ASTM E2216-02(2020)

Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 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.  
4.3 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.  
4.4 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.  
4.5 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.  
4.6 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)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
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.

General Information

• Status: Published
• Publication Date: 30-Jun-2020
• ICS: 27.120.01 - Nuclear energy in general
• 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 E2216-02(2013) - Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
• Effective Date: 01-Jul-2020
• Refers: ASTM E1760-16 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Jul-2016
• Refers: ASTM E1760-09 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Jun-2009
• Refers: ASTM E1893-08a - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Nov-2008
• Refers: ASTM E1893-08 - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Jun-2008
• Refers: ASTM E1893-97(2003) - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments in Support of Decommissioning
• Effective Date: 10-Jun-1997
• Refers: ASTM E1760-96(2003)e1 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 10-Jan-1996
• Refers: ASTM E1760-96(2003) - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 10-Jan-1996
• Refers: ASTM E1278-88(1996)e1 - Standard Guide for Radioactive Pathway Methodology for Release of Sites Following Decommissioning (Withdrawn 2005)
• Effective Date: 01-Jan-1996
• Refers: ASTM E1760-96 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Jan-1996
• Referred By: ASTM E1281-15(2021) - Standard Guide for Nuclear Facility Decommissioning Plans
• Effective Date: 01-Jul-2020

Overview

ASTM E2216-02(2020) is a standard guide developed by ASTM International for evaluating disposal options for concrete resulting from the decommissioning of nuclear facilities. This guide provides a structured, 10-step process for developing strategies to manage, analyze, and select the most appropriate method for disposing of radioactively contaminated concrete. Its emphasis is on balancing public dose and disposal cost, supporting the responsible and compliant release or disposal of such concrete while ensuring public safety and adherence to regulatory standards.

This standard addresses both surface and volumetric radioactive contamination in concrete with well-characterized history and geometry. It's particularly valuable for facilities where large volumes of concrete are involved and where contamination may be shallow or limited in depth, making partial decontamination and potential release feasible.

Key Topics

• Concrete Applicability: Focuses on concrete still in place with defined geometry and documented history. Not intended for already rubbelized concrete or rebar embedded within the concrete, as these present unique measurement and contamination control challenges.
• Contamination Types: Covers both surface and volumetrically contaminated concrete, provided the contamination depth can be measured or reasonably estimated.
• 10-Step Evaluation Process: Outlines a methodology that includes characterization, regulatory guideline determination, cost-risk analysis, and final approval steps for releasing or disposing of concrete.
• Dose and Cost Analysis: Recommends evaluating each disposal option for public radiation dose and cost implications. Methodologies and default data for such calculations are included, with encouragement to use site-specific data where available.
• Regulatory Compliance: Ensures all decisions comply with applicable standards, including requirements for verifying regulatory criteria before release, and documenting all procedures for transparency.
• Exclusions: Does not cover concrete reinforcement bar (rebar) or decommissioned concrete already reduced to rubble, and does not focus on occupational exposure for workers who are already within a formal radiation protection program.
• Decision Support: Results can be used to justify compliance with existing release criteria, support site-specific release requests, or even develop new release criteria where none exist.

Applications

• Decommissioning Planning: Essential for project managers, environmental engineers, and regulatory compliance officers planning the closure or repurposing of nuclear facilities with significant concrete structures.
• Public and Environmental Safety: Supports calculation of estimated doses to nonradiation workers and future site residents, optimizing for options that minimize public risk.
• Regulatory Submissions: Provides detailed, auditable documentation necessary for approvals from oversight agencies. Facilitates the release of decommissioned concrete only when all regulatory requirements are met.
• Cost Management: Offers a framework for transparent cost assessment, allowing nuclear facility operators to select disposal or release strategies that optimize cost-efficiency and safety.

Common scenarios addressed by ASTM E2216 include:

• Justifying the unrestricted release of lightly contaminated concrete after appropriate decontamination
• Evaluating the option of reusing concrete as backfill or construction material after confirming contamination is within regulatory limits
• Supporting case-by-case proposals for concrete release when default guidelines are inapplicable or absent
• Site-specific tailoring of disposal strategies using real data on contamination and cost

Related Standards

When implementing ASTM E2216-02(2020), the following standards and guidance documents are often relevant:

• ASTM E1760: Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• ASTM E1278: Guide for Radioactive Pathway Methodology for Release of Sites Following Decommissioning
• ANSI/HPS N13.12: Surface and Volume Radioactivity Standards for Clearance
• U.S. NRC Regulatory Guide 1.86: Termination of Operating Licenses for Nuclear Reactors
• DOE G 441.1-1B / DOE Order 5400.5: Radiation Protection of the Public and the Environment
• ISO 7503 Series: Methods for Evaluation of Surface Contamination
• IAEA Safety Series No. 111-P-1.1: Application of Exemption Principles to the Recycle and Reuse of Materials From Nuclear Facilities

These resources provide supplementary methodologies, definitions, or criteria that support the safe, standardized management of contaminated concrete from nuclear decommissioning projects.

Keywords: nuclear facility decommissioning, contaminated concrete disposal, ASTM E2216, radioactive waste management, public radiation dose, regulatory compliance, concrete characterization, cost analysis, decontamination, environmental safety.

Standards Content (Sample)

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.
Designation: E2216 − 02 (Reapproved 2020)
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 July 1, 2020. Published July 2020. Originally approved
in 2002. Last previous edition approved in 2013 as E2216–02(2013). DOI: The boldface numbers in parentheses refer to a list of references at the end of
10.1520/E2216-02R20. this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E2216 − 02 (2020)
addition, Guide E1278 provides a general process for analyz- MeV) and Alpha Emitters
ing radioactive pathways. This standard guide is intended for ISO-7503-2 Evaluation of Surface Contamination—Part 2:
use in conjunction with Guides E1760 and E1278, and pro- Tritium Surface Contamination
vides a more detailed approach for the release of concrete. ISO-7503-3 Evaluation of Surface Contamination—Part 3:
Isomeric Transition and Electron Capture Emitters, Low
1.4 This international standard was developed in accor-
Energy Beta Emitters (E <0.15 MeV)
Bmax
dance with internationally recognized principles on standard-
2.5 DOE Standards:
ization established in the Decision on Principles for the
DOE G 441.1–1B Radiation Protection Programs Guide,
Development of International Standards, Guides and Recom-
Order 5400.5 Radiation Protection of the Public and the
mendations issued by the World Trade Organization Technical
Environment, as amended
Barriers to Trade (TBT) Committee.
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
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-
ciplestotheRecycleandReuseofMaterialsfromNuclear
cess used for radiation protection to manage and control
Facilities exposures(bothindividualandcollectivetotheworkforceand
IAEA-TECDOC-855 ClearanceLevelsforRadionuclidesin
tothegeneralpublic)andreleasesofradioactivematerialtothe
Solid Materials environment so that the levels are as low as is reasonable
2.4 ISO Standards: taking into account social, technical, economic, practical, and
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
contamination can result from neutron activation or from the
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
penetration of radioactive contamination into cracks or interior
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
surfaces within the interior matrix of an item. ANSI/HPS
Standards volume information, refer to the standard’s Document Summary page on
N13.12
the ASTM website.
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 (2020)
4. Significance and Use 5.2.10 Release property.
4.1 This standard guide applies to concrete that is still in 5.3 Characterize Property and Prepare a Description:
placewithadefinedgeometryandknown,documentedhistory.
5.3.1 Document the concrete’s physical and radiological
characteristics, including history. The concrete’s history and
4.2 It is not intended for use on concrete that has already
condition can be used to estimate the depth of penetration of
been rubbelized where it is difficult to measure the radiation
radioactive contamination, or this can be measured. Radiologi-
levels and not easy to remove surface contamination to reduce
cal surveys must be done to determine the isotopes and level of
radiation levels after concrete has been rubbelized.
radioactive contamination on the surface of the concrete.
4.3 This standard guide applies to surface or volumetrically
5.4 Determine Whether Authorized Release Guidelines Al-
contaminated concrete, where the depth of contamination can
ready Exist:
be measured or estimated based on the history of the concrete.
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
be used to estimate the ramifications of each disposal option,
4.6 This standard guide helps determine estimated doses to
select the best disposal option, and then apply for approval to
thepublicduringdisposalofconcreteandtofutureresidentsof
releasethematerialbasedonthesedata.Suchreleasescouldbe
disposal areas. It does not include dose to radiation workers
doneonacase-by-casebasis,ortosetanewauthorizedrelease
already involved in a radiation control program. It is assumed
limit.
that the dose to radiation workers is already tracked and kept
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;
5.5.1.2 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
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
dose and cost for each action in the disposal option. Then sum
for Concrete at U.S. Department of Energy Sites” (1) and also
for this guide. the dose and cost from all of the applicable actions to find the
total dose and cost for that disposal option.
5.2.1 Characterize property and prepare a description;
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.
E2216 − 02 (2020)
5.6.3 After completing a detailed analysis of the estimated 5.11 Verify that Applicable Authorized or Supplemental
dose and cost for each option, compare the results and choose Guidelines Have Been Met:
the best option. The best option is likely to be the one that
5.11.1 Compare the survey results with the release guide-
meets regulatory guidelines while reducing dose and cost. The
lines to verify that the release guidelines have been met and
data can be used to support release of the concrete if release
document the results.
guidelines already exist. If release guidelines do not exist, the
5.12 Release Material:
data can be used to establish a basis to request release of the
concrete either on a case-by-case basis or to set new release
5.12.1 Before releasing the concrete, verify that all of the
guidelines.
applicable regulations and procedures have been met. When
compliance with all requirements has been verified and
5.7 Compile and Submit an Application for Approval to
documented, the concrete may be released under direction of
Release Material:
the governing regulatory agencies.
5.7.1 Present the results of the analysis for the chosen
alternative to the governing regulatory agencies to request
permission to release the concrete. Document any limitations 6. Quality Assurance
or restrictions on the use of the concrete (such as decontami-
6.1 This standard guide addresses release of concrete that
nation to a certain level), and any comments or recommenda-
was previously radioactively contaminated, so quality assur-
tionsbyfederal,state,orregulatoryagenciesintheapplication.
ance principles and methods should be applied both in the
In addition, attach the survey procedures and results to the
initial surveys and data collection, and in estimating the dose
application.
and cost of disposal options. Care should be taken to ensure
5.8 Document the Approved Guidelines in the Public Re-
thatallworkisdoneaccordingtoappropriatequalityassurance
cord:
methods and procedures. These quality assurance procedures
5.8.1 Document the planned release of concrete in the
should be established before initiating the calculations con-
public record to provide the public with information about
tained in the appendices. Quality assurance procedures are
radiation levels and expected dose.
especially important when using site-specific data for the
5.9 Implement the Approved Guidelines:
calculations in Appendix X1.
5.9.1 Once the governing regulatory agencies approve the
release, the approved guidelines can be implemented. This
7. Use of the Appendices
should be done in compliance with all required regulations and
site specific procedures and requirements. 7.1 Appendix X1 through Appendix X5 provide details
about how to complete step 5.6 to estimate the dose and cost
5.10 Conduct Surveys/Measurements:
for various disposal options. The methodology and formulas
5.10.1 Conduct radiological surveys to show that the con-
are presented in Appendix X1, while Appendix X2 through
crete meets applicable release guidelines. Previously con-
Appendix X5 provide unit-dose factors, unit-cost factors, and
ducted surveys can be used if the documentation is sufficient to
other data that can be used in the formulas. After using the
meet regulatory requirements. Documentation should show
methodology and data in the appendices to complete step 5.6,
that surveys were done according to site-specific procedures
and should include survey results. Guidelines such as Guide the resulting estimates of dose and cost can be used to select
E1893 may provide useful information about conducting the best disposal option and proceed through the remaining
surveys. steps of the process.
APPENDIXES
(Nonmandatory Information)
X1. METHODOLOGY TO ESTIMATE DOSE AND COST FOR DISPOSAL OPTIONS FOR CONCRETE FROM D&D OF
NUCLEAR FACILITIES
INTRODUCTION
Adapted from the Argonne report, “Protocol for Development of Authorized Release Limits for
Concrete of U.S. Department of Energy Sites,” (1).
X1.1 These sections describe the methodology used to subsets of these general options. The options may include:
estimate the costs and nonradiation worker doses for the
X1.1.1 Decontaminate, dispose of all low-level radioactive
disposal options. Seven general options are described here.
waste (LLW), crush and reuse as roadbed material.
Other options may be feasible, and can usually be analyzed as
E2216 − 02 (2020)
X1.1.2 Crush without decontamination and reuse as road- spots exist. If significant variations of source throughout the
bed material. mass or in the surface distribution exist, these should be taken
into account with more detailed analysis and calculations.
X1.1.3 Decontaminate, dispose of all LLW, demolish, and
Radiologicaldosesareestimatedonlyfornonradiationworkers
dispose of the decontaminated material as construction debris,
(that is, workers not already part of a radiation protection
or reuse as backfill.
program). Although doses for radiation workers are not in-
X1.1.4 Demolish, without decontamination and either dis-
cluded here, they should be added when comparing the
pose as construction debris, or reuse it as backfill.
comprehensive cost and dose for each option. For the cost
components, if site-specific or process-specific costs are
X1.1.5 Demolish without decontamination and dispose of
all materials as LLW. available, then those values should be used instead of the
unit-cost factors presented in this document.
X1.1.6 Decontaminate the structure and reuse.
X1.1.7 Demolish with or without decontamination and en-
X1.3 Decontamination—For contaminated concrete
tomb the demolished material.
materials,decontaminationcanremovetheamountofcontami-
nation on the material. In general, contaminants are less likely
X1.2 For each of the options, one or more of the following
to migrate into the concrete when the surface is painted or
individual actions may apply:
coated. In dry areas, contaminant migration into unpainted
X1.2.1 Decontamination;
concrete will probably be limited to the top ⁄4 in. If the
concrete has been exposed to contaminated liquids for long
X1.2.2 Demolition/crushing;
periods, or is cracked, the contaminants may migrate farther
X1.2.3 Packaging/transportation;
into the concrete matrix. The process rates and costs for
X1.2.4 Reuse; and
decontamination can vary greatly because of the large number
of factors that affect technology efficiency and effectiveness.A
X1.2.5 Disposal/entombment.
common technique for removing fixed contamination from
X1.2.6 The dose and cost calculation methods for each
concrete walls and floors is the use of hand-held or automated
action are discussed in the individual sections of this appendix.
scabbling units. These units mechanically remove a thin layer
To find the total nonradiation worker dose for each disposal
1 1
( ⁄8 to ⁄4 in.) from the surface of the concrete. Another
option, the dose and cost for all applicable actions need to be
commonly used technique for removing loose contamination is
summed. Table X1.1 provides a list of the options and the
spraying the surface with a nontoxic cleaner and wiping,
applicable sections of this appendix for estimating the costs
although strippable coatings have also been used with success.
and associated radiological doses.
The use of water and abrasive blasting is limited because of
X1.2.7 The costs or radiological doses (when applicable) problems with handling the waste that is generated. For each
can be estimated by using unit-cost or unit-dose factors. The decontamination method considered, the decontamination
efficiency, volume of waste generated, and cost need to be
unit-costfactorswereobtainedfromsuchsourcesasRefs(2, 3)
and (4) and others. The unit-cost factors for the applicable calculated. The decontamination efficiency will be used to
sections are provided in the individual sections and in Appen- estimate the dose from reuse or disposal. The volume of waste
dix X2 through Appendix X5. Unit-dose factors are used to generated will be used to estimate the transportation and
estimate the radiological doses to members of the public from disposalcosts.Itisassumedthatthedecontaminationworkeris
the reuse or disposal of concrete materials. These factors were already part of an ALARA program, so this dose is not
generatedwithasuiteofcomputercodessuchasRESRAD(5), included here. To support completion of the formulas in the
RESRAD-BUILD (6), RESRAD-RECYCLE (7), TSD-DOSE decontamination module, Appendix X2 has unit operational
(8) and RISKIND (9). The unit-dose factors are presented in cost, production rates, and waste generation information for
Appendix X2 through Appendix X5 and discussed in the some decontamination methods. The waste from decontamina-
specific sections below. These calculations assume that source tion activities will be disposed of in a LLW radioactive
distribution throughout the mass is uniform, and that no hot disposal site.
TABLE X1.1 Concrete Disposal Options and the Corresponding Cost and Dose Assessment Sections
Options Appendix Sections
Decontaminate the concrete material, dispose of all LLW, and Decontamination, Demolition/Crushing, Packaging/Transportation,
crush and reuse the decontaminated material Reuse, and Disposal
Crush and reuse the concrete without decontamination Demolition/Crushing, Packaging/Transportation, and Reuse
Decontaminate the concrete, dispose of all LLW, demolish the Decontamination, Demolition/Crushing, Packaging/Transportation,
structure, and dispose of the decontaminated material as Reuse, and Disposal
construction debris (nonradiological landfill) or reuse as backfill
Demolish the structure and dispose of the concrete material as Demolition/Crushing, Packaging/Transportation, Reuse, and
construction debris or reuse as backfill (nonradiological Disposal
landfill—no decontamination)
Demolish the structure and dispose of all materials as LLW Demolition/Crushing, Packaging/Transportation, and Disposal
Decontaminate the building and reuse as office space Decontamination, Packaging/Transportation, Reuse, and Disposal
Demolish the building and entomb on-site Demolition/Crushing, and Disposal/Entombment
E2216 − 02 (2020)
X1.3.1 Decontamination Effıciency—Decontamination effi- X1.3.2.1 For fixed contamination, decontamination is per-
ciency (D ), a measure of the amount of contamination left formed by physically removing layers of concrete. Hence the
EF
after decontamination, must be estimated so that the dose from total amount of waste generated is estimated as:
eitherreuseordisposalafterdecontaminationcanbeestimated.
WasteGen 5 Area 3RR 3P1Other (X1.4)
The decontamination efficiency is defined here to be the
where:
inverse of the decontamination factor (DF) (that is,
D =1⁄DF). The D value of 0 is interpreted as meaning all RR = removal rate (thickness/pass), and
EF EF
P = number of passes or treatments.
radioactive material has been removed from the surface of the
concrete material; the D value of 1 means no decontamina-
EF
X1.3.2.2 If a concrete structure is decontaminated with
tion was performed. Generally, decontamination is limited to
abrasive blasting, the total amount of waste generated is a
surface-contaminated concrete materials; hence, for most acti-
combination of both factors and is therefore estimated as:
vated volumetrically contaminated concrete, the decontamina-
WasteGen 5 Area 3 @~RR 3P !1WGR#1Other (X1.5)
tion efficiency should be set equal to 1.
X1.3.1.1 If field measurements are available, the decon-
Appendix X2 provides the waste generation rates for some
tamination efficiency is derived in the following manner:
decontamination technologies.
A
Final
X1.3.3 Decontamination Costs—Threecomponentsmustbe
D 5 (X1.1)
EF
A
Initial
considered in estimating the cost for the decontamination
technologies: (1) amortization cost for the equipment, (2)
where:
process costs, and (3) labor costs.The amortization cost for the
A = total activity, dpm/100 cm , after decontamination,
Final
equipment takes into account the cost of purchasing the
and
decontamination equipment, the equipment life, and the inter-
A = total activity, dpm/100 cm , prior to
Initial
est rate. The process cost is the cost of operating the
decontamination.
equipment, which may include supplies required to run the
X1.3.1.2 If no field measurements are available, the decon-
equipment or may include costs for routine maintenance. The
tamination efficiency can be estimated for contamination dis-
labor costs are the costs associated with workers using the
tributeduniformlythroughoutagiventhicknessoftheconcrete
decontamination equipment.Although other costs may also be
material as:
associated with decontamination, only these costs are consid-
RR
ered here because they would contribute the most to the total
D 5 1 2 3P (X1.2)
F S D G
EF
T
C cost associated with decontamination activities. The hourly
amortization cost (EC), over the life of the equipment is given
where:
as:
D = decontamination efficiency applied to all isotopes,
EF
N
PI ~11I! 1
RR = removal rate, thickness/pass,
EC 5 3 (X1.6)
F G
N
11I 2 1 8760
P = number of passes or treatments, and $~ ! %
T = thickness of the contamination.
C
where:
X1.3.1.3 Appendix X2 lists some decontamination tech-
P = purchase cost of the equipment,
nologies for both loose and fixed contamination and provides
I = interest rate,
estimated parameter values for the removal rate.
N = equipment life, yr, and
1/8760 = conversion from per year to per h.
X1.3.2 Waste Generation—The total amount of waste gen-
eratedduringdecontaminationisusedasinputwhenestimating
X1.3.3.1 The total cost for decontamination operations is
the cost associated with the transportation of the decontamina-
estimated as:
tion wastes to a LLW disposal facility. For decontamination
technologies that provide a waste generation rate in units of
Decon$ 5 EC 3UT 3A 3P 3 PC1 3HC (X1.7)
S D
PR
cubicfeetofwastegeneratedpersquarefootofmaterialtreated
3 2
(ft /ft ), the total amount of waste generated is estimat
...