ASTM E2216-02(2008)
(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
SIGNIFICANCE AND USE
This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.
It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.
This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.
This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.
General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.
This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
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,” (1) 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: E2216 − 02(Reapproved 2008)
Standard Guide for
Evaluating Disposal Options for Concrete from Nuclear
Facility Decommissioning
This standard is issued under the fixed designation E2216; 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 (´) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
Numerous nuclear facilities containing large amounts of concrete are scheduled for decontamina-
tion 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
dose to nonradiation workers (the public); the methodology
1.2 This standard guide is based on the “Protocol for
and supporting data to perform this analysis are detailed in the
Development of Authorized Release Limits for Concrete at
appendices.The resulting data can be used to balance dose and
U.S.DepartmentofEnergySites,”(1) fromwhichtheanalysis
methodology and supporting data are taken.
1.3 Guide E1760 provides a general process for release of
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
materials containing residual amounts of radioactivity. In
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. 1, 2008. Published March 2008. Originally
approved in 2002. Last previous edition approved in 2008 as E2216–02. DOI: The boldface numbers in parentheses refer to a list of references at the end of
10.1520/E2216-02R08. this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E2216 − 02 (2008)
addition, Guide E1278 provides a general process for analyz- 2.5 DOE Standards:
ing radioactive pathways. This standard guide is intended for DOE G 441.1–1B Radiation Protection Programs Guide,
use in conjunction with Guides E1760 and E1278, and pro- Order 5400.5 Radiation Protection of the Public and the
vides a more detailed approach for the release of concrete. Environment, as amended
Order 5400.5 Radiation Protection of the Public and the
2. Referenced Documents
Environment, as amended
2.6 U.S. Government Documents:
2.1 ASTM Standards:
NUREG-1640 Radiological Assessments for Clearance of
E1278 Guide for Radioactive Pathway Methodology for
Equipment and Materials From Nuclear Facilities
Release of Sites Following Decommissioning (Withdrawn
NUREG/CR-5512 Residual Radioactive Contamination
2005)
From Decommissioning
E1760 Guide for Unrestricted Disposition of Bulk Materials
10 CFR 20 Standards for Protection Against Radiation
Containing Residual Amounts of Radioactivity
2.7 NRC Standards:
E1893 Guide for Selection and Use of Portable Radiological
Regulatory Guide 1.86 Termination of Operating Licenses
Survey Instruments for Performing In Situ Radiological
for Nuclear Reactors
Assessments to Support Unrestricted Release from Fur-
ther Regulatory Controls
3. Terminology
2.2 ANSI Standards:
3.1 Definitions of Terms Specific to This Standard:
ANSI/HPS N13.12 Surface and Volume Radioactivity Stan-
3.1.1 activated concrete—concrete that has components
dards for Clearance
(such as metal filings or pieces) that have become radioactive
ANSI/HPS N13.2 Guide for Administrative Practices in
through exposure to high radiation fields; the concrete itself is
Radiation Monitoring
6 radioactive.
2.3 IAEA Standards:
Safety Series No. 111-P-1.1 Application of Exemption Prin- 3.1.2 as low as reasonably achievable (ALARA)—is a pro-
cess used for radiation protection to manage and control
ciplestotheRecycleandReuseofMaterialsfromNuclear
Facilities exposures(bothindividualandcollectivetotheworkforceand
tothegeneralpublic)andreleasesofradioactivematerialtothe
IAEA-TECDOC-855 ClearanceLevelsforRadionuclidesin
Solid Materials environment so that the levels are as low as is reasonable
taking into account social, technical, economic, practical, and
2.4 ISO Standards:
public policy consideration. ANSI/HPS N13.12
ISO-4037 X and Gamma Reference Radiations for Calibrat-
ing Dosimeters and Dose-rate Meters and for Determining
3.1.3 release—occurs when property is transferred out of
their Response as a Function of Photon Energy regulatory control by sale, lease, gift, or other disposition,
ISO-6980-1 Nuclear Energy – Reference beta-particle radia-
provided that the property does not remain under radiological
tion – Part 1: Methods of production control by a regulatory agency. The release does not apply to
ISO-6980-2 Nuclear Energy – Reference beta-particle ra-
real property (such as real estate), radioactive wastes, soils,
diation – Part 2: Calibration fundamentals related to basic liquid discharges, or gaseous or radon emissions.
quantities characterizing the radiation field
3.1.4 surface contamination—radioactive contamination re-
ISO-8769 Reference Sources for the Calibration of Surface
sidingonornearthesurfaceofanitem.Thiscontaminationcan
Contamination Monitors—Beta Emitters (Maximum Beta
be adequately quantified in terms of activity per unit area.
Energy Greater than 0.15 MeV) and Alpha Emitters
ANSI/HPS N13.12
ISO-7503-1 Evaluation of Surface Contamination—Part 1:
3.1.5 volumetric contamination—radioactive contamination
Beta Emitters (Maximum Beta Energy Greater than 0.15
residing in or throughout the volume of an item. Volumetric
MeV) and Alpha Emitters
contamination can result from neutron activation or from the
ISO-7503-2 Evaluation of Surface Contamination—Part 2:
penetration of radioactive contamination into cracks or interior
Tritium Surface Contamination
surfaces within the interior matrix of an item. ANSI/HPS
ISO-7503-3 Evaluation of Surface Contamination—Part 3:
N13.12
Isomeric Transition and Electron Capture Emitters, Low
Energy Beta Emitters (E <0.15 MeV)
Bmax
4. Significance and Use
4.1 This standard guide applies to concrete that is still in
For referenced ASTM standards, visit the ASTM website, www.astm.org, or placewithadefinedgeometryandknown,documentedhistory.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
4.2 It is not intended for use on concrete that has already
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. been rubbelized where it is difficult to measure the radiation
The last approved version of this historical standard is referenced on
www.astm.org.
5 8
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St., Available from United States Department of Energy, National Technical
4th Floor, New York, NY 10036, http://www.ansi.org. Information Service, US Dept. of Commerce, Springfield, VA 22161.
6 9
AvailablefromInternationalAtomicEnergyAgency,Wagramerstrasse,POBox Available from the Superintendent of Documents, US Government Printing
100 A-1400, Vienna, Austria. Office, Washington, DC 20402.
7 10
Available from International Organization for Standardization (ISO), 1 rue de Available from Nuclear Regulatory Commission, Public Document Room,
Varembé, Case postale 56, CH-1211, Geneva 20, Switzerland. 1717H St. NW, Washington, DC 20555.
E2216 − 02 (2008)
levels and not easy to remove surface contamination to reduce radioactive contamination, or this can be measured. Radiologi-
radiation levels after concrete has been rubbelized. cal surveys must be done to determine the isotopes and level of
radioactive contamination on the surface of the concrete.
4.3 This standard guide applies to surface or volumetrically
contaminated concrete, where the depth of contamination can 5.4 Determine Whether Authorized Release Guidelines Al-
be measured or estimated based on the history of the concrete.
ready Exist:
5.4.1 If surface or volumetric activity release guidelines
4.4 This standard guide does not apply to the reinforcement
exist, and the concrete is below those levels, the concrete can
bar (rebar) found in concrete.Although most concrete contains
be released through approved regulatory methods. Documents
rebar, it is generally removed before the concrete is disposi-
including ANSI/HPS N13.12-1999, U.S. NRC Regulatory
tioned. In addition, rebar may be activated, and is covered
Guide 1.86, and others may provide applicable release guide-
under procedures for reuse of scrap metal.
lines. In any case, this standard guide can be used to complete
4.5 General unit-dose and unit-cost data to support the
an analysis of the dose and cost for various disposal options
calculations is provided in the appendices of this standard
and select the best one.All required regulatory approvals must
guide. However, if site-specific data is available, it should be
still be obtained before releasing the concrete.
used instead of the general information provided here.
5.4.2 If no existing guidelines apply, this standard guide can
4.6 This standard guide helps determine estimated doses to
be used to estimate the ramifications of each disposal option,
thepublicduringdisposalofconcreteandtofutureresidentsof
select the best disposal option, and then apply for approval to
disposal areas. It does not include dose to radiation workers releasethematerialbasedonthesedata.Suchreleasescouldbe
already involved in a radiation control program. It is assumed
doneonacase-by-casebasis,ortosetanewauthorizedrelease
that the dose to radiation workers is already tracked and kept limit.
within acceptable levels through a radiation control program.
5.5 Define WhatAuthorized or Supplemental Guidelines are
The cost and dose to radiation workers could be added in to
Needed:
find an overall cost and dose for each option.
5.5.1 If authorized release guidelines do not exist, define
what type of guidelines need to be developed:
5. Elements of the Release Process
5.5.1.1 Surface or volumetric contamination;
5.1 This standard guide describes the steps of an overall
5.5.1.2 One-time or routine release;
release process for radioactively contaminated concrete from
5.5.1.3 Restricted or unrestricted release.
decommissioning nuclear facilities. As one of the steps, it
5.6 Define Authorized or Supplemental Guidelines:
providesamethodandsupportingdatatoestimatethedoseand
5.6.1 Estimate the dose and cost for the various disposal
costimpactsforvariousdisposaloptions.Thisdatacanbeused
options. Each disposal option consists of a set of actions such
to select the best disposal option, which should be one that
as decontamination and disposal. The dose and cost of a
meets regulatory guidelines while reducing dose and cost.
disposal option depend upon the actions that make up that
Releaseofanysurfaceorvolumetricallycontaminatedmaterial
option. Five actions are defined in the appendices:
must meet all criteria of the governing regulatory agencies.
decontamination, demolition/crushing, packaging/
5.2 Ref (2) described a 10-step release process in the
transportation, reuse, and disposal/entombment. The appendi-
publication, “Authorized Release of DOE’s Non-Real Prop-
ces provide the methodology and supporting data to estimate
erty: Process and Approach.” These 10 steps are the basis for
the dose and cost of each action. To evaluate a disposal option,
the, “Protocol for Development of Authorized Release Limits
use the applicable sections in the appendices to calculate the
for Concrete at U.S. Department of Energy Sites” (1) and also
dose and cost for each action in the disposal option. Then sum
for this guide.
the dose and cost from all of the applicable actions to find the
5.2.1 Characterize property and prepare a description;
total dose and cost 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, s
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