ASTM E1760-96
(Guide)Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
SCOPE
1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D∧and;D) from restricted use. It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Figure 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as "candidate for release based on dose."
1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects.
1.3 Surface contaminated objects are materials externally contaminated with radioactive material. Provisions already exist for their release for recycle if it can be shown that they meet applicable federal and state regulations for surface contamination. Regulatory Guide 1.86 and DOE Order 5400.5 specify the upper limits for radioactive surface contamination on material to be released for unrestricted use.
1.4 The release of material containing residual radioactive material (except for 226 Ra) in bulk form (for example, soil or slightly activated metal) is based on the demonstration that the dose to a member of the public will be lower than a specified value (proposed by the petitioner or to be determined by future regulation) for its intended use and lower than a second specified value (also proposed by the petitioner or to be determined by future regulation) via the most restrictive plausible scenario. The first proposed value should be lower than the second since the dose to any member of the public (via the intended use scenario) will almost certainly be realized, whereas the dose from the alternate scenario will only accrue if an unintended (and presumably less probable) circumstance arises. Federal regulation already exists for the release of 226 Ra contaminated soils.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: E 1760 – 96
Standard Guide for
Unrestricted Disposition of Bulk Materials Containing
Residual Amounts of Radioactivity
This standard is issued under the fixed designation E 1760; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
The feasibility of the recycle of bulk material containing trace amounts of radioactive contamination
depends on the dose to the public that could occur as a result. However, the assessment of this dose
depends not only on the measurements of contaminants present, but also on the future use of the
material and the pathways by which persons can be exposed. This guide provides a recommended
approach to support a petition (to a regulatory agency) seeking approval for the recycle or disposal of
the material outside of the radioactive materials regulatory arena.
If dose rate limits are established by regulation, this approach is a recommended way to demonstrate
compliance with them. Until that occurs, the limits will have to be proposed by the owners that
advance the argument that recycle should be permitted because the dose is very small.
The Scope defines the range of applicability of this guide; the Summary identifies the two major
steps that comprise the method; and the significance of the guide is given in Section 5. Section 6
discusses the need for dose rate based release criteria, and Section 7 delineates the steps for deciding
whether or not a material should be considered for recycle. Section 8 describes the steps needed to
implement the recommendations of this guide including the development of a data package to support
the petition and to serve as a permanent record.
1. Scope contamination. Regulatory Guide 1.86 and DOE Order 5400.5
specify the upper limits for radioactive surface contamination
1.1 This guide covers the techniques for obtaining approval
on material to be released for unrestricted use.
for release of materials encountered in decontamination and
1.4 The release of material containing residual radioactive
decommissioning (D&D) from restricted use. It applies to
material (except for Ra) in bulk form (for example, soil or
materials that do not meet any of the requirements for
slightly activated metal) is based on the demonstration that the
regulatory control because of radioactivity content. Fig. 1
dose to a member of the public will be lower than a specified
shows the logic diagram for determining the materials that
value (proposed by the petitioner or to be determined by future
could be considered for release. Materials that negotiate this
regulation) for its intended use and lower than a second
logic tree are referred to as “candidate for release based on
specified value (also proposed by the petitioner or to be
dose.”
determined by future regulation) via the most restrictive
1.2 The objective of this guide is to provide a methodology
plausible scenario. The first proposed value should be lower
for distinguishing between material that must be carefully
than the second since the dose to any member of the public (via
isolated to prevent human contact from that that can be
the intended use scenario) will almost certainly be realized,
recycled or otherwise disposed of. It applies to material in
whereas the dose from the alternate scenario will only accrue
which the radioactivity is dispersed more or less uniformly
if an unintended (and presumably less probable) circumstance
throughout the volume of the material (termed residual in bulk
arises. Federal regulation already exists for the release of Ra
form) as opposed to surface contaminated objects.
contaminated soils.
1.3 Surface contaminated objects are materials externally
1.5 This standard does not purport to address all of the
contaminated with radioactive material. Provisions already
safety concerns, if any, associated with its use. It is the
exist for their release for recycle if it can be shown that they
responsibility of the user of this standard to establish appro-
meet applicable federal and state regulations for surface
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use.
This guide is under the jurisdiction of ASTM Committee E-10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
2. Referenced Documents
E10.03on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
2.1 ASTM Standards:
Current edition approved Jan. 10, 1996. Published March 1996.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
E 1760
2.6 U.S. Government Documents:
40 CFR 192, Health and Environmental Protection Stan-
dards for Uranium and Thorium Mill Tailings
10 CFR 60, Disposal of High-Level Radioactive Wastes in
Geological Repositories
10 CFR 61, Licensing Requirements for Land Disposal of
Radioactive Waste
40 CFR 117, Determination of Reportable Quantities for
Hazardous Substances
40 CFR 261, Identification and Listing of Hazardous Waste
40 CFR 268, Land Disposal Restrictions
40 CFR 712, Chemical Information Rules
40 CFR 716, Health and Safety Data Reporting
3. Terminology
3.1 Definitions of Terms Specific to This Standard:
3.1.1 credible, adj—offering reasonable grounds for being
believed.
3.1.2 intended use, n—the first use planned for the material
proposed to be released from radiological controls.
3.1.3 primary dose limit, n—the limit for exposures that
could occur via the intended use scenario.
3.1.4 secondary dose limit, n—the limit for exposure that
could occur via the unplanned use scenario.
3.1.5 unplanned use, n—any use other than the planned use
that may occur after the intended use or by accident.
4. Summary of Guide
4.1 The owner of the material must first determine if the
material is candidate for release. To do this one must take
representative samples of the bulk material and identify the
FIG. 1 Prerequisites for Material To Be Candidate For Release
radioactive contaminants and concentrations. Sampling should
be done using standard statistical inspection methods. The
E 1278 Guide for Radioactive Pathway Methodology for
kinds of analyses shall be appropriate for the potential con-
Release of Sites Following Decommissioning
taminant expected, and performed using standard techniques.
2.2 American Nuclear Insurers Document: 3 14
For some of these analyses, for example, Hor C in activated
ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-
concrete or Fe in steel, the standard techniques are beyond
ity Insurance Records Retention
the capabilities of many laboratories. Material that passes the
2.3 DOE Document:
logic diagram shown in Fig. 1 is candidate for release. The
DOE Order 5400.5, Radiation Protection of the Public and
sampling, analysis, and determination of candidacy must be
the Environment
documented and included in the record package.
Regulatory Guide 1.86, Termination of Operating Licenses
4.2 Fig. 2 diagrammatically shows how a material that is
for Nuclear Reactors
candidate for release should be treated to justify its release
2.4 International Atomic Energy Agency Document:
from radiologically restricted use. Section 7 describes the
Safety Series No. 111-P-1.1, Application of Exemption
methodology shown.
Principles to the Recycle and Reuse of Materials from
Nuclear Facilities 5. Significance and Use
2.5 Nuclear Regulatory Commission Document:
5.1 Materials encountered during D&D may contain re-
NUREG/CR-5512, Residual Radioactive Contamination
sidual radioactivity varying in amounts from that in irradiated
from Decommissioning
fuel to barely detectable quantities in or on building materials.
It is clear that highly radioactive materials have to be disposed
as radioactive waste pursuant to 10 CFR 60 and 10 CFR 61.
Annual Book of ASTM Standards, Vol 12.02.
Conversely, it is not reasonable to expend a disproportionate
Available from American Nuclear Insurers, 29 South Main, Suite 300 S, West
amount of resources to isolate materials that contain minute
Hartford, CT 06107-2445.
quantities of radioactive materials that will not cause even
Available from Department of Energy, National Technical Information Service,
U.S. Dept. of Commerce, Springfield, VA 22161.
statistically measurable health effects.
International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100,
5.2 This guide provides a rationale and methodology for
A-1400 Vienna, Austria.
distinguishing between materials that contain sufficient radio-
Available from the Superintendent of Documents, U.S. Government Printing
Office, Washington, DC 20402. activity to warrant isolation of some type (storage awaiting
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
E 1760
5.4 This guide also asserts that the owner of the materials is
responsible for ensuring that society’s criteria for “no measur-
able health effects” is met before release, and that the respon-
sibility for providing materials with the purity required for a
special application rests not with the owner, but with the
developer of that application.
6. Criteria for Unrestricted Release
6.1 There are three criteria for the release of bulk materials
that are candidates for release (that is, that have negotiated the
logic diagram shown in Fig. 1). First, the material must not be
expected to cause more than the intended use dose limit when
used for the intended purpose. Second, the material must not be
expected to cause more than the unplanned use dose limit when
used for the most restrictive credible unplanned purpose.
Finally, the materials must maneuver the procedural gates
described in this guide sucessfully.
7. Candidate Materials for Unrestricted Release
7.1 There are two groups of materials encountered in
decontamination and decommissioning that are likely to be
candidates for release for unrestricted use. The first group
includes basic building materials that were used originally in
the construction of a nuclear facility but were not exposed to
significant amounts of activating radiation or radioactive con-
tamination. The second group is materials that were contami-
nated but have been subjected to a decontamination treatment.
Some types of building material from both groups that could be
cost effectively released are described in 7.1.1-7.1.6.
7.1.1 Miscellaneous and structural steel that is not intended
for use “as is” (on the basis of surface contamination) would be
smelted. Contaminant levels in the melt would be minimized
by avoiding the selection of steel from highly contaminated
FIG. 2 Methodology for Approving Candidate Material for
areas or surface cleaning the steel before smelting. In addition,
Unrestricted Release
the slagging process also generally reduces the concentration
of contaminants in the melt. If the metal ingot met the release
decay, near-surface disposal, disposal with intruder protection,
criteria given in this guide it would not have to be disposed of
or placement in a deep repository) from materials with insig-
as radioactive waste. At worst it would be disposed of in a
nificant radioactive content. Materials with insignificant radio-
sanitary landfill. Preferably it would be recycled.
active content can be recycled in the economy or disposed of
7.1.2 Asbestos insulation is a porous bulk material that is
in conventional (landfill) facilities without adverse health
not amenable to surface surveys. Economical decontamination
effects. Materials that meet the criteria identified in this guide
methods for asbestos insulation have not been demonstrated.
are not simply excluded from regulation because they do not
Ordinarily, most of the asbestos in a facility is not contami-
fall precisely in the regulatory scope. They are sufficiently free
nated or is very slightly contaminated, but cannot be shown to
of radioactive material so that no further efforts at control are
be absolutely free of radioactivity. Asbestos could be disposed
justified for radiation protection purposes. Therefore, the re-
of in a permitted landfill instead of a licensed radioactive
lease of materials for unrestricted use in accordance with this
materials disposal site if shown to meet the release criteria
guide meets the criteria for being an “as low as reasonably
given in this guide.
achievable” (ALARA) activity.
7.1.3 Miscellaneous building materials such as wood, non-
5.3 For the purpose of this guide, the return of materials
containing residual radioactivity to society without regulatory asbestos insulation, built-up roofing, and sheet rock are not
amenable to surface survey for release. Although these mate-
restrictions is referred to as “unrestricted release based on the
absence of the credible potential for adverse health effects.” rials are not ordinarily useful for recycle they could be
disposed of in a sanitary landfill rather than at a licensed
This guide asserts that materials recycled this way will have no
statistically measurable health effects regardless of use. It does disposal facility if they met the release criteria described in this
guide.
not guarantee that the materials are suitable for use in every
possible application, for example, trace amounts of radionu- 7.1.4 Granular materials such as soil, concrete, or masonry
clides in materials may not be acceptable for certain photo- rubble cannot be surveyed against surface criteria. However,
graphic and electronic applications. they could be disposed of in a sanitary landfill or used as clean
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
E 1760
fill if shown to meet the release criteria recommended in this 8.1.4 Compute the annual dose to the receptor by way of the
guide. identified scenario. NUREG/CR-5512 gives examples of such
7.1.5 Neutron-activated material has radioactivity distrib- calculations. Additional guidance is given in IAEA’s “Appli-
uted within the solid mass because of the neutron transmutation cation of Exemption Principles to the Recycle and Reuse of
of atoms within the material itself. Surface measuremen
...
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