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ASTM E1760-96(2003)

(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 (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
Current Stage
Ref Project

Relations

Replaces
ASTM E1760-96 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
Effective Date
10-Jan-1996
Replaced By
ASTM E1760-96(2003)e1 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
Effective Date
10-Jan-1996
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

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ASTM E1760-96(2003) - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of RadioactivityASTM E1760-96(2003) - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
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ASTM E1760-96(2003) - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
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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
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.
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 exist for their release for recycle if it can be shown that they
meet applicable federal and state regulations for surface
1.1 This guide covers the techniques for obtaining approval
contamination. Regulatory Guide 1.86 and DOE Order 5400.5
for release of materials encountered in decontamination and
specify the upper limits for radioactive surface contamination
decommissioning (D&D) from restricted use. It applies to
on material to be released for unrestricted use.
materials that do not meet any of the requirements for
1.4 The release of material containing residual radioactive
regulatory control because of radioactivity content. Fig. 1
material (except for Ra) in bulk form (for example, soil or
shows the logic diagram for determining the materials that
slightly activated metal) is based on the demonstration that the
could be considered for release. Materials that negotiate this
dose to a member of the public will be lower than a specified
logic tree are referred to as “candidate for release based on
value (proposed by the petitioner or to be determined by future
dose.”
regulation) for its intended use and lower than a second
1.2 The objective of this guide is to provide a methodology
specified value (also proposed by the petitioner or to be
for distinguishing between material that must be carefully
determined by future regulation) via the most restrictive
isolated to prevent human contact from that that can be
plausible scenario. The first proposed value should be lower
recycled or otherwise disposed of. It applies to material in
thanthesecondsincethedosetoanymemberofthepublic(via
which the radioactivity is dispersed more or less uniformly
the intended use scenario) will almost certainly be realized,
throughout the volume of the material (termed residual in bulk
whereas the dose from the alternate scenario will only accrue
form) as opposed to surface contaminated objects.
if an unintended (and presumably less probable) circumstance
1.3 Surface contaminated objects are materials externally
arises. Federal regulation already exists for the release of Ra
contaminated with radioactive material. Provisions already
contaminated soils.
1.5 This standard does not purport to address all of the
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
safety concerns, if any, associated with its use. It is the
Technology and Applications and is the direct responsibility of Subcommittee
responsibility of the user of this standard to establish appro-
E10.03 on Radiological Protection for Decontamination and Decommissioning of
priate safety and health practices and determine the applica-
Nuclear Facilities and Components.
bility of regulatory limitations prior to use.
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.
E1760–96 (2003)
2. Referenced Documents NUREG/CR-5512, Residual Radioactive Contamination
from Decommissioning
2.1 ASTM Standards:
2.6 U.S. Government Documents:
E 1278 Guide for Radioactive Pathway Methodology for
40 CFR 192, Health and Environmental Protection Stan-
Release of Sites Following Decommissioning
dards for Uranium and Thorium Mill Tailings
2.2 American Nuclear Insurers Document:
10 CFR 60, Disposal of High-Level Radioactive Wastes in
ANI/MAELU Information Bulletin 80-1A, Nuclear Liabil-
Geological Repositories
ity Insurance Records Retention
10 CFR 61, Licensing Requirements for Land Disposal of
2.3 DOE Document:
Radioactive Waste
DOE Order 5400.5, Radiation Protection of the Public and
40 CFR 117, Determination of Reportable Quantities for
the Environment
Hazardous Substances
Regulatory Guide 1.86, Termination of Operating Licenses
40 CFR261,IdentificationandListingofHazardousWaste
for Nuclear Reactors
40 CFR 268, Land Disposal Restrictions
2.4 International Atomic Energy Agency Document:
40 CFR 712, Chemical Information Rules
Safety Series No. 111-P-1.1, Application of Exemption
40 CFR 716, Health and Safety Data Reporting
Principles to the Recycle and Reuse of Materials from
Nuclear Facilities
3. Terminology
2.5 Nuclear Regulatory Commission Document:
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
Annual Book of ASTM Standards, Vol 12.02.
proposed to be released from radiological controls.
Available from American Nuclear Insurers, 29 South Main, Suite 300 S, West
3.1.3 primary dose limit, n—the limit for exposures that
Hartford, CT 06107-2445.
could occur via the intended use scenario.
Available from Department of Energy, NationalTechnical Information Service,
U.S. Dept. of Commerce, Springfield, VA 22161.
3.1.4 secondary dose limit, n—the limit for exposure that
International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100,
could occur via the unplanned use scenario.
A-1400 Vienna, Austria.
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
radioactive contaminants and concentrations. Sampling should
be done using standard statistical inspection methods. The
kinds of analyses shall be appropriate for the potential con-
taminant expected, and performed using standard techniques.
3 14
For some of these analyses, for example,Hor C in activated
concrete or Fe in steel, the standard techniques are beyond
the capabilities of many laboratories. Material that passes the
logic diagram shown in Fig. 1 is candidate for release. The
sampling, analysis, and determination of candidacy must be
documented and included in the record package.
4.2 Fig. 2 diagrammatically shows how a material that is
candidate for release should be treated to justify its release
from radiologically restricted use. Section 7 describes the
methodology shown.
5. Significance and Use
5.1 Materials encountered during D&D may contain re-
sidual radioactivity varying in amounts from that in irradiated
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.
Conversely, it is not reasonable to expend a disproportionate
Available from the Superintendent of Documents, U.S. Government Printing
FIG. 1 Prerequisites for Material To Be Candidate For Release Office, Washington, DC 20402.
E1760–96 (2003)
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.
FIG. 2 Methodology for Approving Candidate Material for
Sometypesofbuildingmaterialfrombothgroupsthatcouldbe
Unrestricted Release
cost effectively released are described in 7.1.1-7.1.6.
7.1.1 Miscellaneous and structural steel that is not intended
amount of resources to isolate materials that contain minute foruse“asis”(onthebasisofsurfacecontamination)wouldbe
quantities of radioactive materials that will not cause even smelted. Contaminant levels in the melt would be minimized
statistically measurable health effects. by avoiding the selection of steel from highly contaminated
5.2 This guide provides a rationale and methodology for areas or surface cleaning the steel before smelting. In addition,
distinguishing between materials that contain sufficient radio- the slagging process also generally reduces the concentration
activity to warrant isolation of some type (storage awaiting
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 asbestos insulation, built-up roofing, and sheet rock are not
containing residual radioactivity to society without regulatory amenable to surface survey for release. Although these mate-
restrictions is referred to as “unrestricted release based on the rials are not ordinarily useful for recycle they could be
E1760–96 (2003)
disposed of in a sanitary landfill rather than at a licensed 8.1.3 Theintendeduseofthematerialshallbespecified,and
disposal facility if they met the release criteria described in this the person likely to have the highest risk (receptor) and the
guide.
scenario for exposure shall be identified. These determinations
7.1.4 Granular materials such as soil, concrete, or masonry shall be included in the documentation package described in
rubble cannot be surveyed against surface criteria. However,
8.1.8. Appendix X1 gives some typical examples of material,
they could be disposed of in a sanitary landfill or used as clean
intended use scenarios, and receptors.
fill if shown to meet the release criteria recommended in this
8.1.4 Computetheannualdosetothereceptorbywayofthe
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-
utedwithinthesolidmassbecauseoftheneutrontransmutation
cation of Exemption Principles to the Recycle and Reuse of
of atoms within the material itself. Surface measurements
Materials from Nuclear Facilities.” All applicable pathways
generally are not appropriate for the release of such material.
shall be considered. For example, if material were to be
However, a metal could be smel
...

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1.1 This guide provides an approach for developing a basis for obtaining approval for release of bulk materials to be removed from a decontamination and decommissioning (D&D) or environmental remediation site from regulatory control. This would be addressed in the decommissioning plan (Guide E1281). Fig. 1 follows the logic described in the MARSAME 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.”    
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1.2 The purpose of this guide is to provide the user with information on assessing the effective use of spill-cleanup equipment. It is intended for use by those involved in planning for and responding to oil spills.  
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5.1 Waste samples collected using this practice provide representative samples for analysis in a laboratory using the TCLP.  
5.2 The TCLP is used to simulate the transfer of lead from buried lead-containing waste into the ground water system upon codisposal of the lead-containing waste and municipal solid waste in unlined solid-waste landfills. The TCLP attempts to simulate rain or ground water leaching, or both. For the procedure to yield a predictor of the subsurface (in-ground) leaching process, a representative sample of the volume of the waste must be selected and submitted for leaching and analysis. The result of the sampling, leaching, and analysis process is used to determine the waste handling and disposal protocols to be followed and to document compliance with applicable laws, regulations, and requirements. This practice addresses the sampling process by defining a component-volume-based method to collect and assemble a representative sample of a solid waste stream that may contain heterogeneous components.  
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(1) Not to be less than 4.93 ± 0.05 for the extraction of wastes with an acid neutralization capacity of less than the acid available in the total volume of extraction fluid used in the method (Extraction Fluid No. 1).
(2) At 2.88 ± 0.05, as defined by the pH of the acid, for the extraction of wastes with an acid neutralization capacity of more than the acid available in the extraction fluid used in the method (Extraction Fluid No. 2).  
5.5 The interpretation and use of the results of this test method are limited by the assumptions of a single co-disposal scenario and by the factors affecting the composition of a landfill leachate and chemical or other differences between a selected extraction fluid and the real landfill leachate.  
5.6 This test method may be affected by biological changes in the waste, and it is not designed to isolate or measure the effect of such processes.  
5.7 This test method produces extracts that are amenable to the determination of both minor and major constituents. When minor constituents are being determined,...
SCOPE
1.1 This test method is applicable to the extraction of samples of treated or untreated solid wastes or sludges, or solidified waste samples, to provide an indication of the leaching potential.  
1.2 This test method is intended to provide an extract for measurement of the concentration of the analytes of concern. The measured values may be compared against set or chosen acceptance levels in some applications.  
1.3 If the sole application of the test method is such a pass/fail comparison and a total analysis of the waste demonstrates that individual analytes are not present in the waste, or that the chosen acceptance concentration levels could not possibly be exceeded, the test method need not be run.  
1.4 If the sole application of the test method is such a pass/fail comparison and an analysis of any one of the liquid fractions of the extract indicates that the concentration of the target analyte is so high that, even after accounting for dilution from the other fractions of the extract, it would be equal to or above an acceptance concentration level, then the waste fails the test. In such a case it may not be necessary to analyze the remaining fractions of the extract.  
1.5 This test method is intended to provide an extract suitable for the measurement of the concentration of analytes that will not volatilize under the conditions of the test method.  
1.6 Presence of volatile analytes may be established if an analysis of the extract obtained using this test method detects the target volatile analyte. If its concentration is equal to or exceeds an acceptance level for that analyte, the waste fails the test. However, extract from this test method shall not be used to determine the concentration of volatile organic analytes.  
1.7 This test method is intended to describe only the procedure for performing a batch extraction. It does not describe all of the sampling and analytical requirements that may be associate...

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ASTM
ASTM D4793-09(2023)(Test Method)
Standard Test Method for Sequential Batch Extraction of Waste with Water

SIGNIFICANCE AND USE
4.1 This test method is intended as a means for obtaining sequential extracts of a waste. The extracts may be used to estimate the release of certain constituents of the waste under the laboratory conditions described in this test method.  
4.2 This test method is not intended to provide extracts that are representative of the actual leachate produced from a waste in the field or to produce extracts to be used as the sole basis of engineering design.  
4.3 This test method is not intended to simulate site-specific leaching conditions. It has not been demonstrated to simulate actual disposal site leaching conditions.  
4.4 An intent of this test method is that the final pH of each of the extracts reflects the interaction of the extractant with the buffering capacity of the waste.  
4.5 An intent of this test method is that the water extractions reflect conditions where the waste is the dominant factor in determining the pH of the extracts.  
4.6 This test method produces extracts that are amenable to the determination of both major and minor constituents. When minor constituents are being determined, it is especially important that precautions are taken in sample storage and handling to avoid possible contamination of the samples.  
4.7 This test method has been tested to determine its applicability to certain inorganic components in the waste. This test method has not been tested for applicability to organic substances, volatile matter (see Note 3 in 5.15), or biologically active samples.  
4.8 The agitation technique, rate, liquid-to-solid ratio, and filtration conditions specified in the procedure may not be suitable for extracting all types of wastes (see Sections 7, 8, and the discussion in Appendix X1).
SCOPE
1.1 This test method is a procedure for the sequential leaching of a waste containing at least five percent solids to generate solutions to be used to determine the constituents leached under the specified testing conditions.  
1.2 This test method calls for the shaking of a known weight of waste with water of a specified purity and the separation of the aqueous phase for analysis. The procedure is conducted ten times in sequence on the same sample of waste and generates ten aqueous solutions.  
1.3 This test method is intended to describe the procedure for performing sequential batch extractions only. It does not describe all types of sampling and analytical requirements that may be associated with its application.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM D5284-09(2023)(Test Method)
Standard Test Method for Sequential Batch Extraction of Waste with Acidic Extraction Fluid

SIGNIFICANCE AND USE
4.1 This test method is intended as a means for obtaining sequential extracts of a waste. The extracts may be used to estimate the release of certain constituents of the waste under the laboratory conditions described in this test method.  
4.2 The pH of the extraction fluid used in this test method is to reflect the pH of acidic precipitation in the geographic region in which the waste being tested is to be disposed.
Note 1: Possible sources of information concerning the pH of precipitation in the geographic region of interest include state and federal environmental agencies, state universities, libraries, etc.  
Note 2: For sequential batch extraction of waste using a nonacidic extraction fluid, see Test Method D4793.  
4.3 An intent of this test method is for the final pH of each of the extracts to reflect the interaction of the extractant with the buffering capacity of the waste.  
4.4 This test method is not intended to provide extracts that are representative of the actual leachate produced from a waste in the field or to produce extracts to be used as the sole basis of engineering design.  
4.5 This test method has not been demonstrated to simulate actual disposal site leaching conditions.  
4.6 This test method produces extracts that are amenable to the determination of both major and minor (trace) constituents. When minor constituents are being determined, it is especially important that precautions be taken in sample storage and handling to avoid possible contamination of the samples.  
4.7 This test method has been tested to determine its applicability to certain inorganic components in the waste. This test method has not been tested for applicability to organic substances, volatile matter (see Note 5), or biologically active samples.  
4.8 The agitation technique, rate, liquid-to-solid ratio, and filtration conditions specified in the procedure may not be suitable for extracting all types of wastes (see Sections 7 and 8 and Appendix X1).
SCOPE
1.1 This test method provides a procedure for the sequential leaching of a waste containing at least 5 % dry solids in order to generate solutions to be used to determine the constituents leached under the specified testing conditions.  
1.2 This test method calls for the shaking of a known weight of waste with acidic extraction fluid of a specified composition as well as the separation of the liquid phase for analysis. The pH of the extraction fluid is to reflect the pH of acidic precipitation in the geographic region in which the waste being tested is to be disposed. The procedure is conducted ten times in sequence on the same sample of waste, and it generates ten solutions.  
1.3 This test method is intended to describe the procedure for performing sequential batch extractions only. It does not describe all types of sampling and analytical requirements that may be associated with its application.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM D7204-23(Practice)
Standard Practice for Sampling Waste Streams on Conveyors

SIGNIFICANCE AND USE
4.1 This practice can be used in sampling ash from a kiln or incinerator, soils, and process waste from conveying systems, such as a conveyer and vertical lifts. Some slurries, such as the bottom solids, can be sampled from the quench waters at the end of a kiln.  
4.2 This practice can be used to determine material balances for burner efficiency studies and compliance studies.  
4.3 This practice can be used on lifts, sloping, and horizontal conveyor systems. The type of conveyor and the amount and type of sample required will dictate the type of sampling equipment required to get a representative sample.  
4.4 The sample is taken directly from the conveyor before emptying into the waste container or pile for disposal or recycling using a scoop, dipper, or shovel depending upon the sample requirements (see Practice D5633). The sample is then put into the sample container for analysis.  
4.5 The place, quantity, frequency, and time of sampling is dependent upon the conveying system equipment, data quality objectives (DQOs) (Practice D5792), work or sampling plan (see Practice D5283 and Guide D4687), and analysis to be run.  
4.5.1 Large particles can be mechanically excluded on a belt system. Large particles may accumulate at the bottom of an inclined/sloped belt system. Therefore, steps, if possible, need to be taken so that particles of all sizes have equal chances of being sampled.  
4.5.2 The number of samples and sample time is dependent upon the system, the precision required, the decisions that are to be made, the cost, and the degree of heterogeneity of the material (see Guides D5956 and D6311).  
4.5.3 In general, the ideal sampling location is nearest to the point of generation since temperature, oxidation, and air movement may change some samples with time.  
4.6 The practice does not address issues related to the heterogeneity of the sample.
SCOPE
1.1 This practice describes standard procedures for sampling waste on open and closed conveying systems and is applicable to any waste material that can be conveyed to a waste pile or container. The conveyor system can be a vertical (vertical lifts), sloped, or horizontal type.  
1.2 This practice is intended for particles and slurries, which can be sampled using scoop, dipper, or shovel type samplers.  
1.3 The practice is not intended for large size sample constituents, such as boulders, large rocks, and debris.  
1.4 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E889-82(2023)(Test Method)
Standard Test Method for Composition or Purity of a Solid Waste Materials Stream

SIGNIFICANCE AND USE
5.1 This method is used to document the ability of solid waste resource recovery separators to concentrate or classify a particular component (or components) present in solid waste.  
5.2 The purity determined in this way is used to calculate the recovery achieved by a separator as another measure of its performance, according to Test Method E1108.
SCOPE
1.1 This test method covers the determination of the composition of a materials stream in a solid waste resource recovery processing facility. The composition is determined with respect to one or more defined components. The results are used for determining the purity resulting from the operation of one or more separators, and in conjunction with Test Method E1108 used to measure the efficiency of a materials separation device.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. For hazard statements, see Section 7.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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