ASTM E2216-02
(Guide)Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, ( 2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.
1.2 This standard guide is based on the "Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites," (Arnish, J. et.al., 2000) from which the analysis methodology and supporting data are taken.
1.3 Guide E 1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E 1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E 1760 and E 1278, and provides a more detailed approach for the release of concrete.
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Designation: E 2216 – 02
Standard Guide for
Evaluating Disposal Options for Concrete from Nuclear
Facility Decommissioning
This standard is issued under the fixed designation E 2216; 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
Numerousnuclearfacilitiescontaininglargeamountsofconcretearescheduledfordecontamination
and decommissioning over the next several decades. Much of this concrete is either not contaminated
or only lightly contaminated on or near the surface. However, since concrete is slightly porous, it has
the potential to be contaminated volumetrically.Volumetric contamination is more difficult to measure
than surface contamination, and currently there are no release guidelines for volumetrically
contaminated concrete. As a result, large volumes of concrete are often disposed of as radioactive
waste at a large cost.
Under certain conditions, the depth or amount of contamination may be limited such that a case can
be made for concrete release for other purposes outside of regulatory control. These cases are likely
to be ones where the radioactive contamination is shallow and is limited to a depth that can be
removed by scabbling (removal of the concrete surface), or where the depth can be estimated based
on the history and condition of the concrete. In addition to surface contaminated concrete, some
facilities contain activated concrete where the depths of contamination vary. This type of concrete
should be handled on a case-by-case basis.Accurate measurements of the radiation source are difficult
for activated concrete, because the activated portions of the embedded metal or concrete are partially
shielded by the concrete that lies between the source and the measuring device. Care must be taken
to measure radiation levels of activated concrete accurately, so actual radiation levels are documented
and used when applying release criteria.
This standard guide applies to nonrubbelized concrete that is still in place with a defined geometry
and known history where the depth of contamination can be measured or estimated based on its
history. It is not practical to measure radiation levels of concrete rubble. The process outlined here
starts with characterizing the concrete in place, then evaluating the dose to the public and cost of
various disposal options.
1. Scope cost and select the best disposal option. These data, which
establish a technical basis to apply to release the concrete, can
1.1 This standard guide defines the process for developing a
be used in several ways: (1) to show that the release meets
strategy for dispositioning concrete from nuclear facility de-
existing release criteria, (2) to establish a basis to request
commissioning. It outlines a 10-step method to evaluate
release of the concrete on a case-by-case basis, (3) to develop
disposal options for radioactively contaminated concrete. One
a basis for establishing release criteria where none exists.
of the steps is to complete a detailed analysis of the cost and
1.2 This standard guide is based on the “Protocol for
dose to nonradiation workers (the public); the methodology
Development of Authorized Release Limits for Concrete at
and supporting data to perform this analysis are detailed in the
U.S. Department of Energy Sites,” (Arnish, J. et.al., 2000)
appendices.The resulting data can be used to balance dose and
from which the analysis methodology and supporting data are
taken.
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
1.3 Guide E 1760 provides a general process for release of
Technology and Applications and is the direct responsibility of Subcommittee
materials containing residual amounts of radioactivity. In
E10.03 on Radiological Protection for Decontamination and Decommissioning of
addition, Guide E 1278 provides a general process for analyz-
Nuclear Facilities and Components.
ing radioactive pathways. This standard guide is intended for
Current edition approved June 10, 2002. Published October 2002.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E2216–02
use in conjunction with Guides E 1760 and E 1278, and 2.6 U.S. Government Documents:
provides a more detailed approach for the release of concrete. NUREG-1640 Radiological Assessments for Clearance of
Equipment and Materials From Nuclear Facilities
2. Referenced Documents
NUREG/CR-5512 Residual Radioactive Contamination
From Decommissioning
2.1 ASTM Standards:
10 CFR 20 Standards for Protection Against Radiation
E 1278 Guide for Radioactive Pathway Methodology for
2.7 NRC Standards:
Release of Sites Following Decommissioning
Regulatory Guide 1.86 Termination of Operating Licenses
E 1760 Guide for Unrestricted Disposition of Bulk Materi-
for Nuclear Reactors
als Containing Residual Amounts of Radioactivity
E 1893 Guide for Selection and Use of Portable Radiologi-
3. Terminology
calSurveyInstrumentsforPerformingInSituRadiological
Assessments in Support of Decommissioning
3.1 Definitions of Terms Specific to This Standard:
2.2 ANSI Standards:
3.1.1 activated concrete—concrete that has components
ANSI/USAS N13.12 Surface and Volume Radioactivity
(such as metal filings or pieces) that have become radioactive
Standards for Clearance
through exposure to high radiation fields; the concrete itself is
ANSI/USAS N13.2 Guide for Administrative Practices in
radioactive.
Radiation Monitoring
3.1.2 as low as reasonably achievable (ALARA)—is a pro-
2.3 IAEA Standards:
cess used for radiation protection to manage and control
Safety Series No. 111-P-1.1 Application of Exemption Prin- exposures (both individual and collective to the work force and
ciples to the Recycle and Reuse of Materials from Nuclear
tothegeneralpublic)andreleasesofradioactivematerialtothe
Facilities environment so that the levels are as low as is reasonable
IAEA-TECDOC-855 Clearance Levels for Radionuclides taking into account social, technical, economic, practical, and
in Solid Materials, (Interim Report for Comment) public policy consideration. ANSI/HPS N13.12
2.4 ISO Standards: 3.1.3 release—occurs when property is transferred out of
regulatory control by sale, lease, gift, or other disposition,
ISO-4037 X and Gamma Reference Radiations for Calibrat-
provided that the property does not remain under radiological
ing Dosimeters and Dose-rate Meters and for Determining
control by a regulatory agency. The release does not apply to
their Response as a Function of Photon Energy
real property (such as real estate), radioactive wastes, soils,
ISO-6980 Reference Beta Radiations for Calibrating Do-
liquid discharges, or gaseous or radon emissions.
simeters and Dose-rate Meters and for Determining Their
3.1.4 surface contamination—radioactive contamination re-
Response as a Function of Beta Radiation Energy
sidingonornearthesurfaceofanitem.Thiscontaminationcan
ISO-8769 Reference Sources for the Calibration of Surface
be adequately quantified in terms of activity per unit area.
Contamination Monitors—Beta Emitters (Maximum Beta
ANSI/HPS N13.12
Energy Greater than 0.15 MeV) and Alpha Emitters
3.1.5 volumetric contamination—radioactive contamination
ISO-7503-1 Evaluation of Surface Contamination—Part 1:
residing in or throughout the volume of an item. Volumetric
Beta Emitters (Maximum Beta Energy Greater than 0.15
contamination can result from neutron activation or from the
MeV) and Alpha Emitters
penetration of radioactive contamination into cracks or interior
ISO-7503-2 Evaluation of Surface Contamination—Part 2:
surfaces within the interior matrix of an item. ANSI/HPS
Tritium Surface Contamination
N13.12
ISO-7503-3 Evaluation of Surface Contamination—Part 3:
Isomeric Transition and Electron Capture Emitters, Low
4. Significance and Use
Energy Beta Emitters (E <0.15 MeV)
Bmax
2.5 DOE Standards:
4.1 This standard guide applies to concrete that is still in
DOE G 4441.1–7 Portable Monitoring Instrument Calibra- placewithadefinedgeometryandknown,documentedhistory.
4.2 It is not intended for use on concrete that has already
tion Guide for Use With Title 10, Code of Federal
Regulations, Part 835, Occupational Radiation Program, been rubbelized where it is difficult to measure the radiation
levels and not easy to remove surface contamination to reduce
6–17–1999.
radiation levels after concrete has been rubbelized.
Order 5400.5 Radiation Protection of the Public and the
4.3 This standard guide applies to surface or volumetrically
Environment, as amended
contaminated concrete, where the depth of contamination can
be measured or estimated based on the history of the concrete.
4.4 This standard guide does not apply to the reinforcement
Annual Book of ASTM Standards, Vol 12.02.
bar (rebar) found in concrete.Although most concrete contains
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036.
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100 A-1400, Vienna, Austria.
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Available from International Organization for Standardization (ISO), 1 rue de Available from the Superintendent of Documents, US Government Printing
Varembé, Case postale 56, CH-1211, Geneva 20, Switzerland. Office, Washington, DC 20402.
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Available from United States Department of Energy, National Technical Available from Nuclear Regulatory Commission, Public Document Room,
Information Service, US Dept. of Commerce, Springfield, VA 22161. 1717H St. NW, Washington, DC 20555.
E2216–02
rebar, it is generally removed before the concrete is disposi- lines. In any case, this standard guide can be used to complete
tioned. In addition, rebar may be activated, and is covered an analysis of the dose and cost for various disposal options
under procedures for reuse of scrap metal.
and select the best one.All required regulatory approvals must
4.5 General unit-dose and unit-cost data to support the still be obtained before releasing the concrete.
calculations is provided in the appendices of this standard
5.4.2 If no existing guidelines apply, this standard guide can
guide. However, if site-specific data is available, it should be
be used to estimate the ramifications of each disposal option,
used instead of the general information provided here.
select the best disposal option, and then apply for approval to
4.6 This standard guide helps determine estimated doses to
releasethematerialbasedonthesedata.Suchreleasescouldbe
the public during disposal of concrete and to future residents of
done on a case-by-case basis, or to set a new authorized release
disposal areas. It does not include dose to radiation workers
limit.
already involved in a radiation control program. It is assumed
5.5 Define WhatAuthorized or Supplemental Guidelines are
that the dose to radiation workers is already tracked and kept
Needed:
within acceptable levels through a radiation control program.
5.5.1 If authorized release guidelines do not exist, define
The cost and dose to radiation workers could be added in to
what type of guidelines need to be developed:
find an overall cost and dose for each option.
5.5.1.1 Surface or volumetric contamination;
5. Elements of the Release Process
5.5.1.2 One-time or routine release;
5.1 This standard guide describes the steps of an overall
5.5.1.3 Restricted or unrestricted release.
release process for radioactively contaminated concrete from
5.6 Define Authorized or Supplemental Guidelines:
decommissioning nuclear facilities. As one of the steps, it
5.6.1 Estimate the dose and cost for the various disposal
providesamethodandsupportingdatatoestimatethedoseand
options. Each disposal option consists of a set of actions such
costimpactsforvariousdisposaloptions.Thisdatacanbeused
as decontamination and disposal. The dose and cost of a
to select the best disposal option, which should be one that
disposal option depend upon the actions that make up that
meets regulatory guidelines while reducing dose and cost.
option. Five actions are defined in the appendices: decontami-
Releaseofanysurfaceorvolumetricallycontaminatedmaterial
nation, demolition/crushing, packaging/transportation, reuse,
must meet all criteria of the governing regulatory agencies.
and disposal/entombment. The appendices provide the meth-
5.2 S.Y. Chen, et al, (1999), described a 10-step release
process in the publication, “Authorized Release of DOE’s odology and supporting data to estimate the dose and cost of
Non-Real Property: Process andApproach.”These 10 steps are each action. To evaluate a disposal option, use the applicable
the basis for the, “Protocol for Development of Authorized sections in the appendices to calculate the dose and cost for
Release Limits for Concrete at U.S. Department of Energy each action in the disposal option. Then sum the dose and cost
Sites” (Arnish, J., et al, 2000) and also for this standard guide.
from all of the applicable actions to find the total dose and cost
5.2.1 Characterize property and prepare a description; for that disposal option.
5.2.2 Determine whether applicable authorized or supple-
5.6.2 The dose estimate is based on the isotopes present, the
mental guidelines already exist;
estimated or measured depth of penetration, and the disposal
5.2.3 Define authorized or supplemental guidelines needed;
option.Thecostisbasedonfactorsassociatedwiththedisposal
5.2.4 Develop authorized or supplemental guidelines;
option, such as decontamination, transportation, and disposal.
5.2.5 Compile and submit application for approval from the
The cost analysis information here does not include cost
regulatory agencies;
avoidance through such things as schedule acceleration and
5.2.6 Document approved guidelines in the public record;
reduced surveillance. Formulas and tables of unit-dose and
5.2.7 Implement approved guidelines;
unit-cost data for estimating the dose and cost are in the
5.2.8 Conduct surveys/measurements;
appendices. However, if site-specific information (such as cost
5.2.9 Verify that applicable authorized or supplemental
and decontamination factors) is available, it should be used
guidelines have been met; and
instead of the general information provided here.
5.2.10 Release property.
5.6.3 After completing a detailed analysis of the estimated
5.3 Characterize Property and Prepare a Description:
dose and cost for each option, compare the results and choose
5.3.1 Document the concrete’s physical and radiological
the best option. The best option is likely to be the on
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