procedures for the reporting of information having environmental
protection, safety, or health protection significance.
p. DOE Orders in the 5500 series that outline responsibilities for
emergency preparedness and response.
q. DOE 5820.2A, RADIOACTIVE WASTE MANAGEMENT, of 9-26-88, which
establishes policies and guidelines for the management of
radioactive waste and contaminated facilities.
r. DOE 6430.1A, GENERAL DESIGN CRITERIA, of 4-6-89, which provides
general design criteria for use in the acquisition of the
Department's facilities and establishes responsibilities and
authorities for the development and maintenance of those criteria.
s. 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.
t. 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.
u. DOE Publication DOE/EH-0173T, "Environmental Regulatory Guide for
Radiological Effluent Monitoring and Environmental Surveillance," of
1-91, which establishes elements of a radiological monitoring
program in support of DOE 5400.1 and 5400.5.
v. DOE publication DOE/EV/1830-T5, "A Guide to Reducing Radiation
Exposure to as Low as Reasonably Achievable," of 4-80, which
provides contractor personnel with general guidance regarding
programs and techniques to reduce radiation exposure to levels as
low as is reasonably achievable.
w. DOE publication, "Formerly Utilized Sites Remedial Action Program;
Summary Protocol: Identification - Characterization - Designation
- Remedial Action - Certification," of 1-86, which provides
procedures for conducting remedial actions at formerly utilized
sites.
x. DOE/CH-8901, "A Manual for Implementing Residual Radioactive
Material Guidelines; A Supplement to U.S. Department of Energy
Guidelines for Residual Radioactive Material at Formerly Utilized
Sites Remedial Action Program and Remote Surplus Facilities
Management Program Sites," of 6-89, which provides guidance on the
implementation of DOE residual radioactive material limits.
y. EPA Publication EPA-520/1-88-020, Federal Guidance Report No. 11,
Limiting Values of Radionuclide Intake and Air Concentration and
Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"
of 1988, which provides preferred dose conversion factors for use by
Federal agencies.
z. Title 10 CFR Part 60, "Disposal of High-Level Wastes in Geologic
Repositories," which prescribes rules governing the licensing of DOE
to receive and possess source, special nuclear, and byproduct
material at a geologic repository operations area.
aa. Title 10 CFR Part 72, "Licensing Requirements for the Storage of
Spent Fuel in an Independent Spent Fuel Storage Installation
(ISFSI)," which establishes requirements, procedures, and criteria
for licensing ISFSI.
bb. Title 40 CFR Part 61, Subpart H, "National Emission Standard for
Radionuclide Emissions from Department of Energy (DOE) Facilities,"
which regulates radionuclide air emissions from DOE facilities.
cc. Title 40 CFR Part 141, "National Interim Primary Drinking Water
Regulations (Safe Drinking Water Act)," which prescribes
radionuclide concentration limits for public drinking water.
dd. Title 40 CFR Part 190, "Environmental Radiation Protection Standards
for Nuclear Power Operations," which contains the radiation dose
limits for members of the public in the general environment and
curie release limits for radioactive materials released into the
general environment from operations within the nuclear fuel cycle
operations that are associated with the production of electrical
power.
ee. Title 40 CFR Part 191, "Environmental Standards for the Management
and Disposal of Spent Nuclear Fuel, High-Level and Transuranic
Wastes," which establishes requirements for the management and
disposal of spent nuclear fuel, high-level, and transuranic wastes.
ff. Title 40 CFR Part 192, "Standards for Remedial Actions at Inactive
Uranium Processing Sites," of 1-5-83, which concerns the control
of residual radioactive material at designated processing or
disposal sites.
gg. Title 42 U.S.C. 300, et seq., Safe Drinking Water Act, as amended,
which authorizes EPA to promulgate regulations under two specific
programs: the first protects the Nation's public drinking water
supplies; the second protects subsurface waters by regulating
underground injection of materials.
hh. Title 42 U.S.C. 2011, et seq., Atomic Energy Act of 1954, as
amended, which authorizes the conduct of atomic energy activities
and establishes authority for protecting the health and safety of
the public.
ii. Title 42 U.S.C. 4341, et seq., National Environmental Policy Act
of 1969, as amended, which establishes broad national environmental
policy.
jj. Title 42 U.S.C. 7401, et seq., Clean Air Act, as amended, which
provides requirements to protect and enhance the quality of the
Nation's air resources, to promote the public health and welfare.
kk. Title 47 Federal Register (FR) 47073, "Food and Drug Administration
(FDA) Accidental Radioactive Contamination of Human Food and Animal
Feeds; Recommendations for State and Local Agencies," which provides
guidance for protecting consumers of produce following a nuclear
accident.
ll. Title 48 CFR Part 923.70, "Environmental Conservation and
Occupational Safety," which contains the basic provisions of the
DOE Environment, Conservation and Occupational Safety Program.
mm. Title 48 CFR Part 970.23, "DOE Management and Operations Contracts,
Environmental Conservation, and Occupational Safety," which contains
supplemental information to Title 48 CFR Part 923.70 in providing
the basic provisions of the DOE Environment, Conservation and
Occupational Safety Program.
nn. International Commission on Radiological Protection (ICRP)
Publication 23, "Reference Man: Anatomical, Physiological and
Metabolic Characteristics," Pergamon Press, Oxford, England.
oo. ICRP Publication 26, "Recommendations of the International
Commission on Radiological Protection," Pergamon Press, Oxford,
England (1977).
pp. ICRP Publication 30, "Limits for Intakes of Radionuclides by
Workers."
qq. ICRP Publication 45, "Quantitative Bases for Developing a Unified
Index of Harm," Pergamon Press, Oxford, England.
rr. ICRP Publication 48, "The Metabolism of Plutonium and Related
Elements," Pergamon Press, Oxford, England.
ss. National Council on Radiation Protection and Measurements (NCRP)
Report No. 91, "Recommendations on Limits for Exposure to Ionizing
Radiation," NCRP, Bethesda, MD 20814.
tt. Nuclear Regulatory Commission, Regulatory Guide 1.86, "Termination
of Operating Licenses for Nuclear Reactors," of 6-74, which
establishes limits for surface contamination on materials and
equipment.
uu. Nuclear Regulatory Commission publication, "Guidelines for
Decontamination of Facilities and Equipment Prior to Release for
Unrestricted Use or Termination of Licenses for Byproduct, Source
or Special Nuclear Material," of 7-82.
vv. Oak Ridge National Laboratory (ORNL), Publication CCC - 475, 11-86,
"CAAC - Code System for Implementation of Atmospheric Dispersion
Assessment Required by the Clean Air Act." RSIC Computer Code
Collection.
9. 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 Department 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. Further, the Secretary retains the authority to
suspend any and all requirements under this Order whenever the
Secretary deems it necessary. This authority may be delegated by
the Secretary as appropriate.
b. In addition to those responsibilities and authorities contained in
DOE 5480.1B and DOE 5400.1, the following responsibilities and
authorities are assigned:
(1) Assistant Secretary for Environment, Safety and Health (EH-1)
(a) Develop DOE public and environmental radiation protection
policy and requirements; and
(b) Approve, if warranted, specific exceptions to this Order,
pursuant to provisions in DOE 5400.1 and DOE 5820.2A.
(2) Program Secretarial Officers.
(a) Implement DOE public and environmental radiation
protection policy and requirements in their respective
programs; and
(b) Implement, if warranted, interim control strategies
proposed by field organizations pursuant to this Order and
DOE 5820.2A.
(3) Heads of Field Elements.
(a) Implement provisions of this Order for their respective
activities;
(b) Maintain appropriate capabilities at each operating site
for monitoring and assessing routine and unplanned
releases of radioactive materials, with respect to the
characteristics of radioactive material released and the
release modes, consistent with the types of operations
conducted;
(c) Process specific requests for exceptions to this Order,
pursuant to paragraph II.1a(4); and
(d) Temporarily suspend the requirements of this Order when
doing so is in their judgement necessary to minimize
damage to life or property or to protect public health
or safety. Whenever this provision is invoked, such
suspension and the reason therefore are to be reported
to EH-1 at the earliest practicable time.
(4) Director, Naval Nuclear Propulsion Program: Executive Order
12344, statutorily prescribed by PL 98-525 (42 USC 7158 note)
establishes the responsibilities and authority of the Director,
Naval Nuclear Propulsion Program (who is also the Deputy
Assistant Secretary for Naval Reactors within the Department)
over all facilities and activities which comprise the Program,
a joint Navy-DOE organization. The policy principle promoted
by these executive and legislative actions is cited in the
Executive Order as "...preserving the basic structure,
policies, and practices developed for this Program in the
past...". Accordingly, The Naval Nuclear Propulsion Program is
exempt from the provisions of this Order. The Director shall
maintain an environmental protection program to ensure
compliance with applicable environmental statues and
regulations. The Director and EH-1 shall cooperatively develop
information exchange and other mutually beneficial programs as
appropriate, consistent with PL 98-525.
10. DEFINITIONS.
a. As Low As Reasonably Achievable (ALARA) is a phrase (acronym) used
to describe an approach to radiation protection to control or
manage exposures (both individual and collective to the work force
and the general public) and releases of radioactive material to
the environment as low as social, technical, economic, practical,
and public policy considerations permit. As used in this Order,
ALARA is not a dose limit, but rather it is a process that has as
its objective the attainment of dose levels as far below the
applicable limits of the Order as practicable.
b. Best Available Technology (BAT) means the preferred technology for
treating a particular process liquid waste, selected from among
others after taking into account factors related to technology,
economics, public policy, and other parameters. As used in this
Order, BAT is not a specific level of treatment, but the
conclusion of a selection process that includes several treatment
alternatives.
c. Derived Concentration Guide (DCG) is the concentration of a
radionuclide in air or water that, under conditions of continuous
exposure for one year by one exposure mode (i.e., ingestion of
water, submersion in air, or inhalation), would result in an
effective dose equivalent of 100 mrem 0.1 rem (1 mSv). DCGs do
not consider decay products when the parent radionuclide is the
cause of the exposure (DCG values are presented in Chapter III)
(1 rem = 0.01 sievert).
d. Dose Terms.
(1) Absorbed Dose is 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) Collective Dose Equivalent and Collective Effective Dose
Equivalent are the sums of the dose equivalents or effective
dose equivalents of all individuals in an exposed population
within an 80-km radius, for the purposes of this Order, and
they are expressed in units of person-rem, (or person-sievert).
When the collective dose equivalent of interest is for a
specific organ, the units would be organ-rem (or
organ-sievert). For purposes of this Order, the 80-km distance
shall be measured from a point located centrally with respect
to major facilities or DOE program activities.
(3) Committed Dose Equivalent is the predicted total dose
equivalent to a tissue or organ over a 50-year period after a
known intake of a radionuclide into the body. It does not
include contributions from external dose. Committed dose
equivalent is expressed in units of rem (or sievert).
(4) Committed Effective Dose Equivalent is the sum of the committed
dose equivalents to various tissues in the body, each
multiplied by the appropriate weighting factor. Committed
effective dose equivalent is expressed in units of rem (or
sievert).
(5) Deep Dose Equivalent, as used in this Order, means the dose
equivalent in tissue at a depth of 1 cm deriving from external
(penetrating) radiation.
(6) Dose Equivalent is the product of absorbed dose in rad (or
gray) in tissue and a quality factor. Dose equivalent is
expressed in units of rem (or sievert).
(7) Effective Dose Equivalent is the summation of the products of
the dose equivalent received by specified tissues of the body
and a tissue-specific weighting factor. This sum is a
risk-equivalent value and can be used to estimate the
health-effects risk of the exposed individual. The
tissue-specific weighting factor represents the fraction of
the total health risk resulting from uniform whole-body
irradiation that would be contributed by that particular
tissue. The effective dose equivalent includes the committed
effective dose equivalent from internal deposition of
radionuclides and the effective dose equivalent due to
penetrating radiation from sources external to the body.
Effective dose equivalent is expressed in units of rem (or
sievert).
(8) Public Dose means the dose received by member(s) of the public
from exposure to radiation and to radioactive material released
by a DOE facility or operation, whether the exposure is within
a DOE site boundary or off-site. It does not include dose
received from occupational exposures, doses received from
naturally occurring "background" radiation, doses received as a
patient from medical practices, or doses received from consumer
products.
(9) Weighting Factor is tissue-specific and represents the fraction
of the total health risk resulting from uniform, whole-body
irradiation that could be contributed to that particular
tissue. The weighting factors recommended by the ICRP
(Publication 26) and used here are
--------------------------------------------------
| Organ or Tissue Weighting Factor |
| --------------- ---------------- |
| Gonads 0.25 |
| Breasts 0.15 |
| Red Bone Marrow 0.12 |
| Lungs 0.12 |
| Thyroid 0.03 |
| Bone Surfaces 0.03 |
| Remainder 1/ 0.30 |
|________________________________________________|
1/ "Remainder means the five other organs with the highest
dose (e.g., liver, kidney, spleen, thymus, adrenal,
pancreas, stomach, small intestine, or upper and lower
large intestine, but excluding skin, lens of the eye,
and extremities). The weighting factor for each of
these organs is 0.06.
(10) Quality Factor is the principal modifying factor used to
regulate the dose equivalent from the absorbed dose. For the
purposes of this Order, the following quality factors, which
are taken from DOE 5480.11, are to be used.
__________________________________________________________
| Radiation Type Quality Factor |
| -------------- -------------- |
| X-rays, gamma rays, 1 |
| positrons, and electrons |
| (including tritium) |
| - - - - - - - - - - - - - - - - - - - - - - - - - - - |
| Neutrons, <10 keV 3 |
| - - - - - - - - - - - - - - - - - - - - - - - - - - - |
| Neutrons, >10 keV 10 |
| Protons and single charged |
| particles of unknown energy with |
| rest mass > one atomic mass unit |
| - - - - - - - - - - - - - - - - - - - - - - - - - - - |
| Alpha particles 20 |
| Multiple-charged particles |
| (and particles of unknown |
| charge) of unknown energy |
|________________________________________________________|
For neutrons of known energies, the more detailed quality
factors given in DOE 5480.11 may be used.
e. Members of the Public means persons who are not occupationally
associated with the DOE facility or operations, i.e., persons
whose assigned occupational duties do not require them to enter
the DOE site. (Also see Dose Terms: Public Dose.)
f. Monitoring Terms.
(1) Effluent Monitoring is the collection and analysis of samples
or measurements of liquid and gaseous effluents for purposes
of characterizing and quantifying contaminants, assessing
radiation exposures of members of the public, and demonstrating
compliance with applicable standards.
(2) Environmental Surveillance is the collection and analysis of
samples of air, water, soil, foodstuffs, biota, and other
media from DOE sites and their environs and the measurement
of external radiation for purposes of demonstrating compliance
with applicable standards, assessing radiation exposures of
members of the public, and assessing effects, if any, on the
local environment.
g. Protective Action Guides (PAG) are projected numerical dose values
established by EPA, DOE, or States for individuals in the
population. These values may trigger protective actions that would
reduce or avoid the projected dose.
h. Radioactivity means the property or characteristic of radioactive
material to spontaneously "disintegrate" with the emission of
energy in the form of radiation. The unit of radioactivity is the
curie (or becquerel).
i. Reference Man means a hypothetical aggregation of human (male and
female) physical and physiological characteristics arrived at by
international consensus (ICRP Publication 23). These
characteristics may be used by researchers and public health
workers to standardize results of experiments and to relate
biological insult from ionizing radiation to a common base. The
"reference man" is assumed to inhale 8400 cubic meters of air in a
year and to ingest 730 liters of water in a year.
j. Release of Property, as used in this Order, means the exercising
of DOE's authority to release property from its control after
confirming that residual radioactive material (over which DOE has
authority) on the property has been determined to meet the
guidelines for residual radioactive material in Chapter IV or any
other applicable radiological requirements. There may be
instances in which DOE or other authority will impose restrictions
on the management and/or use of the property if the residual
radioactive material guidelines of Chapter IV are not met or if
other applicable Federal, State, or local requirements cause the
imposition of such restrictions.
k. Remedial Action means those actions consistent with permanent remedy
taken instead of, or in addition to, removal action in the event of
a release or threatened release of a hazardous substance into the
environment, to prevent or minimize the release of hazardous
substances so that they do not migrate to cause substantial danger
to present or future public health or welfare or the environment.
l. Residual Radioactive Material means any radioactive material which
is in or on soil, air, equipment, or structures as a consequence
of past operations or activities.
m. Settleable Solids means those solids suspended in waste water that
are determined to be settleable using Method 209 E, Settleable
Solids pp 98 and 99, 16th edition, Standard Methods for Examination
of Water and Waste Water.
n. Sewerage Terms.
(1) Sewage means the waste matter that passes through sewers.
(2) Sewer means the artificial conduit, usually underground, for
carrying off waste water and refuse.
(3) Sewerage means the system of sewers.
o. Soil Column is an in situ volume of soil down through which liquid
wastes percolate from ponds, cribs, seepage basins, or trenches.
p. Stochastic Effects are biological effects, the probability, rather
than the severity, of which is a function of the magnitude of the
radiation dose without threshold; i.e., stochastic effects are
random in nature. Nonstochastic Effects are biological effects,
the severity of which, in affected individuals, varies with the
magnitude of the dose above a threshold value.
BY ORDER OF THE SECRETARY OF ENERGY:
DONNA R. FITZPATRICK
Assistant Secretary
Management and Administration
TABLE OF CONTENTS
CHAPTER I - GENERAL
1. Background I-1
2. Dose Standards and Terminology I-1
a. International Commission on Radiological
Protection I-1
b. Other Sources of Regulations and Guidance I-1
3. Dose Limit Selection I-2
4. As Low As Reasonably Achievable I-2
5. Liquid Wastes and Effluents I-2
a. Protection of Resources I-2
b. Treatment of Liquid Radioactive Waste Streams I-2
6. Environmental Protection I-2
7. Discharges to Sanitary Sewerage I-3
8. Effluent Monitoring and Environmental Surveillance I-3
a. Demonstration of Compliance I-3
b. Monitoring and Surveillance Requirements I-3
9. Residual Radioactive Material I-3
10. Dose Evaluations I-3
a. Standard Methods I-3
b. Supplemental Documents I-4
c. EPA Models I-4
11. Reporting I-4
CHAPTER II - REQUIREMENTS FOR RADIATION PROTECTION OF THE PUBLIC
AND THE ENVIRONMENT
1. Public Dose Limits II-1
a. DOE Public Dose Limit--All Exposure Modes,
All DOE Sources of Radiation II-1
b. Airborne Emissions Only,--All DOE Sources of
Radionuclides II-3
c. All Exposure Modes, Sources from Management,
and Storage of Spent Nuclear Fuel, High-Level,
and Transuranic Wastes at Disposal Facilities II-4
d. Drinking Water Pathway Only, All DOE Sources of
Radionuclides II-5
2. The ALARA Process II-5
a. Considerations II-5
b. Evaluations II-6
3. Management and Control of Radioactive Materials in
Liquid Discharges and Phaseout of Soil Columns II-6
a. Discharges of Liquid Waste to Surface Waters II-6
b. Discharges of Liquid Waste to Aquifers
and Phaseout of Soil Columns II-8
c. Management of Soil Columns, Natural Draining
Systems, and Ground Water at Inactive Sites Previously
Contaminated with Radioactive Material II-9
d. Discharges of Liquid Waste to Sanitary Sewerage II-9
e. Exceptions for Liquid Waste Control Requirements II-10
4. Management of Low-Level Radioactive Solid Waste II-10
5. Release of Property Having Residual Radioactive Material II-10
a. Release of Real Property II-10
b. Release of Personal Property II-10
c. Release of Materials and Equipment II-11
6. Demonstration of Compliance with the Dose Limits II-12
a. Monitoring and Surveillance II-12
b. Dose Evaluations II-12
7. Reporting Requirements II-14
8. Records II-15
a. Content II-15
b. Retention II-15
9. Units II-15
CHAPTER III - DERIVED CONCENTRATION GUIDES FOR AIR AND WATER
1. Purpose III-1
2. Basis III-1
a. Exposure Conditions for Ingestion of Water and
Inhalation III-1
b. Exposure Conditions for Air Immersion III-2
c. Application to Mixtures of Radionuclides III-3
3. Limitations III-3
Figure III-1 - Derived Concentration Guides for
Members of the Public from Ingested Water and
Inhalation Resulting in 100 mrem/yr III-4
Figure III-2 - Alternative Absorption Factors and Lung
Retention Classes for Specific Compounds III-27
Figure III-3 - Derived Concentration Guides for Members
of the Public from External Exposure During
Immersion in a Contaminated Atmospheric Cloud III-36
CHAPTER IV - RESIDUAL RADIOACTIVE MATERIAL
1. Purpose IV-1
2. Implementation IV-1
a. Residual Radioactive Material IV-1
b. Basic Dose Limit IV-2
c. Guideline IV-2
d. Authorized Limit IV-2
e. ALARA Applications IV-3
3. Basic Dose Limits IV-3
a. Defining and Determining Dose Limits IV-3
b. Unusual Circumstances IV-3
4. Guidelines for Residual Radioactive Material IV-3
a. Residual Radionuclides in Soil IV-3
b. Airborne Radon Decay Products IV-4
c. External Gamma Radiation IV-5
d. Surface Contamination IV-5
e. Residual Radionuclides in Air and Water IV-5
5. Authorized Limits for Residual Radioactive Material IV-5
a. Establishment of Authorized Limits IV-5
Figure IV-1 - Surface Contamination Guidelines IV-6
b. Application of Authorized Limits IV-7
6. Control of Residual Radioactive Material IV-7
a. Operational and Control Requirements IV-7
b. Interim Storage IV-8
c. Interim Management IV-8
d. Long-Term Management IV-9
7. Supplemental Limits and Exceptions IV-9
a. Supplemental Limits IV-10
b. Exceptions IV-10
c. Justification for Supplemental Limits and Exceptions IV-10
8. Sources IV-11
a. Basic Dose Limits IV-11
b. Generic Guidelines for Residual Radioactive Material IV-11
c. Control of Radioactive Wastes and Residues IV-12
CHAPTER I
GENERAL
1. BACKGROUND. This Order has been developed to integrate, consolidate,
and update the portions of DOE 5480.1B that addressed public and
environmental radiation protection standards and control practices.
Specifically, this Order replaces requirements of DOE 5480.1B, Chapter
XI; adopts current guidance and standards issued by national and
international authoritative bodies on radiation protection; incorporates
current regulatory requirements applicable to DOE operations; and
consolidates and upgrades DOE guidance for contaminated property. The
following paragraphs provide a summary of the topics considered in this
Order.
2. DOSE STANDARDS AND TERMINOLOGY.
a. International Commission on Radiological Protection (ICRP). This
Order adopts and implements radiation protection dose standards
consistent with the recommendations of the ICRP. In 1977, the
ICRP recommended a system of dose limitations that has been
adopted and implemented by essentially all countries with nuclear
programs. The ICRP system of dose limitations provides a
scientific basis for health protection and selection of dose
limits. The system also reflects current information on health
risks, dosimetry, and radiation practices, and promotes a more
uniform and consistent application of radiation protection among
diverse activities than had previously been possible. The ICRP
system is based on sophisticated analytical models and requires
computer capabilities for making evaluations or using the dose
conversion tables produced from such evaluations.
b. Other Sources of Regulations and Guidance. DOE is required to
comply with legally applicable rules and regulations of other
Federal, State, and local agencies, some of which have not adopted
the ICRP system. The result is a mixture of dose standards,
terminology, and units. Therefore, some dose limits in this Order
are expressed in terms of effective dose equivalent, consistent
with current ICRP recommendations, while others are expressed in
terms of dose equivalent to the whole body or to specific organs,
consistent with pre-1977 recommendations of ICRP. The presentation
of this Order includes both the more traditional dose terms and
units and the new dose terms and concepts introduced by the ICRP for
their system of dose limitations. Definitions presented in this
Order are consistent with the definitions presented in related
Orders, such as DOE 5480.11.
3. DOSE LIMIT SELECTION. The DOE primary standard of 100 mrem (1 mSv)
effective dose equivalent to members of the public in a year is lower
than the previous primary limit of 500 mrem (5 mSv). The lower value
was selected in recognition of the ICRP recommendation to limit the
long-term average effective dose equivalent to 100 mrem (1 mSv) per
year, or less. Experience suggests that the lower dose is readily
achievable for normal operations of DOE facilities. A higher dose
limit, not to exceed the 500-mrem effective dose equivalent recommended
by ICRP as an occasional annual limit, may be authorized for a limited
period if it is justified by unusual operating conditions.
4. AS LOW AS REASONABLY ACHIEVABLE (ALARA). The DOE primary public dose
limit is based on consideration of the potential risk of
radiation-induced fatal cancers and serious genetic defects (i.e., the
ICRP risk-based system). The ICRP recommends that doses to individuals
be within the appropriate dose limit for the individuals and that all
exposures be ALARA. Accordingly, this Order adopts the ALARA process
in planning and carrying out all DOE activities.
5. LIQUID WASTES AND EFFLUENTS.
a. Protection of Resources. In addition to limiting dose to members
of the public (onsite or offsite) to the primary radiation
protection standards established in this Order and to the applicable
limits of EPA and State regulations, additional controls on the
release of liquid wastes are adopted to reduce the potential for
radiological contamination of natural resources such as land, ground
and surface water, and ecosystems.
b. Treatment of Liquid Radioactive Waste Streams. Standards for liquid
effluent discharges are driven by the DOE ALARA policy and objective
to minimize contamination in the environment to the extent
practicable. The Order adopts the "best available technology" (BAT)
as the appropriate level of treatment for liquid wastes containing
radioactive material and provides that the BAT be phased in at the
earliest practicable time. Technical and economic considerations
are included in determining the BAT. Based on cost and benefit
considerations, radioactive waste streams that contain radionuclide
concentrations of not more than the derived concentration guide
(DCG) reference values at the point of discharge to a surface
waterway normally will not require treatment to further reduce the
concentration. BAT treatment is provided to protect ground water
and to prevent radionuclide buildup in soil.
6. ENVIRONMENTAL PROTECTION. The phasing out of the use of soil columns
and the additional requirements associated with the burial of low-level
radioactive wastes (discussed in Chapter II) address concerns with
potential long-term contamination of the environment on and near DOE
activities and sites. These requirements are intended to prevent the
buildup of contamination in soils and ground water and to protect the
environment from the spread of contamination from burial trenches and
pits.
7. DISCHARGES TO SANITARY SEWERAGE. The control of releases of liquid
wastes to community sanitary sewer systems is designed to be generally
consistent with requirements imposed by NRC on its licensees. As
discussed in Chapter II, the "best available technology" (BAT) selection
process is to be applied to the treatment of liquid wastes released to
sanitary sewerage when concentrations of radionuclides would otherwise
exceed five times the DCG reference values given in Chapter III.
Operators should ensure that the total annual discharge of radioactive
material to the sanitary sewer system will not cause exposures to
members of the general public that will result in doses exceeding a
small fraction of the basic annual dose limit.
8. EFFLUENT MONITORING AND ENVIRONMENTAL SURVEILLANCE.
a. Demonstration of Compliance. Demonstrations of compliance with
requirements of this Order generally will be based upon calculations
that make use of information obtained from monitoring and
surveillance programs. The abilities to detect, quantify, and
adequately respond to unplanned releases of radioactive material to
the environment also rely on in-place effluent monitoring,
monitoring of environmental transport and diffusion conditions, and
assessment capabilities. This will enable DOE to develop useful
data and to collect and analyze pertinent information on unplanned
releases in a timely manner. It is the intent of DOE that the
monitoring and surveillance programs for the DOE activities,
facilities, and locations be of high quality. Although some
differences result from specific site or specific activity
conditions, uniformity in the methods and performance criteria used
in obtaining the information is desirable.
b. Monitoring and Surveillance Requirements. To ensure that the
effluent monitoring and environmental surveillance programs are of
good quality at all DOE facilities and sites, certain requirements
and recommendations are provided in DOE publication DOE/EH-073T
which deal with radiological effluent monitoring and environmental
surveillance.
9. RESIDUAL RADIOACTIVE MATERIAL. DOE practices and requirements for
residual radioactive material are presented in Chapter IV, including
limits of potential dose, authorized contamination limits for the
release of property, and ALARA considerations.
10. DOSE EVALUATIONS
a. Standard Methods. Data developed by the Department to demonstrate
that DOE operations comply with applicable standards and
requirements should be correct and representative. Accordingly,
this Order requires that calculations of dose to the public from
exposures resulting from both routine and unplanned activities be
performed using standard EPA or DOE dose conversion factors or
analytical models prescribed in regulations applicable to DOE
operations.
b. Supplemental Documents. The dose conversion factors and derived
concentrations needed to make dose evaluations to meet DOE
requirements are provided in Chapter III and three supplemental
documents: EPA-520/1-88-020, Federal Guidance Report No. 11,
"Limiting Values of Radionuclide Intake and Air Concentration
Factors for Inhalation, Submersion, and Ingestion;" DOE/EH-0071,
"Internal Dose Conversion Factors for Calculation of Dose to the
Public," and DOE/EH-0070, "External Dose-Rate Conversion Factors
for Calculation of Dose to the Public." The dose conversion
factors in these documents provide the primary basis for determining
compliance with this Order. The table of DCGs (Chapter III) has
been expanded considerably to present all classes of uptake and
retention.
c. EPA Models. The use of AIRDOS/RADRISK, CAP-88, or AIRDOS-PC models
is prescribed by EPA in 40 CFR Part 61, Subpart H, to evaluate
potential doses from airborne releases. Thus, two evaluations of
doses from airborne pathways could be required: one to satisfy 40
CFR Part 61 requirements and one for DOE purposes using contemporary
dosimetry. [Caution: Unless modified, AIRDOS/RADRISK (also known
as CAP-88 or AIRDOS-PC) is not suitable for calculating doses from
accidents.]
11. REPORTING. The Order addresses the notification of headquarters
personnel when DOE activities might have caused, or might cause, a
noncompliance with requirements of this Order. These requirements are
in addition to the general requirements for reporting, specified in DOE
5484.1. "Federally permitted" designation of releases, for purposes of
EPA reporting requirements, are addressed in section II.7.
CHAPTER II
REQUIREMENTS FOR RADIATION PROTECTION
OF THE PUBLIC AND THE ENVIRONMENT
1. PUBLIC DOSE LIMITS. Dose limits for members of the public are presented
in this chapter. The primary public dose limits include consideration
of all exposure modes from all DOE activities (including remedial
actions). The primary dose limit is expressed as an effective dose
equivalent, a term developed by the ICRP for their risk-based system,
which requires the weighted summation of doses to various organs of the
body. Additional public dose limits are established by EPA regulations
for exposures to several selected sources or exposure modes (pathways or
conditions). Public dose limits promulgated by EPA for selected
exposure modes are sometimes expressed as dose equivalents, which do not
include risk-based weighting or summation of doses to various organs,
and sometimes expressed as effective dose equivalent. DOE must also
comply with legally applicable requirements (e.g., 40 CFR Parts 61, 191,
and 192 and 10 CFR Parts 60 and 72), including administrative and
procedural requirements. Except for those provided in paragraph
II.1a(4), administrative and procedural requirements of legally
applicable regulations are not addressed in this Order. Such legally
applicable regulations must be consulted for provisions not addressed in
this Order.
a. DOE Public Dose Limit--All Exposure Modes, All DOE Sources of
Radiation. Except as provided by II.1a(4), the exposure of members
of the public to radiation sources as a consequence of all routine
DOE activities shall not cause, in a year, an effective dose
equivalent greater than 100 mrem (1 mSv). Dose evaluations should
reflect realistic exposure conditions (see II.6b).
(1) Dose Components. The limit of 100 mrem (1 mSv) effective dose
equivalent in a year specified in paragraph II.1a is the sum of
the effective dose equivalent (or deep dose equivalent, if
dosimeter data are used) from exposures to radiation sources
external to the body during the year plus the committed
effective dose equivalent from radionuclides taken into the
body during the year.
(2) Exposure Modes. Other than for sources specifically excepted,
doses to members of the public from all exposure modes that
could contribute significantly to the total dose shall be
considered for evaluation. Requirements and methods for
performing the evaluations are discussed in paragraph II.6.
(3) Application. The public dose limits in paragraph II.1a apply
to doses from exposures to radiation sources from routine
activities, including remedial actions and naturally occurring
radionuclides released by DOE processes and operations. The
dose limits also apply to the doses to individuals who are
exposed to radiation or contamination by radionuclides at
properties subsequent to remedial action and release of the
property. Limits for radon and its decay products in air are
provided in terms of Working Levels and concentrations in air
and are addressed independently (Chapter IV and Figure III-1).
In addition, DOE operators are required to report DOE-related
effective dose equivalent contributions of 10 mrem (0.10 mSv)
or more in a year (see paragraph II.7).
(a) Doses from Sources Other than DOE Man-Made or Enhanced
Natural Radionuclides. Except for medical sources,
consumer products, residual fallout from past nuclear
accidents and weapons tests, and naturally occurring
radiation sources, DOE operators shall make a reasonable
effort to be aware of the existence of other than DOE
man-made sources of radiation which, combined with the
DOE sources, might present a potential for exceeding
contributions of 10 mrem (0.1 mSv) effective dose
equivalent in a year. Reasonable efforts shall be made
to limit dose to members of the public, from multiple
sources of radiation, to 100-mrem (1 mSv) effective dose
equivalent, or less, in a year. EH-1 and the appropriate
Headquarters Program Offices shall be notified if the
100-mrem in a year dose limit cannot be achieved.
(b) Doses Not Included in Evaluations. The public dose limits
do not apply to doses from medical exposures, consumer
products, and generally do not apply to doses from
naturally occurring radiation sources or from exposures
due to accident conditions, where controls of exposures
cannot be maintained. The policy and requirements
relating to protective actions following the uncontrolled
release of radionuclides are set forth in the DOE 5500
series of directives. Requirements for planning to
prevent or mitigate accidents and their effects are
presented in DOE 5480.5 and DOE 5480.6.
(c) Doses from Underground Nuclear Weapons Tests. The
unanticipated release of radioactive material due to
venting or seepage from underground nuclear weapons is
considered to be an accident. However, the release of
radioactive material that results from planned sampling
or reentry following an underground nuclear weapons test
is not an accidental condition, and shall be controlled
in accordance with this standard.
(4) Exceptions. Unusual circumstances could affect a DOE activity
in such a manner that the potential public dose could exceed an
effective dose equivalent of 100 mrem (1 mSv) in a year.
(a) Temporary Increases of Dose Limit. If avoidance of the
higher exposures is impracticable, the Manager of the DOE
Field Office, in coordination with their Program Office,
may request, from EH-1, specific authorization for a
temporary public dose limit higher than 100 mrem (1
mSv), but not to exceed 500 mrem (5 mSv), for the year.
The temporary higher dose limit derives from ICRP
recommendations (ICRP Publication 45) for a principal
stochastic dose limit of 100 mrem (1 mSv) effective dose
equivalent in a year for exposures to the public, and a
subsidiary dose limit of 500 mrem (5 mSv) effective dose
equivalent in a year, for some years, if the dose averaged
over a lifetime does not exceed the principal limit of 100
mrem (1 mSv) effective dose equivalent per year. The
specific sources excepted in paragraph II.1a(3)(b) are
also excepted for II.1a(4)(a).
(b) Justification for Increase of Public Dose Limit. A
request to EH-1 for a dose limit higher than 100 mrem
(1 mSv) shall be accompanied by documentation that
discusses the need for the increase, the alternatives
considered, and the application of the ALARA process.
EH-1 may approve such a request, or a lesser increase in
the public dose limit, as appropriate.
b. Airborne Emissions Only, All DOE Sources of Radionuclides. To the
extent required by the Clean Air Act, the exposure of members of
the public to radioactive materials released to the atmosphere as
a consequence of routine DOE activities shall not cause members of
the public to receive, in a year, an effective dose equivalent
greater than 10 mrem (0.1 mSv). Exposures to, and releases of,
radon-220, radon-222, and their respective decay products are
subject to DOE limits (See Figure III-3 and paragraphs IV.4b and
IV.6).
(1) Title 40 CFR Part 61. The public dose limits as outlined in
paragraph II.1b are established by EPA regulation 40 CFR Part
61, Subpart H, under the authority of the Clean Air Act.
These limits apply offsite where the members of the public
reside or abide. Subparts Q and T provide radon flux limits
for DOE radium storage and disposal facilities (Chapter IV)
and DOE inactive uranium mill tailings sites regulated under
40 CFR Part 192.
(2) AIRDOS/RADRISK Codes. To demonstrate compliance analytically
with air emissions for the Clean Air Act Standards, doses to
the individuals shall be evaluated using the version of
AIRDOS/RADRISK known as CAP-88 or, when available and approved,
AIRDOS-PC. Other computer codes or models, such as "Comply
Code," which are specifically approved in accordance with 40
CFR Part 61, may also be used.
(3) Environmental Measurements. Compliance may also be
demonstrated through environmental or effluent measurements
using EPA-approved techniques. In this case, the doses
estimated are to individuals in areas offsite, where they are
assumed to reside at the point of maximum annual air
concentration.
c. All Exposure Modes, Sources from Management and Storage of Spent
Nuclear Fuel, High-Level, and Transuranic Wastes at Disposal
Facilities. To the extent required by 40 CFR Part 191, the
exposure of members of the public to direct radiation or
radioactive material released from DOE management and storage
activities at a disposal facility for spent nuclear material or
for high-level or transuranic radioactive wastes that are not
regulated by the NRC shall not cause members of the public to
receive, in a year, a dose equivalent greater than 25 mrem (0.25
mSv) to the whole body or a committed dose equivalent greater than
75 mrem (0.75 mSv) to any organ.
(1) 40 CFR Part 191. The dose limits as outlined in paragraph
II.1c, are established by Section 191.03(b) of EPA regulation
40 CFR Part 191, Subpart A, "Environmental Standards for
Management and Storage." The implementation of the
requirements of Subpart B, "Environmental Standards for
Disposal," is beyond the scope of this Order. DOE waste
management and storage activities at facilities other than
disposal facilities are subject to the dose limits outlined
in paragraph II.1c. The Waste Isolation Pilot Plant, for
purposes of this Order, is considered to be a disposal facility
subject to this Order and 40 CFR Part 191. Other requirements
and guidelines for the management and storage of spent nuclear
fuel and high-level and transuranic waste at DOE facilities
that are not licensed by the NRC are given in DOE 5820.2A.
(2) Regulatory Requirements. DOE facilities and operations, in
some instances, are subject to the regulatory requirements of
the NRC and the EPA, e.g., 10 CFR Parts 60 and 72 and 40 CFR
Parts 61, 191, and 192. It is Departmental policy that DOE
facilities and operations will comply fully with the
requirements of those and other applicable regulatory
requirements. In addition, these same DOE facilities and
operations shall comply with all applicable requirements in
this Order unless they are duplicative or conflict with any
of the other Federal regulatory requirements. The resolution
of issues concerning duplicative or conflicting requirements
will be conducted pursuant to the issue coordination provisions
of DOE 5400.2A.
(3) Evaluation of Exposure Modes. Dose conversion factors that
provide dose estimates for exposure to concentrations of
specific radionuclides in air and water and selected exposure
modes are provided in the documents Federal Guidance Report
No. 11 (EPA-520/1-88-020), DOE/EH-0070 and DOE/EH-0071. Use
of these factors is discussed in paragraph II.6b.
d. Drinking Water Pathway Only, All DOE Sources of Radionuclides. It
is the policy of DOE to provide a level of protection for persons
consuming water from a public drinking water supply operated by
the DOE, either directly or through a DOE contractor, that is
equivalent to that provided to the public by the public community
drinking water standards of 40 CFR Part 141. These systems shall
not cause persons consuming the water to receive an effective dose
equivalent greater than 4 mrem (0.04 mSv) in a year. Combined
radium-226 and radium-228 shall not exceed 5x10-9 micro Ci/ml and
gross alpha activity (including radium-226 but excluding radon and
uranium) shall not exceed 1.5x10-8 micro Ci/ml.
(1) DOE Drinking Water Systems. The dose limit is consistent with
the drinking water criteria in 40 CFR Part 141, "National
Interim Primary Drinking Water Regulations (Safe Drinking Water
Act)."
(2) Dose Components. The dose limit is the effective dose
equivalent to individuals whose exclusive source of drinking
water contains a radionuclide, or a mixture of radionuclides,
at a monthly average level of four percent of the appropriate
DCG value. For simplicity, it is assumed that site workers
are also exposed to four percent of DCG values or the radium
and gross alpha levels in II.1d for drinking water while away
from the DOE site.
(3) Impact on Other Systems. The liquid effluents from DOE
activities shall not cause private or public drinking water
systems downstream of the facility discharge to exceed the
drinking water radiological limits in 40 CFR Part 141.
2. THE ALARA PROCESS. Field Elements shall develop a program and shall
require contractors to implement the ALARA Process for all DOE
activities and facilities that cause public doses.
a. Considerations. ALARA requires judgment with respect to what is
reasonably achievable. Factors that relate to societal,
technological, economic, and other public policy considerations
shall be evaluated to the extent practicable in making such
judgments. Factors to be considered, at a minimum, shall include:
(1) The maximum dose to members of the public;
(2) The collective dose to the population;
(3) Alternative processes, such as alternative treatments of
discharge streams, operating methods, or controls;
(4) Doses for each process alternative;
(5) Costs for each of the technological alternatives;
(6) Examination of the changes in cost among alternatives;
(7) Changes in societal impact associated with process
alternatives, e.g., differential doses from various pathways.
b. Evaluations. A quantitative cost-benefit analysis (e.g.,
optimization) could be performed, given the results of the
considerations noted in paragraph II.2a, above. However, the
parameters needed to evaluate the cost-benefit analyses are
difficult to quantify, and evaluations themselves can be expensive.
Furthermore, the evaluations include many additional assumptions,
judgment, and limitations that are often difficult to reflect as
uncertainties in the analyses. Therefore, except for meeting
requirements of the National Environmental Policy Act, qualitative
analyses are acceptable, in most instances, for ALARA judgments,
especially where potential doses are well below the dose limit. The
bases for such judgments should be documented. More detailed
analyses should be considered if the decisions might result in doses
that approach the limit.
3. MANAGEMENT AND CONTROL OF RADIOACTIVE MATERIALS IN LIQUID DISCHARGES
AND PHASEOUT OF SOIL COLUMNS. In addition to the requirement to limit
dose to members of the public (onsite or offsite) in accordance with
the standards established in paragraphs 11.1a and II.1d, further
controls are imposed on liquid releases to protect resources such as
land, surface water, ground water, and the related ecosystems from
undue contamination. DCGs are not release limits, but rather are
screening values for considering BAT for these discharges and for
making dose estimates. The following requirements apply at the point
of discharge from the conduit to the environment.
a. Discharges of Liquid Waste to Surface Waters.
(1) Discharge at Greater Than DCG Level. For liquid wastes
containing radionuclides from DOE activities which are
discharged to surface water, the best available technology
(BAT) is the prescribed level of treatment if the surface
waters otherwise would contain, at the point of discharge and
prior to dilution, radioactive material at annual average
concentrations greater than the DCG values in liquids given
in Chapter III. The BAT selection process shall be implemented
in accordance with II.3a(1)(a) and (b), below. Although there
is no known practicable method for removing tritium from liquid
waste streams, facilities and operations are to be designed and
operated so that tritium sources and releases are considered in
the ALARA process.
(a) BAT Selection. Selection of the best available technology
for a specific application will be made from among
candidate alternative treatment technologies which are
identified by an evaluation process that includes factors
related to technology, economics, and public policy
considerations. Factors that are to be considered in
selecting BAT, at a minimum, shall include:
1 the age of equipment and facilities involved;
2 the process employed;
3 the engineering aspects of the application of
various types of control techniques;
4 process changes;
5 the cost of achieving such effluent reduction;
6 non-water quality environmental impact (including
energy requirements);
7 safety considerations; and
8 public policy considerations.
BAT analyses are difficult to express quantitatively
because the factors do not have a common denominator.
However, consideration of the factors will permit
qualitative evaluations which will support judgments.
(b) Plan and Schedule for Implementation. A plan and schedule
to install waste treatment systems in existing facilities,
if justified by a BAT analysis, shall be developed within
6 months of the issuance date of this Order, to permit
compliance with paragraph II.3a(1) at the earliest
practicable time. The plan shall include an ALARA section
on tritium, where applicable. General design criteria are
presented in DOE 6430.1A.
(c) Approval. The plan shall be submitted for approval to
the responsible DOE Field Office Manager and updated
annually, consistent with the provisions of DOE 5820.2A
for preparing and updating Waste Management Plans.
(2) Discharge at Less Than DCG Level. Implementation of the BAT
process for liquid radioactive wastes is not required where
radionuclides are already at a low level, i.e., the annual
average concentration is less than DCG level. In that case,
the cost consideration component of BAT analysis precludes the
need for additional treatment, since any additional treatment
would be unjustifiable on a cost-benefit basis. Therefore,
additional treatment will not be required for waste streams
that contain radionuclide concentrations of not more than the
DCG values in Chapter III at the point of discharge to a
surface waterway. However, the ALARA provisions are
applicable.
(3) Multiple Radionuclides. For purposes of II.3a(1), above, the
DCG for liquid waste streams containing more than one type of
radionuclide shall be the sum of the fractional DCG values.
(4) Sedimentation. To prevent the buildup of radionuclide
concentrations in sediments, liquid process waste streams
containing radioactive material in the form of settleable
solids may be released to natural waterways if the
concentration of radioactive material in the solids present
in the waste stream does not exceed 5 pCi (0.2 Bq) per gram
above background level, of settleable solids for alpha-emitting
radionuclides or 50 pCi (2 Bq) per gram above background level,
of settleable solids for beta-gamma-emitting radionuclides.
(5) Interim Dose Limit for Native Aquatic Animal Organisms. To
protect native animal aquatic organisms, the absorbed dose to
these organisms shall not exceed 1 rad per day from exposure to
the radioactive material in liquid wastes discharged to natural
waterways. DOE publication DOE/EH-0173T provides guidance on
monitoring and calculating dose for aquatic organisms.
(6) New Facilities. New facilities shall be designed and
constructed to meet the discharge requirements shown in
paragraph 11.3a.
b. Discharges of Liquid Waste to Aquifers and Phaseout of Soil Columns.
(1) Phasing Out the Use of Soil Columns. The use of soil columns
(i.e., trenches, cribs, ponds, and drain fields) to retain, by
sorption or ion exchange, suspended or dissolved radionuclides
from liquid waste streams shall be discontinued at the earliest
practicable time in favor of an acceptable alternative disposal
means. DOE activities that currently discharge liquids
containing radioactive materials not first treated by BAT to
soil columns, shall develop, within 6 months of the issuance
date of this Order, a plan and schedule for implementing
alternate acceptable disposal at the earliest practicable time.
The BAT selection process shall be applied to those liquid
waste streams that will continue to be discharged to soil
columns for indefinite periods and which contain
process-derived radionuclides. The plan shall be submitted for
approval to the respective DOE Field Office Manager and updated
annually, consistent with the provisions of DOE 5820.2A for
preparing and updating Waste Management Plans.
(2) Prohibition of New or Increased Discharge Quantities and New
Soil Columns. Except as permitted by the provisions in
paragraph II.3e(1), new or increased discharges of
radionuclides in liquid waste to active soil columns and
virgin soil columns shall be prohibited after the effective
date of this Order.
c. Management of Soil Columns, Natural Drainage Systems, and Ground
Water at Inactive Sites Previously Contaminated with Radioactive
Material.
(1) Inactive Receptors. Contaminated soil columns, drainage
systems, and ground water to which contaminated liquid
discharges have been discontinued shall be managed or
decontaminated pursuant to the procedures and requirements
of DOE 5480.4 and in the 5400 series.
(2) Discharge of Other Liquids. Liquid discharges, even though
uncontaminated, are prohibited in inactive release areas to
prevent the further spread of radionuclides previously
deposited.
d. Discharges of Liquid Waste to Sanitary Sewerage. The BAT selection
process shall be implemented if liquid wastes discharged from DOE
activities into sanitary sewerage contain radionuclides at
concentrations, averaged monthly, would otherwise be greater than
five times the DCG values for liquids given in Chapter III at the
point of discharge. That is, the BAT selection process shall be
implemented if the total of the fractions of the average
concentrations for each radionuclide to its respective DCG value
would otherwise exceed 5.
(1) Discharges to public sewers should be coordinated with the
operators of the waste water treatment works.
(2) Concentrations shall be controlled so that long-term buildup
of radionuclides in solids will not present a handling and
disposal problem at sewage disposal plants.
(3) Liquid wastes containing concentrations or quantities of
radioactive materials that, when averaged monthly, are
greater than those specified in paragraph II.3d may be
discharged into a chemical or sanitary sewerage system (e.g.,
systems with drain fields excepted) if the system is owned by
the Federal Government. However, ALARA process considerations
are required. Such a sewerage system will provide liquid waste
treatment prior to discharge to surface waters in accordance
with the requirements of paragraph II.3a(1).
(4) Operators should ensure that the total annual discharge of
radioactive material to the sanitary sewer system will not
cause exposures to members of the general public that will
result in doses exceeding a small fraction of the basic
annual dose limit.
e. Exceptions for Liquid Waste Control Requirements.
(1) Interim Control Strategies. DOE Field Office Managers
responsible for DOE activities that cannot comply, when this
Order is issued, with requirements shown in paragraph II.3,
shall develop an interim control strategy with adequate
documentation identifying the alternatives considered and
evaluations thereof. Such interim control strategies shall be
adopted and implemented under the provisions of DOE 5820.2A,
Chapter III, paragraph 3a(2), within 6 months of the issuance
of this Order, and shall be reevaluated every two years
thereafter.
(2) Tritium Control. There is no practicable technology available
for removing tritium from dilute liquid waste streams.
Therefore, process alternatives that reduce the amount of
tritium entering the liquid waste streams shall be identified
and evaluated in accordance with the DOE ALARA policy. Tritium
decay in transit in confined ground water may be an acceptable
alternative to direct release to the atmosphere or to surface
waters. A description and summary of the alternatives
considered in the control of tritium releases shall be
incorporated into the site Waste Management Plan required by
DOE 5820.2A.
4. MANAGEMENT OF LOW-LEVEL RADIOACTIVE SOLID WASTE. The requirements for
the management of low-level wastes are presented in DOE 5400.1 and DOE
5820.2A. Design, operational, and monitoring requirements for disposal
of solid low-level waste containing no constituents regulated by The
Resource Conservation and Recovery Act (RCRA) are addressed in DOE
5820.2A.
5. RELEASE OF PROPERTY HAVING RESIDUAL RADIOACTIVE MATERIAL.
a. Release of Real Property. Release of real property (land and
structures) shall be in accordance with the guidelines and
requirements for residual radioactive material presented in
Chapter IV. These guidelines and requirements apply to both
DOE-owned facilities and to private properties that are being
prepared by DOE for release. Real properties owned by DOE that
are being sold to the public are subject to the requirements of
Section 120(h) of the Comprehensive Environmental Response
Compensation and Liability Act (CERCLA), as amended, concerning
hazardous substances, and to any other applicable Federal, State,
and local requirements. The requirements of 40 CFR Part 192 are
applicable to properties remediated by DOE under Title I of the
Uranium Mill Tailings Radiation Control Act (UMTRA).
b. Release of Personal Property. Personal property, which potentially
could be contaminated, may be released for unrestricted use if the
results of a survey with appropriate instruments indicate that the
property is less than the contamination limits presented in Figure
IV-1.
c. Release of Materials and Equipment.
(1) Surface Contamination Levels. Prior to being released,
property shall be surveyed to determine whether both removable
and total surface contamination (including contamination
present on and under any coating) are in compliance with the
levels given in Figure IV-1 and that the contamination has been
subjected to the ALARA process.
(2) Potential for Contamination. Property shall be considered to
be potentially contaminated if it has been used or stored in
radiation areas that could contain unconfined radioactive
material or that are exposed to beams of particles capable of
causing activation (neutrons, protons, etc.).
(3) Surveys. Surfaces of potentially contaminated property shall
be surveyed using instruments and techniques appropriate for
detecting the limits stated in Figure IV-1.
(4) Inaccessible Areas. Where potentially contaminated surfaces
are not accessible for measurement (as in some pipes, drains,
and ductwork), such property may be released after case-by-case
evaluation and documentation based on both the history of its
use and available measurements demonstrate that the
unsurveyable surfaces are likely to be within the limits given
in Figure IV-1.
(5) Records. The records of released property shall include:
(a) A description or identification of the property;
(b) The date of the last radiation survey;
(c) The identity of the organization and the individual who
performed the monitoring operation;
(d) The type and identification number of monitoring
instruments;
(e) The results of the monitoring operation; and
(f) The identity of the recipient of the released material.
(6) Volume Contamination. No guidance is currently available for
release of material that has been contaminated in depth, such
as activated material or smelted contaminated metals (e.g.,
radioactivity per unit volume or per unit mass). Such
materials may be released if criteria and survey techniques
are approved by EH-1.
6. DEMONSTRATION OF COMPLIANCE WITH THE DOSE LIMITS. Compliance with the
dose limits of this Order shall be demonstrated by documentation of an
appropriate combination of measurements and calculations to evaluate
potential doses and the results of the evaluations.
a. Monitoring and Surveillance. General requirements for routine
effluent monitoring are part of the environmental monitoring plan
prescribed in DOE 5400.1. Specific requirements for radiological
effluent monitoring and environmental surveillance and their
schedule of implementation are prescribed in DOE publication DOE/
EH-0173T which deal with radiological effluent monitoring and
environmental surveillance. The monitoring requirements are
applicable to all DOE and DOE contractor operations that are
subject to the standards and requirements of this Order.
b. Dose Evaluations. Doses to members of the public in the vicinity
of DOE activities shall be evaluated and documented to demonstrate
compliance with the dose limits of this Order and to assess
exposures of the public from unplanned events. Collective doses
to the public within 80 km of the site shall also be evaluated and
documented at least annually.
(1) Modeling. Analytical models used for dose evaluations shall
be appropriate for characteristics of emissions (e.g., gas,
liquid, or particle; depositing or nondepositing; buoyant or
non-buoyant); mode of release (e.g., stack or vent; crib or
pond; surface water or sewer; continuous or intermittent);
environmental transport medium (e.g., air or water); and
exposure pathway (e.g., inhalation; ingestion of food, water,
or milk; direct radiation). Information on dispersion
(transport and diffusion) in the environment, demography,
land use (including the location and number of dairy and
slaughter animals), food supplies, and exposure pathways used
in the dose calculations shall be appropriate to evaluate
actual and potential doses in the environs of DOE facilities.
Such information shall be updated as necessary to document
significant changes that could affect dose evaluations. Dose
evaluation models that are codified, approved, or accepted by
regulatory or other authorities shall be used where
appropriate, such as the AIRDOS/RADRISK codes for demonstrating
compliance with 40 CFR Part 61, Subpart H.
(2) Dose Conversion Factors. Except as provided in paragraph
II.6b(2)(d), tables of approved dose conversion factors in
paragraphs II.6b(2)(a), (b), and (c), below, shall be used to
evaluate doses unless otherwise legally required, e.g., use
of AIRDOS/RADRISK codes pursuant to 40 CFR Part 61, Subpart H.
(a) Committed Dose Conversion Factors. Radionuclides taken
into the body, generally by exposure modes whereby the
radionuclide is ingested or inhaled, will continue to
irradiate the body as long as they exist and are retained
by the body. The dose delivered to a body over the
lifetime of the individual from a single committed dose
conversion factors shall be used, as appropriate, and are
presented in EPA-520/1-88-020, Federal Guidance Report No.
11, "Limiting Values of Radionuclide Intake and Air
Concentration and Dose Conversion Factors for Inhalation,
Submersion, and Ingestion," and in DOE/EH-0071, "Internal
Dose Conversion Factors for Calculation of Dose to the
Public." These conversion factors are based upon the ICRP
reference man model, and the committed dose is the dose
integrated over an interval of 50 years.
(b) External Dose Conversion Factors. The doses from exposure
to external radiation from radionuclide concentrations in
air and in water that result from submersion or from
exposure to contaminated plane surfaces shall be
estimated, as appropriate, using the external dose
conversion factors presented in EPA-520/1-88-020, Federal
Guidance Report No. 11, "Limiting Values of Radionuclides
Intake and Air Concentration and Dose Conversion Factors
for Inhalation, Submersion, and Ingestion" and in
DOE/EH-0070, "External Dose-Rate Conversion Factors for
Calculation of Dose to the Public."
(c) Derived Concentration Guides (DCG). DCG values are
presented as reference values in Chapter III for each of
three exposure modes: inhalation of air containing the
radionuclide; submersion in a semi-infinite cloud of air
containing the radionuclide; and ingestion of water
containing the radionuclide. The DCG tables may be used
to evaluate only the three exposure modes upon which
they are based.
(d) Other Methods and Alternatives. Methods and alternatives
other than those discussed above and as prescribed in
applicable regulations shall be submitted to EH-1 for
approval. EH-1 may approve the alternative method, if
appropriate.
(3) Parametric Considerations.
(a) Dose limits for members of the general public, from
routine operation of a DOE activity, shall be expressed
as a dose received by the individuals during the year
(if, for example, the exposure is external to the body)
or the committed dose received by the individual over a
period of 50 years from radionuclides taken into the
body during the year. The limits should not be
interpreted as dose rates per se, especially not in the
sense of instantaneous dose rates.
(b) Doses calculated should be as realistic as practicable.
Consequently, the individuals subject to the greatest
exposure shall be identified, to the extent practicable,
so that the highest dose might be determined.
(c) Dose limits apply to actual or committed doses to real
individuals. Consequently, all factors germane to dose
determination should be applied. Alternatively, if
available data are not sufficient to evaluate these
factors or if they are too costly to determine, the
assumed parametric values shall be sufficiently
conservative so that it is unlikely that individuals
would actually receive a dose that would exceed the dose
calculated using the values assumed.
(d) Parametric values used in performing dose calculations
shall be recorded.
(e) Collective public dose in the environs of a site with
multiple emission points may be estimated using the
assumption that all emissions occur from a single point
centrally located on the site. Guidance on combining
emission points is provided in EPA-450/477-001,
"Guidelines for Air Quality Maintenance Planning and
Analysis," Vol. 10, Revised: Procedures for Evaluating
Air Quality Impact of New Stationary Sources.
(f) The assumption of a single point of emission, as discussed
in II.6b(3)(e), may be used to calculate public dose for
the maximally exposed individuals if the emission points
are close to one another relative to the distance to the
site boundary. Otherwise, the public dose to the
maximally exposed individuals should be determined taking
into consideration the actual locations of emissions on
the site with respect to the offsite locations.
7. REPORTING REQUIREMENTS. In addition to the reporting requirements of
DOE 5400.1 and DOE 5484.1, the responsible DOE Field Office Manager
shall notify, in a timely manner, the relevant Program Office(s) and the
Deputy Assistant Secretary for Environment (EH-20) of actual or
potential exposures of members of the public that could result in
either an effective dose equivalent from DOE sources exceeding 10 mrem
(0.1 mSv) in a year; or exceeding any limit or not meeting any other
requirement specified in this Order or any other legally applicable
limits, or a combined dose equal to or greater than 100 mrem (1 mSv)
effective dose equivalent in a year due to DOE and other man-made
sources of radiation (medical, consumer products, and natural sources
excepted). For purposes of determining compliance with the reporting
requirements of 40 CFR Parts 302 and 355, releases of source,
by-product, and special nuclear material that occur from DOE activities
are considered to be "Federally permitted" releases if they do not
exceed the limits specified in this Order and the operations and
releases are in compliance with DOE policies, and guidelines, and
requirements specified in DOE Orders, including DOE 5820.2A.
8. RECORDS.
a. Content. Records developed shall include information and data
necessary to identify and characterize releases of radioactive
material to the environment, their fate in the environment, and
their probable impact on radiation doses to the public. Basic
information used assess compliance with the requirements of this
Order pursuant to paragraph 11.6, and the results of such
assessments, shall be incorporated as part of the record.
b. Retention. Information and data developed pursuant to this Order
shall be retained consistent with the requirements of DOE 1324.2A
and other legally applicable requirements.
9. UNITS. All reports, notifications, and records developed pursuant to
DOE Order requirements shall present data in the units used in the
applicable regulation or DOE Order.
CHAPTER III
DERIVED CONCENTRATION GUIDES
FOR AIR AND WATER
1. PURPOSE. The Derived Concentration Guide (DCG) values listed in this
chapter are provided as reference values for conducting radiological
environmental protection programs at operational DOE facilities and
sites. Derived Air Concentrations (DAC) guides for controlling
occupational intake of radionuclides through inhalation are listed in
DOE 5480.11.
2. BASIS. The DCG values are presented for each of three exposure modes:
1) ingestion of water; 2) inhalation of air; and 3) immersion in a
gaseous cloud. The DCG values for internal exposure shown in Figure
III-1 are based on a committed effective dose equivalent of 100 mrem
for the radionuclide taken into the body by ingestion or inhalation
during one year. To use the DCGs for comparison with the DOE drinking
water systems criterion of 4 mrem/yr (0.04 mSv/yr), use 4 percent of
the DCG values for ingestion. Compliance with the 40 CFR Part 61,
Subpart H, criterion of 10 mrem/yr (0.10 mSv/yr) effective dose
equivalent is demonstrated using the AIRDOS/RADRISK models prescribed
by the EPA. Alternative gastrointestinal-tract (GI-tract) absorption
factors (f1) and lung retention classes (noted as D, W, or Y in the
Task Group Lung Model used to produce the inhalation dose factors
reported in ICRP Publication 30) are listed for specific compounds, by
element, in Figure III-2 for cross-referencing with the internal DCGs
in Figure III-1. The data in Figure III-2 are listed in alphabetical
order, by element name. Removal half-times assigned to the compounds
with lung retention classes D, W, and Y are 0.5, 50, and 500 days,
respectively. The air immersion DCG values shown in Figure III-3 are
based on an effective dose equivalent of 100 mrem from exposure during
one year. Figure III-1 contains six columns of information:
Radionuclide/Chemical Form/Isomer Half-Life; f1 Value (GI-tract
absorption); Ingested Water DCG ( Ci/mL); Inhaled Air DCG for Lung
Retention Class D ( Ci/mL); and Inhaled Air DCG for Lung Retention
Class W ( Ci/mL); and Inhaled Air DCG for Lung Retention Class Y
( Ci/mL). Figure III-2 contains five columns of information:
Element/Symbol; Atomic Number; compound; f1 value; and Lung Retention
Class. Figure III-3 contains three columns of information:
Radionuclide; Half-life in units of seconds (s), minutes (min), hours
(h), days (d), or years (yr); and Air Immersion DCG ( Ci;mL).
a. Exposure Conditions for Ingestion of Water and Inhalation. Under
conditions of continuous exposure, members of the public are
assumed to ingest 730 liters of drinking water or to inhale 8,400
cubic meters of air (for exposure of 24 hours per day, 365 days
per year), as given for the "reference man" in ICRP Publication
23. Only single modes of exposure were considered in the
calculation of the DCGs - that is, they apply to either inhalation
or ingestion, not to a combination of both. The dose factors used
to calculate the DCG values for internal exposure were taken from
the report "Internal Dose Conversion Factors for Calculation of
Dose to the Public" (DOE/EH-0071). For ingestion, DCG values are
tabulated for all values of f1 for each radionuclide given in ICRP
Publication 30, as modified for several transuranic elements by
ICRP Publication 48. For inhalation, DCG values are given for all
combinations of f1 and lung retention class (D, in, or Y) given by
the ICRP, as tabulated in Figure III-2. For radionuclides with
multiple f1 listings, where specific data for an airborne or
liquid release are lacking, the f1 value that results in the most
restrictive DCG for ingested water or inhaled air should be used.
b. Exposure Conditions for Air Immersion. The air immersion DCGs were
calculated for a continuous, nonshielded exposure via immersion in a
semi-infinite atmospheric cloud. The dose conversion factors used
to calculate the DCG values for air immersion were taken from the
report "External Dose-Rate Conversion Factors for Calculation of
Dose to the Public" (DOE/EH-0070). The DCG value for air immersion
listed in Figure III-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 Figure
III-3, the DCG value is determined by the limit on annual effective
dose equivalent. Thus, the few cases where the DCG value is
determined by the limit on annual dose equivalent to skin are
indicated in the figure by an appropriate footnote. Again, the DCGs
listed in Figure III-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
DCGs given in Figure III-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 DCG value for inhalation has been calculated
(using the ICRP inhalation dose equivalent factors), but for
which the DCG value for external exposure to a contaminated
atmospheric cloud is more restrictive (i.e., results in a
lower DCG 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) 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.
c. Application to Mixtures of Radionuclides. The DCG values are given
for individual radionuclides. For known mixtures of radionuclides,
the sum of the ratios of the observed concentration of each
radionuclide to its corresponding DCG must not exceed 1.0.
3. LIMITATIONS. The values given in Figures III-1 and III-3 account for
only three exposure pathways (ingested water or inhaled air or air
immersion) and do not include other potentially significant pathways.
When more complex environmental pathways are involved, a more complete
pathway analysis is required for calculating public radiation doses
resulting from the operation of DOE facilities.
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
H-3 (Water) 2.E-03 1/ 1.E-07 2/
H-3 (Elemental) 2.E-02 2/
Be-7 5.E-03 1.E-03 5.E-08 4.E-08
Be-10 5.E-03 3.E-O5 4.E-10 3.E-11
C-11 (Org) 1.E-02 1.E-06
C-11 (CO) 3.E-06
C-11 (CO2) 1.E-06
C-14 (Org) 7.E-02 6.E-09
C-14 (CO) 4.E-06
C-14 (CO2) 5.E-07
F-18 3/ 1.E+00 1.E-03 2.E-07 2.E-07 2.E-07
Na-22 1.E+00 1.E-05 1.E-09
Na-24 3/ 1.E+00 1.E-04 1.E-08
Mg-28 5.E-01 2.E-05 4.E-09 3.E-09
Al-26 1.E-02 1.E-05 1.E-10 2.E-10
Si-31 1.E-02 3.E-04 6.E-08 7.E-08 6.E-08
Si-32 1.E-02 8.E-05 6.E-10 3.E-10 1.E-11
P-32 8.E-01 2.E-05 2.E-09 9.E-10
P-33 8.E-01 2.E-04 2.E-08 6.E-09
S-35 8.E-01 3.E-04 4.E-08 5.E-09
1.E-01 2.E-04
S-35 (Gas) 3.E-08
Cl-36 3/ 1.E+00 5.E-05 6.E-09 6.E-10
Cl-38 1.E+00 7.E-04 1.E-07 1.E-07
Cl-39 1.E+00 1.E-03 1.E-07 1.E-07
K-40 1.E+00 7.E-06 9.E-10
K-42 1.E+00 1.E-04 1.E-08
K-43 3/ 1.E+00 2.E-04 2.E-08
K-44 1.E+00 9.E-04 2.E-07
Figure III-1
Derived Concentration Guides (DCGs) for Members of the Public from
Ingested Water and Inhalation Resulting in 100 mrem/yr
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
K-45 1.E+00 1.E-03 3.E-07
Ca-41 3.E-01 1.E-04 9.E-09
Ca-45 3.E-01 5.E-05 2.E-09
Ca-47 3.E-01 2.E-05 2.E-09
Sc-43 1.E-04 2.E-04 5.E-08
Sc-44m 1.E-04 1.E-05 2.E-09
Sc-44 3/ 1.E-04 1.E-04 3.E-08
Sc-46 1.E-04 2.E-05 6.E-10
Sc-47 1.E-04 7.E-05 7.E-09
Sc-48 1.E-04 2.E-05 3.E-09
Sc-49 1.E-04 6.E-04 1.E-07
Ti-44 1.E-02 7.E-06 3.E-11 7.E-11 1.E-11
Ti-45 3/ 1.E-02 2.E-04 6.E-08 8.E-08 7.E-08
V-47 1.E-02 9.E-04 2.E-07 2.E-07
V-48 1.E-02 2.E-05 3.E-09 2.E-09
V-49 1.E-02 3.E-03 8.E-08 4.E-08
Cr-48 1.E-01 2.E-04 3.E-08 2.E-08 2.E-08
1.E-02 2.E-04
Cr-49 3/ 1.E-01 8.E-04 2.E-07 2.E-07 2.E-07
1.E-02 8.E-04
Cr-51 1.E-01 1.E-03 1.E-07 6.E-08 5.E-08
1.E-02 1.E-03
Mn-51 1.E-01 6.E-04 1.E-07 1.E-07
Mn-52m 3/ 1.E-01 9.E-04 2.E-07 2.E-07
Mn-52 1.E-01 2.E-05 3.E-09 2.E-09
Mn-53 1.E-01 1.E-03 6.E-08 3.E-08
Mn-54 1.E-01 5.E-05 2.E-09 2.E-09
Mn-56 3/ 1.E-01 1.E-04 4.E-08 5.E-08
Fe-52 1.E-01 3.E-05 7.E-09 6.E-09
Fe-55 1.E-01 2.E-04 5.E-09 1.E-08
Fe-59 1.E-01 2.E-05 8.E-10 1.E-09
Fe-60 1.E-01 9.E-07 2.E-11 4.E-11
Co-55 5.E-02 3.E-05 7.E-09 6.E-09
3.E-01 4.E-05
Co-56 5.3-02 1.E-05 7.E-10 5.E-10
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Co-56 3.E-01 1.E-05
Co-57 5.E-02 2.E-04 7.E-09 2.E-09
3.E-01 1.E-04
Co-58m 5.E-02 2.E-03 2.E-01 2.E-07
3.E-01 2.E-03
Co-58 5.E-02 5.E-05 3.E-09 2.E-09
3.E-01 4.E-05
Co-60m 3/ 5.E-02 4.E-02 9.E-06 6.E-06
3.E-01 4.E-02
Co-60 5.E-02 1.E-05 4.E-10 8.E-11
3.E-01 5.E-06
Co-61 5.E-02 5.E-04 1.E-07 1.E-07
3.E-01 6.E-04
Co-62m 5.E-02 1.E-03 4.E-07 4.E-07
3.E-01 1.E-03
Ni-56 5.E-02 4.E-05 5.E-09 3.E-09
Ni-56 (Vapor) 3.E-09
Ni-57 3/ 5.E-02 4.E-05 1.E-08 7.E-09
Ni-57 (Vapor) 1.E-08
Ni-59 5.E-02 7.E-04 9.E-09 2.E-08
Ni-59 (Vapor) 4.E-09
Ni-63 5.E-02 3.E-04 4.E-09 6.E-09
Ni-63 (Vapor) 2.E-09
Ni-65 3/ 5.E-02 2.E-04 6.E-08 7.E-08
Ni-65 (Vapor) 4.E-08
Ni-66 5.E-02 1.E-05 4.E-09 1.E-09
Ni-66 (Vapor) 7.E-09
Cu-60 5.E-01 8.E-04 2.E-07 3.E-07 2.E-07
Cu-61 3/ 5.E-01 3.E-04 7.E-08 1.E-07 8.E-08
Cu-64 5.E-01 3.E-04 7.E-08 5.E-08 5.E-08
Cu-67 5.E-01 1.E-04 2.E-08 1.E-08 1.E-08
Zn-62 5.E-01 4.E-05 7.E-09
Zn-63 5.E-01 7.E-04 2.E-07
Zn-65 5.E-01 9.E-06 6.E-10
Zn-69m 5.E-01 1.E-04 2.E-08
Zn-69 5.E-01 2.E-03 3.E-07
Zn-71m 5.E-01 2.E-04 4.E-08
Zn-72 5.E-01 3.E-05 3.E-09
Ga-65 1.E-03 2.E-03 4.E-07 5.E-07
Ga-66 3/ 1.E-03 3.E-05 8.E-09 7.E-09
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Ga-67 1.E-03 2.E-04 3.E-05 2.E-08
Ga-68 3/ 1.E-03 4.E-04 1.E-01 1.E-07
Ga-70 1.E-03 2.E-03 4.E-01 5.E-07
Ga-72 3/ 1.E-03 3.E-05 8.E-09 7.E-09
Ga-73 1.E-03 1.E-04 4.E-08 4.E-08
Ge-66 1.E+00 7.E-04 6.E-08 5.E-05
Ge-67 1.E+00 1.E-03 2.E-07 2.E-07
Ge-68 1.E+00 1.E-04 9.E-09 2.E-10
Ge-69 1.E+00 4.E-04 4.E-05 2.E-08
Ge-71 1.E+00 1.E-02 1.E-06 1.E-07
Ge-75 1.E+00 2.E-03 2.E-07 2.E-07
Ge-77 1.E+00 2.E-04 2.E-05 1.E-08
Ge-78 1.E+00 7.E-04 5.E-08 5.E-08
As-69 5.E-01 1.E-03 3.E-07
As-70 5.E-01 4.E-04 1.E-07
As-71 5.E-01 1.E-04 1.E-08
As-72 5.E-01 2.E-05 3.E-09
As-73 5.E-01 2.E-04 4.E-09
As-74 5.E-01 4.E-05 2.E-09
As-76 5.E-01 3.E-05 4.E-09
As-77 5.E-01 1.E-04 1.E-08
As-78 5.E-01 2.E-04 5.E-08
Se-70 8.E-01 5.E-04 9.E-08 1.E-07
5.E-02 3.E-04
Se-73m 8.E-01 2.E-03 4.E-07 3.E-07
5.E-02 9.E-04
Se-73 3/ 8.E-01 2.E-04 3.E-08 4.E-08
5.E-02 9.E-05
Se-75 8.E-01 2.E-05 2.E-09 1.E-09
5.E-02 8.E-05
Se-79 8.E-01 2.E-05 2.E-09 1.E-09
5.E-02 1.E-04
Se-81m 8.E-01 1.E-03 2.E-07 2.E-07
5.E-02 7.E-04
Se-81 8.E-01 2.E-03 5.E-07 6.E-07
5.E-02 2.E-03
Se-83 8.E-01 1.E-03 3.E-07 3.E-07
5.E-02 9.E-04
Br-74m 1.E+00 6.E-04 9.E-08 1.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Br-74 1.E+00 1.E-03 2.E-07 2.E-07
Br-75 1.E+00 1.E-03 1.E-07 1.E-07
Br-76 1.E+00 1.E-04 1.E-08 1.E-08
Br-77 3/ 1.E+00 4.E-04 6.E-08 5.E-08
Br-80m 1.E+00 6.E-04 4.E-08 3.E-08
Br-80 3/ 1.E+00 2.E-03 4.E-07 5.E-07
Br-82 3/ 1.E+00 8.E-05 1.E-08 9.E-09
Br-83 1.E+00 2.E-03 2.E-07 1.E-07
Br-84 3/ 1.E+00 9.E-04 1.E-07 2.E-07
Rb-79 1.E+00 2.E-03 3.E-07
Rb-81m 1.E+00 1.E-03 8.E-07
Rb-81 3/ 1.E+00 1.E-03 1.E-07
Rb-82m 1.E+00 3.E-04 4.E-08
Rb-83 1.E+00 2.E-05 2.E-09
Rb-84 1.E+00 1.E-05 2.E-09
Rb-86 1.E+00 1.E-05 2.E-09
Rb-87 1.E+00 3.E-05 4.E-09
Rb-88 3/ 1.E+00 8.E-04 1.E-07
Rb-89 3/ 1.E+00 2.E-03 3.E-07
Sr-80 3.E-01 3.E-02 5.E-06
1.E-02 3.E-02 6.E-06
Sr-81 3.E-01 1.E-04 2.E-07
1.E-02 6.E-04 2.E-07
Sr-83 3.E-01 8.E-05 2.E-08
1.E-02 6.E-05 8.E-09
Sr-85m 3/ 3.E-01 6.E-03 1.E-06
1.E-02 6.E-03 2.E-06
Sr-85 3.E-01 7.E-05 6.E-09
1.E-02 1.E-04 4.E-09
Sr-87m 3/ 3.E-01 1.E-03 3.E-07
1.E-02 1.E-03 4.E-07
Sr-89 3.E-01 2.E-05 2.E-09
1.E-02 2.E-05 3.E-10
Sr-90 3.E-01 1.E-06 5.E-11
1.E-02 1.E-05 9.E-12
Sr-91 3.E-01 6.E-05 1.E-08
1.E-02 5.E-05 8.E-09
Sr-92 3/ 3.E-01 9.E-05 2.E-08
1.E-02 7.E-05 2.E-08
Y-86m 1.E-04 6.E-04 1.E-07 1.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Y-86 3/ 1.E-04 3.E-05 8.E-09 7.E-09
Y-87 1.E-04 6.E-05 8.E-09 7.E-09
Y-88 1.E-04 3.E-05 6.E-10 6.E-10
Y-90m 3/ 1.E-04 2.E-04 3.E-08 3.E-08
Y-90 1.E-04 1.E-05 2.E-09 1.E-O9
Y-91m 3/ 1.E-04 4.E-03 6.E-07 4.E-07
Y-91 1.E-04 2.E-05 4.E-10 3.E-10
Y-92 1.E-04 7.E-05 2.E-08 2.E-08
Y-93 1.E-04 3.E-05 7.E-09 6.E-09
Y-94 1.E-04 8.E-04 2.E-07 2.E-07
Y-95 1.E-04 1.E-03 4.E-07 3.E-07
Zr-86 2.E-03 4.E-05 9.E-09 6.E-09 6.E-09
Zr-88 2.E-03 1.E-04 5.E-10 1.E-09 7.E-10
Zr-89 2.E-03 4.E-05 8.E-09 6.E-09 6.E-09
Zr-93 2.E-03 9.E-05 4.E-11 1.E-10 2.E-10
Zr-95 2.E-03 4.E-05 6.E-10 9.E-10 7.E-10
Zr-97 2.E-03 2.E-05 5.E-09 3.E-09 3.E-09
Nb-88 1.E-02 2.E-03 5.E-07 5.E-07
Nb-89 (66 min) 1.E-02 3.E-04 1.E-07 9.E-08
Nb-89 (122min) 1.E-02 1.E-04 4.E-08 4.E-08
Nb-90 1.E-02 3.E-05 6.E-09 6.E-09
Nb-93m 1.E-02 3.E-04 3.E-09 4.E-10
Nb-94 1.E-02 3.E-05 5.E-10 4.E-11
Nb-95m 1.E-02 7.E-05 6.E-09 5.E-09
Nb-95 1.E-02 6.E-05 3.E-09 3.E-09
Nb-96 1.E-02 3.E-05 6.E-09 6.E-09
Nb-97 3/ 1.E-02 6.E-04 2.E-07 2.E-07
Nb-98 1.E-02 4.E-04 1.E-07 1.E-07
Mo-90 8.E-01 1.E-04 2.E-08
5.E-02 6.E-05 1.E-08
Mo-93m 8.E-01 3.E-04 4.E-08
5.E-02 1.E-04 3.E-08
Mo-93 8.E-01 1.E-04 1.E-08
5.E-02 6.E-04 4.E-10
Mo-99 8.E-01 5.E-05 6.E-09
5.E-02 3.E-05 3.E-09
Mo-101 3/ 8.E-01 2.E-03 3.E-07
5.E-02 1.E-03 4.E-07
Tc-93m 8.E-01 2.E-03 4.E-07 7.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Tc-93 8.E-01 8.E-04 2.E-07 2.E-07
Tc-94m 8.E-01 5.E-04 1.E-07 1.E-07
Tc-94 8.E-01 2.E-04 4.E-08 6.E-08
Tc-96m 3/ 8.E-01 4.E-03 7.E-07 6.E-07
Tc-96 8.E-01 5.E-05 7.E-09 5.E-09
Tc-97m 8.E-01 1.E-04 2.E-08 3.E-09
Tc-97 8.E-01 9.E-04 1.E-07 1.E-08
Tc-98 8.E-01 3.E-05 4.E-09 7.E-10
Tc-99m 3/ 8.E-01 2.E-03 4.E-07 6.E-07
Tc-99 8.E-01 1.E-04 1.E-08 2.E-09
Tc-101 3/ 8.E-01 4.E-03 8.E-07 9.E-07
Tc-104 8.E-01 8.E-04 2.E-07 2.E-07
Ru-94 5.E-02 4.E-04 1.E-07 1.E-07 1.E-07
Ru-97 5.E-02 2.E-04 4.E-08 3.E-08 3.E-08
Ru-103 5.E-02 5.E-05 4.E-09 2.E-09 2.E-09
Ru-105 3/ 5.E-02 1.E-04 3.E-08 3.E-08 3.E-08
Ru-106 5.E-02 6.E-06 2.E-10 1.E-10 3.E-11
Rh-99m 5.E-02 5.E-04 1.E-07 2.E-07 2.E-07
Rh-99 5.E-02 7.E-05 7.E-09 5.E-09 5.E-09
Rh-100 5.E-02 4.E-05 1.E-08 9.E-09 9.E-09
Rh-101m 5.E-02 2.E-04 3.E-08 2.E-08 2.E-08
Rh-101 5.E-02 6.E-05 1.E-09 2.E-09 4.E-10
Rh-102m 5.E-02 4.E-05 1.E-09 9.E-10 3.E-10
Rh-102 5.E-02 2.E-05 2.E-10 4.E-10 1.E-10
Rh-103m 5.E-02 1.E-02 3.E-06 3.E-06 3.E-06
Rh-105 5.E-02 1.E-04 3.E-08 1.E-08 1.E-08
Rh-106m 5.E-02 2.E-04 6.E-08 9.E-08 8.E-08
Rh-107 5.E-02 3.E-03 6.E-07 6.E-07 6.E-07
Pd-100 5.E-03 4.E-05 3.E-09 3.E-09 3.E-09
Pd-101 5.E-03 4.E-04 7.E-08 8.E-08 7.E-08
Pd-103 5.E-03 2.E-04 1.E-08 1.E-08 8.E-09
Pd-107 5.E-03 1.E-03 5.E-08 2.E-08 9.E-10
Pd-109 5.E-03 6.E-05 1.E-08 1.E-08 1.E-08
Ag-102 5.E-02 2.E-03 4.E-07 5.E-07 5.E-07
Ag-103 5.E-02 1.E-03 2.E-07 3.E-07 3.E-07
Ag-104m 5.E-02 9.E-04 2.E-07 3.E-07 3.E-07
Ag-104 5.E-02 6.E-04 2.E-07 4.E-07 4.E-07
Ag-105 5.E-02 7.E-05 3.E-09 4.E-09 4.E-09
Ag-106m 5.E-02 2.E-05 2.E-09 2.E-09 2.E-09
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Ag-106 5.E-02 2.E-03 4.E-07 5.E-07 5.E-07
Ag-108m 5.E-02 2.E-05 4.E-10 6.E-10 6.E-11
Ag-110m 5.E-02 1.E-05 3.E-10 4.E-10 2.E-10
Ag-111 5.E-02 3.E-05 4.E-09 2.E-09 2.E-09
Ag-112 5.E-02 9.E-05 2.E-08 2.E-08 2.E-08
Ag-115 5.E-02 9.E-04 2.E-07 2.E-07 2.E-07
Cd-104 5.E-02 6.E-04 2.E-07 3.E-07 3.E-07
Cd-107 5.E-02 6.E-04 1.E-07 1.E-07 1.E-07
Cd-109 5.E-02 1.E-05 1.E-10 3.E-10 3.E-10
Cd-113m 5.E-02 9.E-07 8.E-12 3.E-11 3.E-11
Cd-113 5.E.02 8.E-07 8.E-12 3.E-11 3.E-11
Cd-115m 5.E-02 9.E-06 2.E-10 3.E-10 3.E-10
Cd-115 5.E-02 3.E-05 3.E-09 3.E-09 3.E-09
Cd-117m 3/ 5.E-02 1.E-04 3.E-08 4.E-08 3.E-08
Cd-117 3/ 5.E-02 1.E-04 3.E-08 4.E-08 3.E-08
In-109 2.E-02 5.E-04 1.E-07 2.E-07
In-110 (69min) 2.E-02 4.E-04 1.E-07 1.E-07
In-110 (5 h) 2.E-02 1.E-04 4.E-08 5.E-08
In-111 2.E-02 1.E-04 2.E-08 2.E-08
In-112 2.E-02 6.E-03 1.E-06 2.E-06
In-113m 3/ 2.E-02 1.E-03 3.E-07 5.E-07
In-114m 2.E-02 9.E-06 2.E-10 2.E-10
In-115m 2.E-02 4.E-04 1.E-07 1.E-07
In-115 2.E-02 1.E-06 3.E-12 1.E-11
In-116m 3/ 2.E-02 1.E-04 2.E-07 3.E-07
In-117m 2.E-02 3.E-04 8.E-08 1.E-07
In-117 3/ 2.E-02 2.E-03 4.E-07 5.E-07
In-119m 2.E-02 1.E-03 3.E-07 3.E-07
Sn-110 2.E-02 9.E-05 3.E-08 3.E-08
Sn-111 2.E-02 2.E-03 5.E-07 6.E-07
Sn-113 2.E-02 5.E-05 3.E-09 1.E-09
Sn-117m 2.E-02 5.E-05 5.E-09 3.E-09
Sn-119m 2.E-02 1.E-04 6.E-09 2.E-09
Sn-121m 2.E-02 1.E-04 2.E-09 1.E-09
Sn-121 2.E-02 2.E-04 4.E-08 3.E-08
Sn-123m 2.E-02 1.E-03 3.E-07 3.E-07
Sn-123 2.E-02 2.E-05 1.E-09 4.E-10
$n-125 2.E-02 1.E-05 2.E-09 8.E-10
Sn-126 2.E-02 8.E-06 1.E-10 2.E-10
Sn-127 2.E-02 2.E-04 5.E-08 4.E-08
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Sn-128 2.E-02 3.E-04 6.E-08 9.E-08
Sb-115 1.E-01 2.E-03 6.E-07
1.E-02 2.E-03 7.E-07
Sb-116m 1.E-01 6.E-04 2.E-07
1.E-02 6.E-04 3.E-07
Sb-116 1.E-01 2.E-03 7.E-07
1.E-02 2.E-03 8.E-07
Sb-117 3/ 1.E-01 2.E-03 5.E-07
1.E-02 2.E-03 7.E-07
Sb-118m 1.E-01 2.E-04 5.E-08
1.E-02 1.E-04 5.E-08
Sb-119 1.E-01 4.E-04 1.E-07
1.E-02 4.E-04 6.E-08
Sb-120 (16min) 1.E-01 5.E-03 1.E-06
1.E-02 5.E-03 1.E-06
Sb-120 (6 d) 1.E-01 3.E-05 5.E-09
1.E-02 3.E-05 3.E-09
Sb-122 1.E-01 2.E-05 5.E-09
1.E-02 2.E-05 3.E-09
Sb-124m 1.E-01 7.E-03 2.E-06
1.E-02 7.E-03 1.E-06
Sb-124 1.E-01 2.E-05 2.E-09
1.E-02 1.E-05 6.E-10
Sb-125 1.E-01 6.E-05 6.E-09
1.E-02 5.E-05 1.E-09
Sb-126m 3/ 1.E-01 2.E-03 4.E-07
1.E-02 2.E-03 5.E-07
Sb-126 1.E-01 2.E-05 3.E-09
1.E-02 1.E-05 1.E-09
Sb-127 1.E-01 2.E-05 5.E-09
1.E-02 2.E-05 2.E-09
Sb-128 (9 h) 1.E-01 3.E-05 1.E-08
1.E-02 3.E-05 8.E-09
Sb-128 (10min) 1.E-01 3.E-03 9.E-07
1.E-02 3.E-03 1.E-06
Sb-129/3 1.E-01 5.E-05 2.E-08
1.E-02 8.E-05 2.E-08
Sb-130 1.E-01 5.E-04 1.E-07
1.E-02 5.E-04 2.E-07
Sb-131 1.E-01 5.E-04 9.E-08
1.E-02 5.E-04 1.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Te-116 2.E-01 2.E-04 5.E-08 7.E-08
Te-121m 2.E-01 2.E-05 9.E-10 1.E-09
Te-121 2.E-01 9.E-05 1.E-08 7.E-09
Te-123m 2.E-01 3.E-05 1.E-09 1.E-09
Te-123 2.E-01 3.E-05 1.E-09 3.E-09
Te-125m 2.E-01 4.E-05 2.E-09 2.E-09
Te-127m 2.E-01 2.E-05 1.E-09 6.E-10
Te-127 2.E-01 2.E-04 5.E-08 4.E-08
Te-129m 2.E-01 1.E-05 1.E-09 6.E-10
Te-129 2.E-01 7.E-04 2.E-07 2.E-07
Te-131m 2.E-01 9.E-06 3.E-09 2.E-09
Te-131 2.E-01 7.E-04 1.E-07 1.E-07
Te-132 2.E-01 2.E-05 2.E-09 2.E-09
Te-133m 3/ 2.E-01 2.E-04 3.E-08 3.E-08
Te-133 3/ 2.E-01 9.E-04 1.E-07 1.E-07
Te-134 3/ 2.E-01 7.E-04 1.E-07 1.E-07
I-120m 1.E+00 4.E-04 5.E-08
I-120 1.E+00 2.E-04 3.E-08
I-121 1.E+00 8.E-04 1.E-07
I-123 1.E+00 3.E-04 4.E-08
I-124 1.E+00 4.E-06 6.E-10
I-125 1.E+00 4.E-06 5.E-10
I-126 1.E+00 2.E-06 3.E-10
I-128 3/ 1.E+00 2.E-03 3.E-07
I-129 1.E+00 5.E-07 7.E-11
I-130 1.E+00 3.E-05 5.E-09
I-131 1.E+00 3.E-06 4.E-10
I-132m 1.E+00 3.E-04 5.E-08
I-132 3/ 1.E+00 2.E-04 4.E-08
I-133 1.E+00 1.E-05 2.E-09
I-134 3/ 1.E+00 7.E-04 1.E-07
I-135 3/ 1.E+00 7.E-05 1.E-08
Cs-125 1.E+00 2.E-03 3.E-07
Cs-127 1.E+00 2.E-03 2.E-07
Cs-129 3/ 1.E+00 6.E-04 8.E-08
Cs-130 1.E+00 3.E-03 4.E-07
Cs-131 1.E+00 6.E-04 7.E-08
Cs-132 1.E+00 7.E-05 1.E-08
Cs-134m 1.E+00 3.E-03 3.E-07
Cs-134 1.E+00 2.E-06 2.E-10
Cs-135m 1.E+00 3.E-03 5.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Cs-135 1.E+00 2.E-05 3.E-09
Cs-136 1.E+00 1.E-05 2.E-09
Cs-137 1.E+00 3.E-06 4.E-10
Cs-138 3/ 1.E+00 9.E-04 1.E-07
Ba-126 1.E-01 2.E-04 4.E-08
Ba-128 1.E-01 1.E-05 4.E-09
Ba-131m 1.E-01 1.E-02 3.E-06
Ba-131 1.E-01 8.E-05 2.E-08
Ba-133m 1.E-01 7.E-05 2.E-08
Ba-133 1.E-01 4.E-05 2.E-09
Ba-135m 1.E-01 9.E-05 3.E-05
Ba-139 1.E-01 3.E-04 7.E-08
Ba-140 1.E-01 2.E-05 3.E-09
Ba-141 3/ 1.E-01 7.E-04 2.E-07
Ba-142 3/ 1.E-01 1.E-03 3.E-07
La-131 1.E-03 1.E-03 3.E-07 4.E-07
La-132 1.E-03 9.E-05 2.E-05 3.E-08
La-135 1.E-03 1.E-03 3.E-07 2.E-07
La-137 1.E-03 3.E-04 2.E-10 6.E-10
La-138 1.E-03 2.E-05 8.E-12 3.E-11
La-140 1.E-03 2.E-05 3.E-09 3.E-09
La-141 1.E-03 1.E-04 2.E-08 3.E-08
La-142 1.E-03 2.E-04 5.E-08 8.E-08
La-143 1.E-03 1.E-03 2.E-07 2.E-07
Ce-134 3.E-04 2.E-05 2.E-09 2.E-09
Ce-135 3.E-04 4.E-05 9.E-09 8.E-09
Ce-137m 3.E-04 7.E-05 1.E-08 9.E-09
Ce-137 3.E-04 1.E-03 3.E-07 3.E-07
Ce-139 3.E-04 1.E-04 2.E-09 2.E-09
Ce-141 3.E-04 5.3-05 2.E-09 1.E-09
Ce-143 3.E-04 3.E-05 4.E-09 4.E-09
Ce-144 3.E-04 7.E-06 6.E-11 3.E-11
Pr-136 3.E-04 2.E-03 6.E-07 5.E-07
Pr-137 3.E-04 1.E-03 4.E-07 3.E-07
Pr-138m 3.E-04 3.E-04 1.E-07 1.E-07
Pr-139 3.E-04 1.E-03 3.E-07 3.E-07
Pr-142m 3.E-04 2.E-03 4.E-07 3.E-07
Pr-142 3.E-04 3.E-05 5.E-09 4.E-09
Pr-143 3.E-04 3.E-05 2.E-09 2.E-09
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Pr-144 3.E-04 1.E-03 3.E-07 3.E-07
Pr-145 3.E.04 9.E-05 2.E-08 2.E-08
Pr-147 3.E-04 2.E-03 5.E-07 4.E-07
Nd-136 3.E-04 4.E-04 1.E-07 1.E-07
Nd-138 3.E-04 5.E-05 2.E-08 1.E-08
Nd-139m 3.E-04 1.E-04 4.E-08 3.E-08
Nd-139 3.E-04 2.E-03 8.E-07 7.E-07
Nd-141 3.E-04 4.E-03 2.E-06 1.E-06
Nd-147 3.E-04 4.E-05 2.E-09 2.E-09
Nd-149 3/ 3.E-04 3.E-04 6.E-08 6.E-08
Nd-151 3.E-04 2.E-03 5.E-07 4.E-07
Pm-141 3.E-04 2.E-03 4.E-07 4.E-07
Pm-143 3.E-04 1.E-04 1.E-09 2.E-09
Pm-144 3.E-04 3.E-05 3.E-10 3.E-10
Pm-145 3.E-04 3.E-04 5.E-10 4.E-10
Pm-146 3.E-04 4.E-05 1.E-10 1.E-10
Pm-147 3.E-04 1.E-04 5.E-10 3.E-10
Pm-148m 3.E-04 2.E-05 7.E-10 7.E-10
Pm-148 3.E-04 1.E-05 1.E-09 1.E-09
Pm-149 3.E-04 4.E-05 4.E-08 4.E-09
Pm-150 3.E-04 1.E-04 4.E-08 4.E-08
Pm-151 3.E-04 5.E-05 8.E-09 7.E-09
Sm-141m 3.E-04 8.E-04 2.E-07
Sm-141 3.E-04 2.E-03 4.E-07
Sm-142 3.E-04 2.E-04 6.E-08
Sm-145 3.E-04 2.E-04 1.E-09
Sm-146 3.E-04 7.E-07 2.E-13
Sm-147 3.E-04 8.E-07 2.E-13
Sm-151 3.E-04 4.E-04 4.E-10
Sm-153 3.E-04 5.E-05 7.E-09
Sm-155 3.E-04 2.E-03 5.E-07
Sm-156 3.E-04 1.E-04 2.E-08
Eu-145 1.E-03 4.E-05 5.E.09
Eu-146 1.E-03 3.E-05 3.E-09
Eu-147 1.E-03 8.E-05 4.E-09
Eu-148 1.E-03 3.E-05 8.E-10
Eu-149 1.E-03 3.E-04 7.E-09
Eu-150 (12 h) 1.E-03 9.E-05 2.E-08
Eu-150 (34 yr) 1.E-03 2.E-05 4.E-11
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Eu-152m 1.E-03 7.E-05 2.E-08
Eu-152 1.E-03 2.E-05 5.E-11
Eu-154 1.E-03 2.E-05 5.E-11
Eu-155 1.E-03 1.E-04 3.E-10
Eu-156 1.E-03 2.E-05 1.E-09
Eu-157 1.E-03 6.E-05 1.E-08
Eu-158 1.E-03 5.E-04 1.E-07
Gd-145 3.E-04 1.E-03 4.E-07 4.E-07
Gd-146 3.E-04 4.E-05 3.E-10 7.E-10
Gd-147 3.E-04 5.E-05 1.E-08 8.E-09
Gd-148 3.E-04 7.E-07 4.E-14 1.E-13
Gd-149 3.E-04 8.E-05 5.E-09 6.E-09
Gd-151 3.E-04 2.E-04 1.E-09 3.E-09
Gd-152 3.E-04 9.E-07 5.E-14 2.E-13
Gd-153 3.E-04 1.E-04 6.E-10 1.E-09
Gd-159 3.E-04 7.E-05 2.E-08 1.E-08
Tb-147 3.E-04 2.E-04 7.E-08
Tb-149 3.E-04 1.E-04 2.E-09
Tb-150 3.E-04 1.E-04 5.E-08
Tb-151 3.E-04 1.E-04 2.E-08
Tb-153 3.E-04 1.E-04 2.E-08
Tb-154 3.E-04 5.E-05 1.E-08
Tb-155 3.E-04 2.E-04 2.E-08
Tb-156m (24 h) 3.E-04 2.E-04 2.E-08
Tb-156m (5 h) 3.E-04 4.E-04 6.E-08
Tb-156 3.E-04 3.E-05 3.E-09
Tb-157 3.E-04 1.E-03 1.E-09
Tb-158 3.E-04 3.E-05 5.E-11
Tb-160 3.E-04 2.E-05 5.E-10
Tb-161 3.E-04 5.E-05 4.E-09
Dy-155 3.E-04 2.E-04 6.E-08
Dy-157 3/ 3.E-04 5.E-04 2.E-07
Dy-159 3.E-04 3.E-04 6.E-09
Dy-165 3.E-04 4.E-04 1.E-07
Dy-166 3.E-04 2.E-05 2.E-09
Ho-155 3.E-04 1.E-03 4.E-07
Ho-157 3.E-04 7.E-03 3.E-06
Ho-159 3.E-04 6.E-03 2.E-06
Ho-161 3.E-04 3.E-03 1.E-06
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Ho-162m 3.E-04 2.E-03 6.E-07
Ho-162 3.E-04 2.E-02 6.E-06
Ho-164m 3.E-04 3.E-03 7.E-07
Ho-164 3.E-04 6.E-03 1.E-06
Ho-166m 3.E-04 2.E-05 2.E-11
Ho-166 3.E-04 2.E-05 4.E-09
Ho-167 3.E-04 4.E-04 1.E-07
Er-161 3.E-04 4.E-04 2.E-07
Er-165 3.E-04 2.E-03 4.E-07
Er-169 3.E-04 1.E-04 6.E-09
Er-171 3.E-04 1.E-04 2.E-08
Er-172 3.E-04 4.E-05 3.E-09
Tm-162 3.E-04 2.E-03 7.E-07
Tm-166 3.E-04 1.E-04 3.E-08
Tm-167 3.E-04 7.E-05 5.E-09
Tm-170 3.E-04 3.E-05 5.E-10
Tm-171 3.E-04 4.E-04 1.E-09
Tm-172 3.E-04 2.E-05 3.E-09
Tm-173 3.E-04 1.E-04 3.E-08
Tm-175 3.E-04 3.E-03 6.E-07
Yb-161 3.E-04 2.E-03 7.E-07 7.E-07
Yb-166 3.E-04 4.E-05 5.E-09 4.E-09
Yb-167 3.E-04 8.E-03 2.E-06 2.E-06
Yb-169 3.E-04 5.E-05 2.E-09 2.E-09
Yb-175 3.E-04 9.E-05 8.E-09 8.E-09
Yb-177 3.E-04 4.E-04 1.E-07 1.E-07
Yb-178 3.E-04 4.E-04 1.E-07 9.E-08
Lu-169 3.E-04 7.E-05 1.E-08 1.E-08
Lu-170 3.E-04 3.E-05 5.E-09 5.E-09
Lu-171 3.E-04 5.E-05 4.E-09 5.E-09
Lu-172 3.E-04 3.E-05 3.E-09 3.E-09
Lu-173 3.E-04 1.E-04 1.E-09 6.E-10
Lu-174m 3.E-04 8.E-05 8.E-10 5.E-10
Lu-174 3.E-04 1.E-04 6.E-10 4.E-10
Lu-176m 3.E-04 2.E-04 6.E-08 5.E-08
Lu-176 3.E-04 2.E-05 3.E-11 2.E-11
Lu-177m 3.E-04 2.E-05 3.E-10 2.E-10
Lu-177 3.E-04 7.E-05 5.E-09 5.E-09
Lu-178m 3.E-04 2.E-03 4.E-07 4.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Lu-178 3.E-04 1.E-03 3.E-07 3.E-07
Lu-179 3.E-04 2.E-04 4.E-08 4.E-08
Hf-170 2.E-03 7.E-05 1.E-08 1.E-08
Hf-172 2.E-03 3.E-05 4.E-11 1.E-10
Hf-I73 2.E-03 1.E-04 3.E-08 3.E-08
Hf-175 2.E-03 8.E-05 2.E-09 3.E-09
Hf-177m 2.E-03 5.E-04 1.E-07 2.E-07
Hf-178m 2.E-03 7.E-06 6.E-12 2.E-11
Hf-179m 2.E-03 3.E-05 1.E-09 1.E-09
Hf-180m 2.E-03 2.E-04 5.E-08 6.E-08
Hf-181 2.E-03 3.E-05 9.E-10 1.E-09
Hf-182m 2.E-03 1.E-03 2.E-07 3.E-07
Hf-l82 2.E-03 1.E-05 4.E-12 2.E-11
Hf-183 2.E-03 6.E-04 1.E-07 1.E-07
Hf-184 2.E-03 7.E-05 2.E-08 2.E-08
Ta-172 1.E-03 1.E-03 3.E-07 2.E-07
Ta-173 1.E-03 2.E-04 5.E-08 4.E-08
Ta-174 1.E-03 7.E-04 2.E-07 2.E-07
Ta-175 1.E-03 2.E-04 4.E-08 3.E-08
Ta-176 1.E-03 1.E-04 3.E-08 3.E-08
Ta-177 1.E-03 3.E-04 5.E-08 4.E-08
Ta-178 1.E-03 5.E-04 2.E-07 2.E-07
Ta-179 1.E-03 6.E-04 1.E-08 2.E-09
Ta-180m 1.E-03 6.E-04 2.E-07 1.E-07
Ta-180 1.E-03 4.E-05 1.E-09 6.E-11
Ta-182m 1.E-03 6.E-03 1.E-06 1.E-06
Ta-182 1.E-03 2.E-05 7.E-10 3.E-10
Ta-183 1.E-03 3.E-05 3.E-09 2.E-09
Ta-184 1.E-03 5.E-05 1.E-08 1.E-08
Ta-185 1.E-03 7.E-04 2.E-07 2.E-07
Ta-186 1.E-03 2.E-03 5.E-07 5.E-07
W-176 1.E-02 3.E-04
3.E-01 4.E-04 1.E-07
W-177 1.E-02 6.E-04
3.E-01 7.E-04 2.E-07
W-178 1.E-02 1.E-04
3.E-01 2.E-04 5.E-08
W-179 1.E-02 2.E-02
3.E-01 2.E-02 4.E-06
W-181 1.E-02 4.E-04
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
W-181 3.E-01 5.E-04 8.E-08
W-185 1.E-02 7.E-05
3.E-01 1.E-04 2.E-08
W-187 1.E-02 5.E-02
3.E-01 7.E-05 2.E-08
W-188 1.E-02 2.E-05
3.E-01 2.E-05 3.E-09
Re-177 8.E-01 3.E-03 6.E-07 8.E-07
Re-178 8.E-01 3.E-03 6.E-07 7.E-07
Re-181 8.E-01 1.E-04 2.E-08 2.E-08
Re-182 (64 h) 8.E-01 4.E-05 6.E-09 5.E-09
Re-182 (12 h) 8.E-01 2.E-04 3.E-08 4.E-08
3/
Re-184m 8.E-01 6.E-05 7.E-09 1.E-09
Re-184 8.E-01 6.E-05 8.E-09 3.E-09
Re-186m 8.E-01 4.E-05 5.E-09 4.E-10
Re-186 8.E-01 5.E-05 7.E-09 4.E-09
Re-187 8.E-01 2.E-02 2.E-06 2.E-07
Re-188m 8.E-01 2.E-03 3.E-07 3.E-07
Re-188 8.E-01 5.E-05 7.E-09 6.E-09
Re-189 8.E-01 9.E-05 1.E-08 1.E-08
Os-180 1.E-02 3.E-03 9.E-07 1.E-06 1.E-06
Os-181 1.E-02 4.E-04 1.E-07 1.E-07 1.E-07
Os-182 1.E-02 6.E-05 1.E-08 1.E-08 9.E-09
Os-185 1.E-02 7.E-05 1.E-09 2.E-09 2.E-09
Os-189m 1.E-02 2.E-03 2.E-07 5.E-07 4.E-07
Os-191m 1.E-02 4.f-04 7.E-08 5.E-08 4.E-08
Os-191 1.E-02 7.E-05 5.E-09 4.E-09 3.E-09
Os-193 1.E-02 4.E-05 1.E-08 7.E-09 6.E-09
Os-194 1.E-02 2.E-05 1.E-10 1.E-10 2.E-11
Ir-182 1.E-02 1.E-03 3.E-07 4.E-07 3.E-07
Ir-184 1.E-02 2.E-04 6.E-08 7.E-08 6.E-08
Ir-185 1.E-02 1.E-04 3.E-08 3.E-08 2.E-08
Ir-186 1.E-02 6.E-05 2.E-08 1.E-08 1.E-08
Ir-187 1.E-02 3.E-04 7.R-08 7.E-08 6.E-08
Ir-188 1.E-02 5.E-05 1.E-08 8.E-09 8.E-09
Ir-189 1.E-02 1.E-04 1.E-08 9.E-09 9.E-09
Ir-190m 3/ 1.E-02 5.E-03 5.E-07 5.E-07 5.E-07
Ir-190 1.E-02 3.E-05 2.E-09 2.E-09 2.E-09
Ir-192m 1.E-02 9.E-05 2.E-10 2.E-10 4.E-11
Ir-192 1.E-02 3.E-05 6.E-10 9.E-10 5.E-10
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Ir-194m 1.E-02 2.E-05 2.E-10 4.E-10 2.E-10
Ir-194 1.E-02 3.E-05 7.E-09 5.E-09 4.E-09
Ir-195m 1.E-02 2.E-04 6.f-08 7.E-08 5.E-05
Ir-195 1.E-02 4.E-04 1.E-07 1.E-07 1.E-07
Pt-186 1.E-02 4.E-04 9.E-08
Pt-188 1.E-02 4.E-05 4.E-09
Pt-189 1.E-02 3.E-04 7.E-08
Pt-191 1.E-02 1.E-04 2.E-08
Pt-193m 1.E-02 8.E-05 1.E-08
Pt-193 1.E-02 1.E-03 6.E-08
Pt-195m 1.E-02 6.E-05 1.E-08
Pt-197m 1.E-02 4.E-04 1.E-07
Pt-197 1.E-02 9.E-05 2.E-08
Pt-199 1.E-02 1.E-03 3.E-07
Pt-200 1.E-02 3.E-05 8.E-09
Au-193 1.E-01 2.E-04 3.E-08 4.E-08 4.E-08
Au-194 1.E-01 7.E-05 9.E-09 3.E-09 1.E-08
Au-195 1.E-01 1.E-04 1.E-08 3.E-09 1.E-09
Au-198m 1.E-01 2.E-05 3.E-09 2.E-09 2.E-09
Au-198 1.E-01 6.E-05 4.E-09 6.E-09 7.E-09
Au-199 1.E-01 8.E-05 8.E-09 8.E-09 8.E-09
Au-200m 1.E-01 3.E-05 4.E-09 5.E-09 6.E-09
Au-200 1.E-01 7.E-04 9.E-08 1.E-07 2.E-07
Au-201 1.E-01 2.E-03 3.E-07 5.E-07 5.E-07
Hg-193m (Org) 1.E+00 3.E-04 3.E-08
4.E-01 1.E-04
Hg-193m 2.E-02 9.E-05 2.E-08 2.E-08
Hg-193m (Vapor) 2.E-08
Hg-193 (Org) 1.E+00 1.E-03 2.E-07
4.E-01 5.E-04
Hg-193 2.E-02 4.E-04 1.E-07 1.E-07
Hg-193 (Vapor) 7.E-08
Hg-194 (Org) 1.E+00 5.E-07 7.E-11
4.E-01 1.E-06
Hg-194 2.E-02 2.E-05 1.E-10 3.E-10
Hg-194 (Vapor) 7.E-11
Hg-195m (Org) 1.E+00 1.E-04 1.E-08
4.E-01 8.E-05
Hg-195m 2.E-02 6.E-05 1.E-08 9.E-09
Hg-195m (Vapor) 9.E-09
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Hg-195 (Org) 1.E+00 1.E-03 1.E-07
4.E-01 5.E-04
Hg-195 2.E-02 4.E-04 8.E-08 8.E-08
Hg-195 (Vapor) 7.E-08
Hg-197m (Org) 1.E+00 2.E-04 2.E-08
4.E-01 1.E-04
Hg-197m 2.E-02 8.E-05 2.E-08 1.E-08
Hg-197m (Vapor) 1.f-08
kg-197 (Org) 1.E+00 3.E-04 3.E-08
4.E-01 2.E-04
Hg-197 2.E-02 1.E-04 3.E-08 2.E-08
Hg-197 (Vapor) 2.E-07
Hg-199m (Org) 1.E+00 3.E-03 4.E-07
4.E-01 2.E-03
Hg-199m 2.E-02 2.E-03 4.E-07 4.E-07
Hg-199m (Vapor) 2.E-07
Hg-203 (Org) 1.E+00 1.E-05 2.E-09
4.E-01 2.E-05
Hg-203 2.E-02 7.E-05 3.E-09 3.E-09
Hg-203 (Vapor) 2.E-09
Tl-194m 1.E+00 2.E-03 4.E-07
Tl-194 1.E+00 7.E-03 1.E-06
Tl-195 1.E+00 2.E-03 3.E-07
Tl-197 1.E+00 2.E-03 3.E-07
Tl-198m 1.E+00 8.E-04 1.E-07
Tl-198 1.E+00 5.E-04 7.E-08
Tl-199 1.E+00 2.E-03 2.E-07
Tl-200 3/ 1.E+00 2.E-04 3.E-08
Tl-201 1.E+00 5.E-04 5.E-08
Tl-202 1.E+00 9.E-05 1.E-08
Tl-204 1.E+00 4.E-05 5.E-09
Pb-195m 2.E-01 2.E-03 5.E-07
Pb-198 2.E-01 9.E-04 2.E-07
Pb-199 2.E-01 6.E-04 2.E-07
Pb-200 2.E-01 9.E-05 1.E-08
Pb-201 2.E-01 2.E-04 5.E-08
Pb-202m 2.E-01 2.E-04 7.E-08
Pb-202 2.E-01 4.E-06 1.E-10
Pb-203 2.E-01 1.E-04 2.E-08
Pb-205 2.E-01 9.E-05 3.E-09
Pb-209 2.E-01 7.E-04 1.E-07
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Pb-210 2.E-01 3.E-08 9.E-13
Pb-211 2.E-01 3.E-04 1.E-09
Pb-212 2.E-01 3.E-06 8.E-11
Pb-214 2.E-01 2.E-04 2.E-09
Bi-200 5.E-02 8.E-04 2.E-07 2.E-07
Bi-201 5.E-02 3.E-04 7.E-08 9.E-08
Bi-202 5.E-02 4.E-04 1.E-07 2.E-07
Bi-203 5.E-02 7.E-05 2.E-08 1.E-08
Bi-205 5.E-02 4.E-05 6.E-09 3.E-09
Bi-206 5.E-02 2.E-05 3.E-09 2.E-09
Bi-207 5.E-02 3.E-05 4.E-09 8.E-10
Bi-210m 5.E-02 2.E-06 1.E-11 2.E-12
Bi-210 5.E-02 2.E-05 9.E-10 6.E-11
Bi-211 5.E-02 1.E-04 6.E-10 7.E-10
Bi-213 5.E-02 2.E-04 7.E-10 8.E-10
Bi-214 5.E-02 6.E-04 2.E-09 2.E-09
Po-203 1.E-01 7.E-04 2.E-07 2.E-07
Po-205 1.E-01 6.E-04 9.E-08 2.E-07
Po-207 1.E-01 2.E-04 6.E-08 7.E-08
Po-210 1.E-01 8.E-08 1.E-12 1.E-12
At-207 1.E+00 2.E-04 6.E-09 5.E-09
At-211 1.E+00 3.E-06 2.E-10 1.E-10
Rn-210 4/ 4/ 4/ 4/
Rn-211 5/ 5/ 5/ 5/
Fr-222 1.E+00 6.E-05 1.E-09
Fr-223 1.E+00 2.E-05 2.E-09
Ra-223 2.E-01 3.E-07 2.E-12
Ra-224 2.E-01 4.E-07 4.E-12
Ra-225 2.E-01 4.E-07 2.E-12
Ra-226 2.E-01 1.E-07 1.E-12
Ra-227 2.E-01 6.E-04 4.E-08
Ra-228 2.E-01 1.E-07 3.E-12
Ac-224 1.E-03 5.E-05 9.E-11 1.E-10 1.E-10
Ac-225 1.E-03 1.E-06 1.E-12 2.E-12 1.E-12
Ac-226 1.E-03 3.E-06 9.E-12 1.E-11 1.E-11
Ac-227 1.E-03 1.E-08 2.E-15 7.E-15 1.E-14
Ac-228 1.E-03 6.E-05 4.E-11 1.E-10 1.E-10
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Th-226 2.E-04 1.E-04 4.E-10 3.E-10
Th-227 2.E-04 4.E-06 8.E-13 7.E-13
Th-228 2.E-04 4.E-07 5.E-14 4.E-14
Th-229 2.E-04 4.E-08 6.E-15 7.E-15
Th-230 2.E-04 3.E-07 4.E-14 5.E-14
Th-231 2.E-04 1.E-04 1.E-08 2.E-08
Th-232 2.E-04 5.E-08 7.E-15 1.E-14
Th-234 2.E-04 1.E-05 5.E-10 4.E-10
Th-Natural 2.E-04 5.E-08 7.E-15 1.E-14
Pa-227 1.E-03 1.E-04 3.E-10 2.E-10
Pa-228 1.E-03 3.E-05 5.E-11 3.E-11
Pa-230 1.E-03 2.E-05 1.E-11 8.E-12
Pa-231 1.E-03 1.E-08 9.E-15 1.E-14
Pa-232 1.E-03 4.E-05 1.E-10 2.E-10
Pa-233 1.E-03 4.E-05 2.E-09 1.E-09
Pa-234 3/ 1.E-03 7.E-05 2.E-08 2.E-08
U-230 5.E-02 2.E-07 1.E-12 8.E-13
2.E-03 1.E-06 6.E-13
U-231 5.E-02 1.E-04 2.E-08 1.E-08
2.E-03 1.E-04 1.E-08
U-232 5.E-02 1.E-07 1.E-12 9.E-33
2.E-03 2.E-06 2.E-04
U-233 5.E-02 5.E-07 4.E-12 2.E-12
2.E-03 5.E-06 9.E-14
U-234 5.E-02 5.E-07 4.E-12 2.E-12
2.E-03 5.E-06 9.E-14
U-235 5.E-02 6.E-07 5.E-12 2.E-12
2.E-03 5.E-06 1.E-13
U-236 5.E-02 5.E-07 5.E-12 2.E-12
2.E-03 6.E-06 1.E-13
U-237 5.E-02 5.E-05 6.E-09 4.E-09
2.E-03 5.E-05 4.E-09
U-238 5.E-02 6.E-07 5.E-12 2.E-12
2.E-03 6.E-06 1.E-13
U-239 3/ 5.E-02 2.E-03 4.E-07 4.E-07
2.E-03 2.E-03 4.E-07
U-240 5.E-02 3.E-05 9.E-09 7.E-09
2.E-03 3.E-05 6.E-09
U-Natural 5.E-02 6.E-07 5.E-12 2.E-12
2.E-03 6.E-06 1.E-13
Np-232 1.E-03 6/ 6.E-03 7/ 1.E-08 8/
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Np-233 1.E-03 6/ 2.E-02 7/ 8.E-06 8/
Np-234 1.E-03 6/ 8.E-05 7/ 6.E-09 8/
Np-235 1.E-03 6/ 6.E-04 7/ 3.E-09 8/
Np-236 (1.E+05 1.E-03 6/ 2.E-07 7/ 1.E-13 8/
yr)
Np-236 (22 h) 1.E-03 6/ 1.E-04 7/ 2.E-10 8/
Np-237 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Np-238 1.E-03 6/ 4.E-05 7/ 4.E-10 8/
Np-239 1.E-03 6/ 5.E-05 7/ 5.E-09 8/
Np-240 3/ 1.E-03 6/ 7.E-04 7/ 2.E-07 8/
Pu-234 1.E-03 6/ 1.E-04 7/ 5.E-10 8/
1.E-05 6/ 2.E-04 7/ 4.E-10/8/
Pu-235 1.E-03 6/ 1.E-02 7/ 7.E-06 8/
1.E-05 6/ 2.E-02 7/ 6.E-06 8/
Pu-236 1.E-03 6/ 1.E-07 7/ 8.E-14 8/
1.E-05 6/ 5.E-06 7/ 9.E-14 8/
Pu-237 1.E-03 6/ 1.E-04 7/ 8.E-09 8/
1.E-05 6/ 3.E-04 7/ 7.E-09 8/
Pu-238 1.E-03 6/ 4.E-08 7/ 3.E-14 8/
1.E-05 6/ 3.E-06 7/ 4.E-14 8/
Pu-239 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
1.E-05 6/ 2.E-06 7/ 4.E-14 8/
Pu-240 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
1.E-05 6/ 2.E-06 7/ 4.E-14 8/
Pu-241 1.E-03 6/ 2.E-06 7/ 1.E-12 8/
1.E-05 6/ 1.E-04 7/ 2.E-12 8/
Pu-242 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
1.E-05 6/ 2.E-06 7/ 4.E-14 8/
Pu-243 1.E-03 6/ 4.E-04 7/ 8.E-14 8/
1.E-05 6/ 4.E-04 7/ 9.E-08 8/
Pu-244 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
1.E-05 6/ 2.E-06 7/ 4.E-14 8/
1.E-03 6/ 6.E-05 7/ 1.E-08 8/
Pu-245 1.E-05 6/ 6.E-05 7/ 1.E-08 8/
Am-237 1.E-03 6/ 2.E-03 7/ 7.E-07 8/
Am-238 1.E-03 6/ 8.E-04 7/ 1.E-08 8/
Am-239 1.E-03 6/ 1.E-04 7/ 3.E-08 8/
Am-240 1.E-03 6/ 5.E-05 7/ 6.E-09 8/
Am-241 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Am-242m 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Am-242 1.E-03 6/ 1.E-04 7/ 2.E-10 8/
Am-243 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Am-244m 1.E-03 6/ 2.E-03 7/ 1.E-08 8/
Am-244 1.E-03 6/ 7.E-05 7/ 7.E-10 8/
Am-245 1.E-03 6/ 8.E-04 7/ 2.E-07 8/
Am-246m 1.E-03 6/ 2.E-03 7/ 4.E-07 8/
Am-246 3/ 1.E-03 6/ 9.E-04 7/ 2.E-07 8/
Cm-238 1.E-03 6/ 4.E-04 7/ 3.E-09 8/
Cm-240 1.E-03 6/ 2.E-06 7/ 1.E-12 8/
Cm-241 1.E-03 6/ 3.E-05 7/ 7.E-11 8/
Cm-242 1.E-03 6/ 1.E-06 7/ 7.E-13 8/
Cm-243 1.E-03 6/ 5.E-08 7/ 3.E-14 8/
Cm-244 1.E-03 6/ 6.E-08 7/ 4.E-14 8/
Cm-245 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Cm-246 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Cm-247 1.E-03 6/ 3.E-08 7/ 2.E-14 8/
Cm-248 1.E-03 6/ 8.E-09 7/ 6.E-15 8/
Cm-249 1.E-03 6/ 1.E-03 7/ 5.E-08 8/
Bk-245 5.E-04 6.E-05 3.E-09
Bk-246 5.E-04 7.E-05 7.E-09
Bk-247 5.E-04 6.E-08 2.E-14
Bk-249 5.E-04 2.E-05 9.E-12
Bk-250 5.E-04 3.E-04 2.E-09
Cf-244 1.E-03 6/ 9.E-04 7/ 1.E-09 8/ 1.E-09 8/
Cf-246 1.E-03 6/ 1.E-05 7/ 2.E-11 8/ 2.E-11 8/
Cf-248 1.E-03 6/ 5.E-07 7/ 3.E-13 8/ 3.E-13 8/
Cf-249 1.E-03 6/ 3.E-08 7/ 2.E-14 8/ 3.E-14 8/
Cf-250 1.E-03 6/ 7.E-08 7/ 5.E-14 8/ 6.E-14 8/
Cf-251 1.E-03 6/ 3.E-08 7/ 2.E-14 8/ 3.E-14 8/
Cf-252 1.E-03 6/ 1.E-07 7/ 1.E-13 8/ 9.E-14 8/
Cf-253 1.E-03 6/ 1.E-05 7/ 5.E-12 8/ 4.E-12 8/
Cf-254 5.E-04 6/ 5.E-08 7/ 5.E-14 8/ 4.E-14 8/
Es-250 5.E-04 1.E-03 3.E-09
Es-251 5.E-04 2.E-04 3.E-09
Es-253 5.E-04 6.E-06 4.E-12
Es-254m 5.E-04 9.E-06 3.E-11
Es-254 5.E-04 9.E-07 3.E-13
Fm-252 5.E-04 1.E-05 3.E-11
Fm-253 5.E-04 4.E-05 2.E-11
Fm-254 5.E-04 8.E-05 2.E-10
Figure III-1 (contd)
Ingested Inhaled Air DCG (uCi/mL)
f 1/ Water DCG -----------------------------
Radionuclide Value (uCi/mL) D W Y
------------ ----- --------- --------- --------- ---------
Fm-255 5.E-04 1.E-05 5.E-11
Fm-257 5.E-04 2.E-06 6.E-13
Md-257 5.E-04 3.E-04 2.E-10
Md-258 5.E-04 2.E-06 8.E-13
---------------
1/ A dash indicates no values given for this data category.
2/ The inhalation DCG 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 lung dose
equivalent is used as the basis for the DCG value shown.
3/ For the radionuclide shown, the DCG for external exposure from immersion
in a contaminated plume (listed in figure III-2) is more restrictive.
4/ DCGs for Rn-220 are being assessed by DOE. Until the review has been
completed and new values issued, the value of 3.E-09 micro Ci/mL given
in figure III-3 shall be used.
5/ DCGs for Rn-222 are being assessed by DOE. Until the review has been
completed and new values issued, the value of 3.E-09 micro Ci/mL given
in Figure III-3 shall be used for Rn-222 releases from DOE facilities.
In addition, the requirements of Chapter IV, Sections 4b, 6b, and 6d,
shall be used when they are applicable.
6/ ICRP Publication No. 48: "The Metabolism of Plutonium and Related
Elements."
7/ Based on the listed f1 value. It is assumed that individual organ
doses, except for the gastrointestinal tract, change in proportion to f1
for all organs, including the "Remainder." Gastrointestinal doses are
unchanged because very little material is absorbed in the upper portions
of the tract.
8/ It is assumed that the effective dose equivalents 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).
Figure III-1 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ -----------------
Actinium/ 89 Oxides, hydroxides 1.E-03 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, 1.E-01 D
Sb halides, 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; dependent
At 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, 5.E-03 Y
Be nitrates
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; dependent
Br upon associated
element
Figure III-2
Alternative Absorption factors and Lung Retention Classes
for Specific Compounds
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention 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 (11 C) 1.E-02 W
Organic (14 C) 7.E-05 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
Cl 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, 5.E-02 Y
Co halides, nitrates
All others 5.E-01 W
Ingestion only 3.E-01
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ -----------------
Copper/ 29 Oxides, hydroxides 5.E-01 Y
Cu Sulphites, halides, 5.E-01 W
nitrates
All others 5.E-01 D
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;
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, 1.E+00 W
Ge halides
All others 1.E+00 D
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention 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, 1.E-03 W
Hf halides, carbides,
nitrates
All others 1.E-03 D
Holmium/ 67 All Forms 3.E-04 W
Ho
Hydrogen/ 1 Water (3H) 1.E+00
H
Indium/ 49 Oxides, hydroxides, 2.E-02 W
In halides
All others 2.E-02 D
Iodine/ 53 All forms 1.E+00 D
I
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, 1.E-01 W
Fe halides
All others 1.E-01 D
Lanthanum/ 57 Oxides, hydroxides 1.E-03 W
La All others 1.E-03 D
Lead/ 81 All forms 2.E-01 D
Pb
Lutetium/ 71 Oxides, hydroxides, 3.E-04 Y
Lu fluorides
All others 3.E-04 W
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ -----------------
Magnesium/ 12 Oxides, hydroxides, 5.E-01 W
Mg carbides, halides,
nitrates
All others 5.E-01 D
Manganese/ 25 Oxides, hydroxides, 1.E-01 W
Mn halides, nitrates
All others 1.E-01 D
Mendelevium/ 101 All forms 5.E-04 W
Md
Mercury/ 80 Oxides, hydroxides, 2.E-02 W
Hg halides, nitrates,
sulphites
Sulphates, 2.E-02 D
elemental form
Organic Forms 1.E+00 D
Vapor D
Molybdenum/ 42 Oxides, hydroxides, 5.E-02 Y
Mo MoS2
All others 8.E-01 D
Ingestion 2/
MoS2 5.E-02
All others 8.E-01
Neodymium/ 60 Oxides, hydroxides, 3.E-04 Y
Nd carbides, fluorides
All others 3.E-04 W
Neptunium/ 93 All forms 1.E-03 W
Np
Nickel/ 28 Oxides, hydroxides 5.E-01 W
Ni All others (vapor) D
Niobium/ 41 Oxides, hydroxides 1.E-02 Y
Nb All others 1.E-02 W
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ -----------------
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
Phosphorus/ 15 Phosphates 8.E-01 W or D; dependent
P upon associated
element
Platinum/ 78 All forms 1.E-02 D
Pt
Plutonium/ 94 Oxides, hydroxides 1.E-05 Y
Pu Nitrates W
All others 1.E-04 W
[Note: Use same 1.E-03
values for
ingestion]
Polonium/ 84 Oxides, hydroxides, 1.E-01 W
Po nitrates
All others 1.E-01 D
Potassium/ 19 All forms 1.E+00 D
K
Praesodymium/ 59 Oxides, hydroxides, 3.E-04 Y
Pr carbides, fluorides
All others 3.E-04 W
Promethlum/ 61 Oxides, hydroxides, 3.E-04 Y
Pm carbides, fluorides
All others 3.E-04 W
Protactinium/ 91 Oxides, hydroxides 1.E-03
Pa All others 1.E-03 W
Radium/ 88 All forms 2.E-01 W
Ra
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention 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, 8.E-01 W
Se carbides
All others 8.E-01 D
Ingestion only 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, 5.E-02 D
elemental form
Sodium/ 11 All Forms 1.E+00 D
Na
Strontium/ 38 SrTiO3 1.E-02 Y
Sr All others 3.E-01 D
(soluble)
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ -----------------
Sulfur/ 16 Sulphates, 1.E-01 W or D; dependent
S sulphides upon associated
element
All inorganic 8.E-01
Elemental form 1.E-01 W
Gases 1.E+00 D
Tantalum/ 73 Oxides, hydroxides, 1.E-03 Y
Ta halides, 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, 2.E-01 W
Te nitrates
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/ 50 Oxides, hydroxides, 2.E-02 W
Sn halides, 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
Figure III-2 (contd)
Element/ Atomic Lung
Symbol Number Compound f 1/ Retention Class
-------------- --------- ------------------- ------------ ---------------
Tungsten/ 74 Ingestion 2/
W Tungstic acid 1.E-02
All others 3.E-01
Uranium/ 92 UO2, U3O8 2.E-03 Y
U UO3, tetravalent 5.E-02 W
compounds
UF6, uranyl 5.E-02 D
compounds
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
Zr Oxides, hydroxides, 2.E-03 W
halides, nitrates
All others 2.E-03 D
----------------
1/ A dash indicates no data For the value shown.
2/ For ingestion, no lung retention classes are listed.
Figure III-2 (contd)
Air Immersion
Radionuclide Half-Life DCG (microCi/mL)
------------ --------- ----------------
C-11 20.48 min 2.E-08
N-13 9.97 min 2.E-08
N-16 7.13 s 3.E-09
O-15 122.24 s 2.E-08
F-18 1/ 109.74 min 2.E-08
Na-24 1/ 15.00 h 4.E-09
Mg-27 2/ 9.458 min 2.E-08
Al-28 2/ 2.240 min 1.E-08
Cl-38 1/ 37.21 min 1.E-08
Ar-37 35.02 d 1.E-02
Ar-39 269 yr 4.E-06 3/
Ar-41 1.827 h 1.E-08
K-43 1/ 22.6 h 2.E-08
Ca-49 2/ 8.719 min 5.E-09
Sc-44 1/ 3.927 h 9.E-09
Sc-46m 2/ 18.72 s 2.E-07
Ti-45 1/ 3.08 h 2.E-08
Ti-51 2/ 5.752 min 5.E-08
V-52 2/ 3.75 min 1.E-08
Cr-49 1/ 42.09 min 2.E-08
Mn-52m 1/ 21.4 min 8.E-09
Mn-56 1/ 2.5785 h 1.E-08
Mn-57 2/ 1.47 min 2.E-07
Co-60m 1/ 10.47 min 4.E-06
Ni-57 1/,/4 36.08 h 1.E-08
Figure III-3
Derived Concentration Guides (DCGs) For Members of the Public from
External Exposure During Immersion in a Contaminated Atmospheric Cloud
Air Immersion
Radionuclide Half-Life DCG (microCi/mL)
------------ --------- ----------------
Ni-65 1/, 5/ 2.520 h 3.E-08
Cu-61 1/ 3.408 h 2.E-08
Cu-62 2/ 9.74 min 2.E-08
Ga-66 1/ 9.40 h 7.E-09
Ga-68 1/ 68.0 min 2.E-08
Ga-72 1/ 14.1 h 7.E-09
Se-73 1/ 7.15 h 2.E-08
Br-77 1/ 57.04 h 6.E-08 6/
Br-80 1/ 17.4 min 2.E-07
Br-82 1/ 35.30 h 7.E-09
Br-84 1/ 31.80 min 1.E-08
Br-85 2/ 172 s 2.E-07
Kr-79 35.04 h 8.E-08
Kr-81 2.1E+05 yr 2.E-06
Kr-83m 1.83 h 2.E-04
Kr-85 10.72 yr 3.E-O6 3/
Kr-85m 4.48 h 1.E-07
Kr-87 76.3 min 2.E-08
Kr-88 2.84 h 9.E-09
Kr-89 3.16 min 1.E-08
Kr-90 32.32 s 1.E-08
Rb-81 1/ 4.58 h 3.E-08
Rb-82 2/ 1.25 min 2.E-08
Rb-88 1/ 17.8 min 3.E-08
Rb-89 1/ 15.44 min 9.E-09
Rb-90 2/ 157 s 8.E-09
Rb-90m 2/ 258 s 5.E-09
Sr-85m 1/ 67.66 min 9.E-08
Sr-87m 1/ 2.805 h 6.E-08
Sr-92 1/ 2.71 h 1.E-08
Sr-93 2/ 7.3 min 8.E-09
Y-86 1/ 14.74 h 5.E-09
Y-90m 1/ 3.19 h 3.E-08 6/
Y-91m 1/ 49.71 min 4.E-08
Nb-90 1/ 14.60 h 4.E-09
Figure III-3 (contd)
Air Immersion
Radionuclide Half-Life DCG (microCi/mL)
------------ --------- ----------------
Nb-94m 2/ 6.26 min 4.E-06
Nb-97 1/ 72.1 min 3.E-08
Nb-97m 1/ 60 s 3.E-08
Mo-91 2/ 15.49 min 2.E-08
Mo-101 1/ 14.61 min 1.E-08
Tc-95 1/ 20.0 h 2.E-08
Tc-96m 1/ 51.5 min 5.E-07
Tc-99m 1/ 6.02 h 1.E-07
Tc-101 1/ 14.2 min 6.E-08
Ru-105 1/ 4.44 h 2.E-08
Rh-105m 2/ 45 s 7.E-07
Rh-106 2/ 29.92 s 8.E-08
Ag-108 2/ 2.37 min 7.E-07
Ag-109m 2/ 39.6 s 4.E-06
Ag-110 2/ 24.57 s 4.E-07
Cd-111m 2/ 48.7 min 7.E-08
Cd-117 1/ 2.49 h 2.E-08
Cd-117m 1/ 3.36 h 9.E-09
In-113m 1/ 1.658 h 8.E-08
In-114 2/ 71.9 s 5.E-07
In-116m 1/ 54.15 min 8.E-09
In-117 1/ 43.8 min 3.E-08
Sb-117 1/ 2.80 h 1.E-07
Sb-126m 1/ 19.0 min 1.E-08
Sb-129 1/ 4.40 h 1.E-08
Te-133 1/ 12.45 min 2.E-08
Te-133m 1/ 55.4 min 8.E-09
Te-134 1/ 41.8 min 2.E-08
I-122 2/ 3.62 min 2.E-08
I-128 1/ 24.99 min 2.E-07
I-132 1/ 2.30 h 8.E-09
I-134 1/ 52.6 min 7.E-09
I-I35 1/ 6.61 h 1.E-08 6/
I-136 2/ 83 s 7.E-09
Figure III-3 (contd)
Air Immersion
Radionuclide Half-Life DCG (microCi/mL)
------------ --------- ----------------
Xe-122 20.1 h 3.E-07
Xe-123 2.14 h 3.E-08
Xe-125 16.8 h 8.E-08
Xe-127 36.406 d 7.E-08
Xe-129m 8.89 d 8.E-07
Xe-131m 11.84 d 2.E-06
Xe-133 5.245 d 5.E-07
Xe-133m 2.19 d 6.E-07
Xe-135 9.11 h 8.E-08
Xe-135m 15.36 min 5.E-08
Xe-137 3.83 min 9.E-08
Xe-138 14.13 min 2.E-08
Cs-126 2/ 1.64 min 2.E-08
Cs-129 1/ 32.06 h 8.E-08 6/
Cs-138 1/ 32.2 min 8.E-09
Cs-139 2/ 9.40 min 5.E-08
Ba-137m 2/ 2.552 min 3.E-08
Ba-141 1/ 18.27 min 2.E-08
Ba-142 1/ 10.70 min 2.E-08
La-142 1/ 95.4 min 6.E-09
Pr-144m 2/ 7.2 min 4.E-06
Nd-149 1/ 1.73 h 5.E-08
Gd-162 2/ 9.7 min 5.E-08
Td-162 2/ 7.76 min 2.E-08
Dy-157 1/ 8.06 h 6.E-08
Re-182m 1/ 12.7 h 2.E-08
Os-190m 1/ 9.9 min 1.E-08
Ir-190m 1/ 3.2 h 5.E-07 6/
Au-195m 2/ 30.6 s 1.E-07
Figure III-3 (contd)
Air Immersion
Radionuclide Half-Life DCG (microCi/mL)
------------ --------- ----------------
Tl-200 1/ 26.1 h 1.E-08
Tl-207 2/ 4.77 min 1.E-06 3/
Tl-208 2/ 3.053 min 5.E-09
Tl-209 2/ 2.20 min 9.E-09
Tl-210 2/ 1.30 min 7.E-09
Pb-204m 2/ 66.9 min 9.E-09
Bi-211 2/ 2.13 min 4.E-07
Po-211 2/ 0.516 s 2.E-06
Rn-220 7/ 55.61 s 3.E-09
Rn-222 7/ 3.82 d 3.E-09
Th-233 2/ 22.3 min 5.E-07
Pa-234 1/ 6.70 h 1.E-08
Pa-234m 2/ 1.17 min 8.E-07 3/
U-239 1/ 23.40 min 4.E-07 6/
Np-240 1/ 65 min 2.E-08
Np-240m 2/ 7.4 min 6.E-08
Am-246 1/ 25.0 min 2.E-08
----------------------
1/ Committed effective dose equivalent from inhalation is calculated in
ICRP Publication 30, but the DCG value for external exposure to a
contaminated atmospheric cloud is more restrictive than the DCG value
for inhalation.
2/ Committed effective dose equivalent from inhalation is not calculated in
ICRP Publication 30, but DCG value for external exposure to contaminated
cloud should be more restrictive than DCG value for inhalation due to
relatively short half-life of radionuclide.
3/ DCG value is determined by limit on annual dose equivalent to skin,
rather than limit on annual effective dose equivalent.
4/ DCG value applies to radionuclide in vapor form only; DCG value for
inhalation is more restrictive for radionuclide in inorganic form.
5/ DCG value applies to radionuclide in inorganic or vapor form.
6/ DCG value for exposure to contaminated atmospheric cloud is the same as
DCG value for inhalation.
7/ The value shown for radon gas is a result of unit conversion from 3
pCi/L to 3 microCi/mL.
Figure III-3 (contd)
CHAPTER IV
RESIDUAL RADIOACTIVE MATERIAL
1. PURPOSE. This chapter presents radiological protection requirements
and guidelines for cleanup of residual radioactive material and
management of the resulting wastes and residues and release of property.
These requirements and guidelines are applicable at the time the
property is released. Property subject to these criteria includes, but
is not limited to sites identified by the Formerly Utilized Sites
Remedial Action Program (FUSRAP) and the Surplus Facilities Management
Program (SFMP). The topics covered are basic dose limits, guidelines
and authorized limits for allowable levels of residual radioactive
material, and control of the radioactive wastes and residues. This
chapter does not apply to uranium mill tailings or to properties covered
by mandatory legal requirements.
2. IMPLEMENTATION. DOE elements shall develop plans and protocols for the
implementation of this guidance. FUSRAP sites shall be identified,
characterized, and designated, as such, for remedial action and
certified for release. Information on applications of the guidelines
and requirements presented herein, including procedures for deriving
specific property guidelines for allowable levels of residual
radioactive material from basic dose limits, is contained in DOE/CH
8901, "A Manual for Implementing Residual Radioactive Material
Guidelines, A Supplement to the U.S. Department of Energy Guidelines
for Residual Radioactive Material at FUSRAP and SFMP Sites," June 1989.
a. Residual Radioactive Material. This chapter provides guidance on
radiation protection of the public and the environment from:
(1) Residual concentrations of radionuclides in soil (for these
purposes, soil is defined as unconsolidated earth material,
including rubble and debris that might be present in earth
material);
(2) Concentrations of airborne radon decay products;
(3) External gamma radiation;
(4) Surface contamination; and
(5) Radionuclide concentrations in air or water resulting from or
associated with any of the above.
b. Basic Dose Limit. The basic dose limit for doses resulting from
exposures to residual radioactive material is a prescribed standard
from which limits for quantities that can be monitored and
controlled are derived; it is specified in terms of the effective
dose equivalent as defined in this Order. The basic dose limits are
used for deriving guidelines for residual concentrations of
radionuclides in soil. Guidelines for residual concentrations of
thorium and radium in soil, concentrations of airborne radon decay
products, allowable indoor external gamma radiation levels, and
residual surface contamination concentrations are based on existing
radiological protection standards (40 CFR Part 192; NRC Regulatory
Guide 1.86 and subsequent NRC guidance on residual radioactive
material). Derived guidelines or limits based on the basic dose
limits for those quantities are used only when the guidelines
provided in the existing standards are shown to be inappropriate.
c. Guideline. A guideline for residual radioactive material is a level
of radioactive material that is acceptable for use of property
without restrictions due to residual radioactive material.
Guidelines for residual radioactive material presented herein are of
two kinds, generic and specific. The basis for the guidelines is
generally a presumed worst-case plausible-use scenario for the
property.
(1) Generic guidelines, independent of the property, are taken
from existing radiation protection standards. Generic
guideline values are presented in this chapter.
(2) Specific property guidelines are derived from basic dose
limits using specific property models and data. Procedures
and data for deriving specific property guideline values are
given by DOE/CH-8901.
d. Authorized Limit. An authorized limit is a level of residual
radioactive material that shall not be exceeded if the remedial
action is to be considered completed and the property is to be
released without restrictions on use due to residual radioactive
material.
(1) The authorized limits for a property will include:
(a) Limits for each radionuclide or group of radionuclides,
as appropriate, associated with residual radioactive
material in soil or in surface contamination of structures
and equipment;
(b) Limits for each radionuclide or group of radionuclides,
as appropriate, in air or water; and
(c) Where appropriate, a limit on external gamma radiation
resulting from the residual material.
(2) Under normal circumstances expected at most properties,
authorized limits for residual radioactive material are set
equal to, or below, guideline values. Exceptional conditions
for which authorized limits might differ from guideline
values are specified in paragraphs IV-5 and IV-7.
(3) A property may be released without restrictions if residual
radioactive material does not exceed the authorized limits or
approved supplemental limits, as defined in paragraph IV.7a,
at the time remedial action is completed. DOE actions in
regard to restrictions and controls on use of the property
shall be governed by provisions in paragraph IV.7b. The
applicable controls and restrictions are specified in
paragraph IV.6 and IV.7.c.
e. ALARA Applications. The monitoring, cleanup, and control of
residual radioactive material are subject to the ALARA policy of
this Order. Applications of ALARA policy shall be documented and
filed as a permanent record.
3. BASIC DOSE LIMITS.
a. Defining and Determining Dose Limits. The basic public dose limits
for exposure to residual radioactive material, in addition to
natural occurring "background" exposures, are 100 mrem (1 mSv)
effective dose equivalent in a year, as specified in paragraph
II.1a.
b. Unusual Circumstances. If, under unusual circumstances, it is
impracticable to meet the basic limit based on realistic exposure
scenarios, the respective project and/or program office may,
pursuant to paragraph II.1a(4), request from EH-1 for a specific
authorization for a temporary dose limit higher than 100 mrem (1
mSv), but not greater than 500 mrem (5 mSv), in a year. Such
unusual circumstances may include temporary conditions at a
property scheduled for remedial action or following the remedial
action. The ALARA process shall apply to the selection of
temporary dose limits.
4. GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL.
a. Residual Radionuclides in Soil. Generic guidelines for thorium
and radium are specified below. Guidelines for residual
concentrations of other radionuclides shall be derived from the
basic dose limits by means of an environmental pathway analysis
using specific property data where available. Procedures for
these derivations are given in DOE/CH-8901. Residual concentrations
of radioactive material in soil are defined as those in excess of
background concentrations averaged over an area of 100 m2.
(1) Hot Spots. If the average concentration in any surface or
below-surface area less than or equal to 25 m2, exceeds the
limit or guideline by a factor of (100/A)0.5, [where A is the
area (in square meters) of the region in which concentrations
are elevated], limits for "hot-spots" shall also be developed
and applied. Procedures for calculating these hot-spot
limits, which depend on the extent of the elevated local
concentrations, are given in DOE/CH-8901. In addition,
reasonable efforts shall be made to remove any source of
radionuclide that exceeds 30 times the appropriate limit for
soil, irrespective of the average concentration in the soil.
(2) Generic Guidelines. The generic guidelines for residual
concentrations of Ra-226, Ra-228, Th-230, and Th-232 are:
(a) 5 pCi/g, averaged over the first 15 cm of soil below the
surface; and
(b) 15 pCi/g, averaged over 15-cm-thick layers of soil more
than 15 cm below the surface.
(3) Ingrowth and Mixtures. These guidelines take into account
ingrowth of Ra-226 from Th-230 and of Ra-228 from Th-232, and
assume secular equilibrium. If both Th-230 and Ra-226 or
both Th-232 and Ra-228 are present and not in secular
equilibrium, the appropriate guideline is applied as a limit
for the radionuclide with the higher concentration. If other
mixtures of radionuclides occur, the concentrations of
individual radionuclides shall be reduced so that either the
dose for the mixtures will not exceed the basic dose limit or
the sum of the ratios of the soil concentration of each
radionuclide to the allowable limit for that radionuclide
will not exceed 1. Explicit formulas for calculating
residual concentration guidelines for mixtures are given in
DOE/CH-8901.
b. Airborne Radon Decay Products. Generic guidelines for
concentrations of airborne radon decay products shall apply to
existing occupied or habitable structures on private property that
are intended for release without restriction; structures that will
be demolished or buried are excluded. The applicable generic
guideline (40 CFR Part 192) is: In any occupied or habitable
building, the objective of remedial action shall be, and a
reasonable effort shall be made to achieve, an annual average (or
equivalent) radon decay product concentration (including background)
not to exceed 0.02 WL. [A working level (WL) is any combination of
short-lived radon decay products in 1 L of air that will result in
the ultimate emission of 1.3 x 10 5 MeV of potential alpha energy.]
In any case, the radon decay product concentration (including
background) shall not exceed 0.03 WL. Remedial actions by DOE are
not required in order to comply with this guideline when there is
reasonable assurance that residual radioactive material is not the
source of the radon concentration.
c. External Gamma Radiation. The average level of gamma radiation
inside a building or habitable structure on a site to be released
without restrictions shall not exceed the background level by more
than 20 micro R/h and shall comply with the basic dose limit when
an "appropriate-use" scenario is considered. This requirement
shall not necessarily apply to structures scheduled for demolition
or to buried foundations. External gamma radiation levels on open
lands shall also comply with the basic limit and the ALARA process,
considering appropriate-use scenarios for the area.
d. Surface Contamination. The generic surface contamination guidelines
provided in Figure IV-1 are applicable to existing structures and
equipment. These guidelines are generally consistent with standards
of the NRC (NRC 1982) and functionally equivalent to Section 4,
"Decontamination for Release for Unrestricted Use," of Regulatory
Guide 1.86, but apply to nonreactor facilities. These limits apply
to both interior equipment and building components that are
potentially salvageable or recoverable scrap. If a building is
demolished, the guidelines in paragraph IV.6a are applicable to the
resulting contamination in the ground.
e. Residual Radionuclides in Air and Water. Residual concentrations
of radionuclides in air and water shall be controlled to the
required levels shown in paragraph II.1a and as required by other
applicable Federal and/or State laws.
5. AUTHORIZED LIMITS FOR RESIDUAL RADIOACTIVE MATERIAL.
a. Establishment of Authorized Limits. The authorized limits for each
property shall be set equal to the generic or derived guidelines
unless it can be established, on the basis of specific property data
(including health, safety, practical, programmatic and socioeconomic
considerations), that the guidelines are not appropriate for use at
the specific property. The authorized limits shall be established
to (1) provide that, at a minimum, the basic dose limits of in
paragraph IV.3, will not be exceeded under the "worst-case" or
"plausible-use" scenarios, consistent with the procedures and
guidance provided in DOE/CH-8901, or (2) be consistent with
applicable generic guidelines. The authorized limits shall be
consistent with limits and guidelines established by other
applicable Federal and State laws. The authorized limits are
developed through the project offices in the field and are approved
by the Headquarters Program Office.
----------------------------------------------------------------------------
Allowable Total Residual Surface Contamination
(dpm/100 cm2) 1/
Radionuclides 2/ Average 3/,4/ Maximum 4/,5/ Removable 4/,6/
------------- ------- ------- ---------
Transuranics, I-125, I-129, RESERVED RESERVED RESERVED
Ra-226, Ac-227, Ra-228,
Th-228, Th-230, Pa-231.
Th-Natural, Sr-90, I-126, 1,000 3,000 200
I-131, I-133, Ra-223,
Ra-224, U-232, Th-232.
U-Natural, U-235, U-238, 5,000 15,000 1,000
and associated decay
product, alpha emitters.
Beta-gamma emitters 5,000 15,000 1,000
(radionuclides with decay
modes other than alpha
emission or spontaneous
fission) except Sr-90 and
others noted above. 7/
---------------------------
1/ 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 measured by an appropriate detector for background,
efficiency, and geometric factors associated with the instrumentation.
2/ Where surface contamination by both alpha- and beta-gamma-emitting
radionuclides exists, the limits established for alpha- and
beta-gamma-emitting radionuclides should apply independently.
3/ Measurements of average contamination should not be averaged over an
area of more than 1 m2. For objects of less surface area, the average
should be derived for each such object.
4/ The average and maximum dose rates associated with surface contamination
resulting from beta-gamma emitters should not exceed 0.2 mrad/h and 1.0
mrad/h, respectively, at 1 cm.
5/ The maximum contamination level applies to an area of not more than 100
cm2.
6/ The amount of removable material per 100 cm2 of surface area should be
determined by wiping an area of that size with dry filter or soft
absorbent paper, applying moderate pressure, and measuring the amount
of radioactive material on the wiping with an appropriate instrument of
known efficiency. When removable contamination on objects of surface
area less than 100 cm2 is determined, the activity per unit area should
be based on the actual area and the entire surface should be wiped. 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.
7/ 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.
----------------------------------------------------------------------------
Figure IV-1
Surface Contamination Guidelines
b. Application of Authorized Limits. Remedial action shall not be
considered complete until the residual radioactive material levels
comply with the authorized limits, except as authorized pursuant
to paragraph IV.7 for special situations where the supplemental
limits and exceptions should be considered and it is demonstrated
that it is not appropriate to decontaminate the area to the
authorized limit or guideline value.
6. CONTROL OF RESIDUAL RADIOACTIVE MATERIAL. Residual radioactive
material above the guidelines shall be managed in accordance with
Chapter II and the following requirements.
a. Operational and Control Requirements. The operational and control
requirements specified in the following Orders shall apply to
interim storage, interim management, and long-term management.
(1) DOE 5000.3B, Occurrence Reporting and Processing of Operations
Information
(2) DOE 5440.1E, National Environmental Policy Act Compliance
Program
(3) DOE 5480.4, Environmental Protection, Safety, and Health
Protection Standards
(4) DOE 5482.1B, Environmental, Safety, and Health Appraisal
Program
(5) DOE 5483.1A, Occupational Safety and Health Program for DOE
Employees at Government-Owned, Contractor-Operated Facilities
(6) DOE 5484.1, Environmental Protection, Safety, and Health
Protection Information Reporting Requirements
(7) DOE 5820.2A, Radioactive Waste Management.
b. Interim Storage.
(1) Control and stabilization features shall be designed to
provide, to the extent reasonably achievable, an effective
life of 50 years with a minimum life of at least 25 years.
(2) Controls shall be designed such that Rn-222 concentrations in
the atmosphere above facility surfaces or openings in
addition to background levels, will not exceed:
(a) 100 pCi/L at any given point;
(b) An annual average concentration of 30 pCi/L over the
facility site; and
(c) An annual average concentration of 3 pCi/L at or above
any location outside the facility site.
(d) Flux rates from the storage of radon producing wastes
shall not exceed 20 pCi/sq.m-sec., as required by 40 CFR
Part 61.
(3) Controls shall be designed such that concentrations of
radionuclides in the groundwater and quantities of residual
radioactive material will not exceed applicable Federal or
State standards.
(4) Access to a property and use of onsite material contaminated
by residual radioactive material should be controlled through
appropriate administrative and physical controls such as
those described in 40 CFR Part 192. These control features
should be designed to provide, to the extent reasonable, an
effective life of at least 25 years.
c. Interim Management.
(1) A property may be maintained under an interim management
arrangement when the residual radioactive material exceeds
guideline values if the residual radioactive material is in
inaccessible locations and would be unreasonably costly to
remove provided that administrative controls are established
by the responsible authority (Federal, State, or local) to
protect members of the public and that such controls are
approved by the appropriate Program Secretarial Officer.
(2) The administrative controls include but are not limited to
periodic monitoring as appropriate; appropriate shielding;
physical barriers to prevent access; and appropriate
radiological safety measures during maintenance, renovation,
demolition, or other activities that might disturb the
residual radioactive material or cause it to migrate.
(3) The owner of the property should be responsible for
implementing the administrative controls and the cognizant
Federal, State, or local authorities should be responsible
for enforcing them.
d. Long-Term Management.
(1) Uranium, Thorium, and Their Decay Products.
(a) Control and stabilization features shall be designed to
provide, to the extent reasonably achievable, an effective
life of 1,000 years with a minimum life of at least 200
years.
(b) Control and stabilization features shall be designed to
limit Rn-222 emanation to the atmosphere from the wastes
to less than an annual average release rate of 20
pCi/m2/s and prevent increases in the annual average
Rn-222 concentration at or above any location outside
the boundary of the contaminated area by more than 0.5
pCi/L. Field verification of emanation rates shall be
in accordance with the requirements of 40 CFR Part 61.
(c) Before any potentially biodegradable contaminated wastes
are placed in a long-term management facility, such
wastes shall be properly conditioned so that the
generation and escape of biogenic gases will not cause
the requirement in paragraph IV.6d(1)(b) to be exceeded
and that biodegradation within the facility will not
result in premature structural failure in violation of
the requirements in paragraph IV.6d(1)(a).
(d) Ground water shall be protected in accordance with
legally applicable Federal and State standards.
(e) Access to a property and use of onsite material
contaminated by residual radioactive material should be
controlled through appropriate administrative and
physical controls such as those described in 40 CFR Part
192. These controls should be designed to be effective
to the extent reasonable for at least 200 years.
(2) Other Radionuclides. Long-term management of other
radionuclides shall be in accordance with Chapters II, III,
and IV of DOE 5820.2A, as applicable.
7. SUPPLEMENTAL LIMITS AND EXCEPTIONS. If special specific property
circumstances indicate that the guidelines or authorized limits
established for a given property are not appropriate for any portion of
that property, then the DOE Field Office Manager may request, through
the Program Office, that supplemental limits or an exception be applied.
The responsible DOE Field Office Manager shall document the decision
that the subject guidelines or authorized limits are not appropriate and
that the alternative action selected will provide adequate protection,
giving due consideration to health and safety, the environment, costs,
and public policy considerations. The DOE Field Office Manager shall
obtain approval for specific supplemental limits or exceptions from
Headquarters as specified in paragraph IV.5, and shall provide to the
Headquarters Program Office those materials required by Headquarters for
the justification as specified in this paragraph and in the FUSRAP and
SFMP protocols and subsequent guidance documents. The DOE Field Office
Manager shall also be responsible for coordination with the State and
local government regarding the limits or exceptions and associated
restrictions as appropriate. In the case of exceptions, the DOE Field
Office Manager shall be responsible for coordinating with the State
and/or local governments to ensure the adequacy of restrictions or
conditions of release and that mechanisms are in place for their
enforcement.
a. Supplemental Limits. Any supplemental limits shall achieve the
basic dose limits set forth in Chapter II of this Order for both
current and potential unrestricted uses of a property. Supplemental
limits may be applied to any portion of a property if, on the basis
of a specific property analysis, it is demonstrated that
(1) Certain aspects of the property were not considered in the
development of the established authorized limits for that
property; and
(2) As a result of these certain aspects, the established limits
either do not provide adequate protection or are unnecessarily
restrictive and costly.
b. Exceptions to the authorized limits defined for a property may be
applied to any portion of the property when it is established that
the authorized limits cannot reasonably be achieved and that
restrictions on use of the property are necessary. It shall be
demonstrated that the exception is justified and that the
restrictions will protect members of the public within the basic
dose limits of this Order and will comply with the requirements
for control of residual radioactive material as set forth in
paragraph IV.6.
c. Justification for Supplemental Limits and Exceptions. The need for
supplemental limits and exceptions shall be documented by the DOE
Field Office on a case-by-case basis using specific property data.
Every reasonable effort should be made to minimize the use of
supplemental limits and exceptions. Examples of specific situations
that warrant DOE use of supplemental standards and exceptions are:
(1) Where remedial action would pose a clear and present risk of
injury to workers or members of the public, notwithstanding
reasonable measures to avoid or reduce risk.
(2) Where remedial action, even after all reasonable mitigative
measures have been taken, would produce environmental harm
that is clearly excessive compared to the health benefits to
persons living on or near affected properties, now or in the
future. A clear excess of environmental harm is harm that is
long-term, manifest, and grossly disproportionate to health
benefits that may reasonably be anticipated.
(3) Where it is determined that the scenarios or assumptions used
to establish the authorized limits do not apply to the property
or portion of the property identified, or where more
appropriate scenarios or assumptions indicate that other limits
are applicable or appropriate for protection of the public and
the environment.
(4) Where the cost of remedial action for contaminated soil is
unreasonably high relative to long-term benefits and where
the residual material does not pose a clear present or future
risk after taking necessary control measure. The likelihood
that buildings will be erected or that people will spend long
periods of time at such a property should be considered in
evaluating this risk. Remedial action will generally not be
necessary where only minor quantities of residual radioactive
material are involved or where residual radioactive material
occurs in an inaccessible location at which specific property
factors limit its hazard and from which it is difficult or
costly to remove. Examples include residual radioactive
material under hard-surfaced public roads and sidewalks,
around public sewer lines, or in fence-post foundations. A
specific property analysis shall be provided to establish
that the residual radioactive material would not cause an
individual to receive a radiation dose in excess of the basic
dose limits stated in paragraph IV.3, and a statement
specifying the level of residual radioactive material shall
be provided to the appropriate State and/or local agencies
for appropriate action, e.g., for inclusion in local land
records.
(5) Where there is no feasible remedial action.
8. SOURCES.
a. Basic Dose Limits. Dosimetry model and dose limits are defined in
Chapter II of this Order.
b. Generic Guidelines for Residual Radioactive Material. Residual
concentrations of radium and thorium in soil are defined in 40 CFR
Part 192. Airborne radon decay products are also defined in 40
CFR Part 192, as are guidelines for external gamma radiation. The
surface contamination definition is adapted from NRC (1982).
c. Control of Radioactive Wastes and Residues. Interim storage is
guided by this Order and DOE 5820.2A. Long-term management is
guided by this Order, 40 CFR Part 192, and DOE 5820.2A.
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