ASTM E1760-96(2003)e1

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 (DD) from restricted use. It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. 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  226Ra) 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 probably) circumstance arises. Federal regulation already exists for the release of 226Ra contaminated soils

General Information

• Status: Historical
• Publication Date: 09-Jan-1996
• ICS: 13.030.40 - Installations and equipment for waste disposal and treatment
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components

Relations

• Replaces: ASTM E1760-96(2003) - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 10-Jan-1996
• Replaced By: ASTM E1760-09 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Jun-2009
• Referred By: ASTM E2216-02(2020) - Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
• Effective Date: 10-Jan-1996
• Referred By: ASTM E1281-15(2021) - Standard Guide for Nuclear Facility Decommissioning Plans
• Effective Date: 10-Jan-1996

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
e1
Designation:E1760–96 (Reapproved 2003)
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.
e NOTE—1.5 was added editorially in November 2005.
INTRODUCTION
Thefeasibilityoftherecycleofbulkmaterialcontainingtraceamountsofradioactivecontamination
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.
Ifdoseratelimitsareestablishedbyregulation,thisapproachisarecommendedwaytodemonstrate
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 isolated to prevent human contact from that that can be
recycled or otherwise disposed of. It applies to material in
1.1 This guide covers the techniques for obtaining approval
which the radioactivity is dispersed more or less uniformly
for release of materials encountered in decontamination and
throughout the volume of the material (termed residual in bulk
decommissioning (D&D) from restricted use. It applies to
form) as opposed to surface contaminated objects.
materials that do not meet any of the requirements for
1.3 Surface contaminated objects are materials externally
regulatory control because of radioactivity content. Fig. 1
contaminated with radioactive material. Provisions already
shows the logic diagram for determining the materials that
exist for their release for recycle if it can be shown that they
could be considered for release. Materials that negotiate this
meet applicable federal and state regulations for surface
logic tree are referred to as “candidate for release based on
contamination. Regulatory Guide 1.86 and DOE Order 5400.5
dose.”
specify the upper limits for radioactive surface contamination
1.2 The objective of this guide is to provide a methodology
on material to be released for unrestricted use.
for distinguishing between material that must be carefully
1.4 The release of material containing residual radioactive
material (except for Ra) in bulk form (for example, soil or
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
slightly activated metal) is based on the demonstration that the
Technology and Applications and is the direct responsibility of Subcommittee
E10.03 on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
Current edition approved Jan. 10, 1996. Published March 1996.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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E1760–96 (2003)
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
thanthesecondsincethedosetoanymemberofthepublic(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 Ra
contaminated soils.
1.5 Warning—Breathing of asbestos dust is hazardous.
Asbestos and asbestos products present demonstrated health
risksforusersandforthosewithwhomtheycomeintocontact.
In addition to other precautions, when working with asbestos
products, minimize the dust that results. For information on the
safe use of chrysoltile asbestos, refer to “Safe Use of Chryso-
tileAsbestos:AManual on Preventive and Control Measures.”
1.6 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 appro-
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use. For a specific
hazard see 1.5.
2. Referenced Documents
2.1 ASTM Standards:
E 1278 Guide for Radioactive Pathway Methodology for
Release of Sites Following Decommissioning
FIG. 1 Prerequisites for Material To Be Candidate For Release
2.2 American Nuclear Insurers Document:
ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-
ity Insurance Records Retention
Geological Repositories
2.3 DOE Document:
10 CFR 61, Licensing Requirements for Land Disposal of
DOE Order 5400.5, Radiation Protection of the Public and
Radioactive Waste
the Environment
40 CFR 117, Determination of Reportable Quantities for
Regulatory Guide 1.86, Termination of Operating Licenses
Hazardous Substances
for Nuclear Reactors
40 CFR261,IdentificationandListingofHazardousWaste
2.4 International Atomic Energy Agency Document:
40 CFR 268, Land Disposal Restrictions
Safety Series No. 111-P-1.1, Application of Exemption
40 CFR 712, Chemical Information Rules
Principles to the Recycle and Reuse of Materials from
40 CFR 716, Health and Safety Data Reporting
Nuclear Facilities
2.5 Nuclear Regulatory Commission Document:
3. Terminology
NUREG/CR-5512, Residual Radioactive Contamination
3.1 Definitions of Terms Specific to This Standard:
from Decommissioning
3.1.1 credible, adj—offering reasonable grounds for being
2.6 U.S. Government Documents:
believed.
40 CFR 192, Health and Environmental Protection Stan-
3.1.2 intended use, n—the first use planned for the material
dards for Uranium and Thorium Mill Tailings
proposed to be released from radiological controls.
10 CFR 60, Disposal of High-Level Radioactive Wastes in
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
Annual Book of ASTM Standards, Vol 12.02.
could occur via the unplanned use scenario.
Available from American Nuclear Insurers, 29 South Main, Suite 300 S, West
3.1.5 unplanned use, n—any use other than the planned use
Hartford, CT 06107-2445.
that may occur after the intended use or by accident.
Available from Department of Energy, NationalTechnical Information Service,
U.S. Dept. of Commerce, Springfield, VA 22161.
International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100,
4. Summary of Guide
A-1400 Vienna, Austria.
4.1 The owner of the material must first determine if the
Available from the Superintendent of Documents, U.S. Government Printing
Office, Washington, DC 20402. material is candidate for release. To do this one must take
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E1760–96 (2003)
representative samples of the bulk material and identify the Conversely, it is not reasonable to expend a disproportionate
radioactive contaminants and concentrations. Sampling should amount of resources to isolate materials that contain minute
be done using standard statistical inspection methods. The quantities of radioactive materials that will not cause even
kinds of analyses shall be appropriate for the potential con- statistically measurable health effects.
taminant expected, and performed using standard techniques. 5.2 This guide provides a rationale and methodology for
3 14
For some of these analyses, for example,Hor C in activated distinguishing between materials that contain sufficient radio-
concrete or Fe in steel, the standard techniques are beyond activity to warrant isolation of some type (storage awaiting
the capabilities of many laboratories. Material that passes the decay, near-surface disposal, disposal with intruder protection,
logic diagram shown in Fig. 1 is candidate for release. The or placement in a deep repository) from materials with insig-
sampling, analysis, and determination of candidacy must be nificant radioactive content. Materials with insignificant radio-
documented and included in the record package. active content can be recycled in the economy or disposed of
4.2 Fig. 2 diagrammatically shows how a material that is in conventional (landfill) facilities without adverse health
candidate for release should be treated to justify its release effects. Materials that meet the criteria identified in this guide
from radiologically restricted use. Section 7 describes the are not simply excluded from regulation because they do not
methodology shown. fall precisely in the regulatory scope. They are sufficiently free
of radioactive material so that no further efforts at control are
5. Significance and Use
justified for radiation protection purposes. Therefore, the re-
lease of materials for unrestricted use in accordance with this
5.1 Materials encountered during D&D may contain re-
guide meets the criteria for being an “as low as reasonably
sidual radioactivity varying in amounts from that in irradiated
achievable” (ALARA) activity.
fuel to barely detectable quantities in or on building materials.
5.3 For the purpose of this guide, the return of materials
It is clear that highly radioactive materials have to be disposed
containing residual radioactivity to society without regulatory
as radioactive waste pursuant to 10 CFR 60 and 10 CFR 61.
restrictions is referred to as “unrestricted release based on the
absence of the credible potential for adverse health effects.”
This guide asserts that materials recycled this way will have no
statistically measurable health effects regardless of use. It does
not guarantee that the materials are suitable for use in every
possible application, for example, trace amounts of radionu-
clides in materials may not be acceptable for certain photo-
graphic and electronic applications.
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
usedfortheintendedpurpose.Second,thematerialmustnotbe
expectedtocausemorethantheunplannedusedoselimitwhen
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.
Sometypesofbuildingmaterialfrombothgroupsthatcouldbe
FIG. 2 Methodology for Approving Candidate Material for
Unrestricted Release cost effectively released are described in 7.1.1-7.1.6.
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E1760–96 (2003)
7.1.1 Miscellaneous and structural steel that is not intended regulatory control because of its radioactivity. The second step
foruse“asis”(onthebasisofsurfacecontamination)wouldbe is to show that the dose by planned and unplanned scenarios is
smelted. Contaminant levels in the melt would be minimized acceptably small. Fig. 1 shows diagrammatically how the first
by avoiding the selection of steel from highly contaminated step is accomplished, and Fig. 2 outlines the process for the
areas or surface cleaning the steel before smelting. In addition, second step. The processes shown in the figures are described
the slagging process also generally reduces the concentration in 8.1.1-8.1.13.
of contaminants in the melt. If the metal ingot met the release
8.1.1 Aprerequisite to the first step in releasing material for
criteria given in this guide it would not have to be disposed of
unrestricted use is to identify and characterize the material (see
as radioactive waste. At worst it would be disposed of in a
3.1). One needs to know or determine what radionuclides are
sanitary landfill. Preferably it would be recycled.
present, their average concentration, and the amount of varia-
7.1.2 Asbestos insulation is a porous bulk material that is
tion. This information is used to determine if a material should
not amenable to surface surveys. Economical decontamination
be candidate for release, and later to do the pathways analysis.
methods for asbestos insulation have not been demonstrated.
Fig. 1 shows the methodology for determining a material’s
Ordinarily, most of the asbestos in a facility is not contami-
candidacy. By proceeding through these gates, materials that
nated or is very slightly contaminated, but cannot be shown to
aresubjecttotheregulationsshown(becauseofthepresenceof
be absolutely free of radioactivity.Asbestos could be disposed
radionuclides) are excluded one by one. Materials remaining
of in a permitted landfill instead of a licensed radioactive
are considered to be candidates for release. Subsequent steps
materials disposal site if shown to meet the release criteria
are then taken to show that credible doses that may result are
given in this guide
...