ASTM E2421-15(2021)
(Guide)Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities
Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities
SIGNIFICANCE AND USE
4.1 A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition.
4.2 The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.
SCOPE
1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.
1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.
1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.
1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.
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.
General Information
Relations
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: E2421 − 15 (Reapproved 2021)
Standard Guide for
Preparing Waste Management Plans for Decommissioning
Nuclear Facilities
This standard is issued under the fixed designation E2421; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2. Referenced Documents
2.1 ASTM Standards:
1.1 Thisguideaddressesthedevelopmentofwastemanage-
D5283Practice for Generation of Environmental Data Re-
ment plans for potential waste streams resulting from decom-
lated to Waste ManagementActivities: QualityAssurance
missioningactivitiesatnuclearfacilities,includingidentifying,
and Quality Control Planning and Implementation
categorizing, and handling the waste from generation to final
D5792Practice for Generation of Environmental Data Re-
disposal.
lated to Waste Management Activities: Development of
1.2 This guide is applicable to potential waste streams Data Quality Objectives
anticipated from decommissioning activities of nuclear facili- E1892Guide for Preparing Characterization Plans for De-
commissioning Nuclear Facilities
ties whose operations were governed by the Nuclear Regula-
tory Commission (NRC) or Agreement State license, under 2.2 Code of Federal Regulations:
10 CFR 60Disposal of High-Level Radioactive Wastes in
Department of Energy (DOE) Orders, or Department of De-
Geologic Repositories
fense (DoD) regulations.
10 CFR 61Licensing Requirements for Land Disposal of
1.3 Thisguideprovidesadescriptionofthekeyelementsof
Radioactive Waste
waste management plans that if followed will successfully
10 CFR 71Packaging and Transportation of Radioactive
allow for the characterization, packaging, transportation, and
Materials
off-site treatment or disposal, or both, of conventional,
10 CFR 830.120Nuclear Safety Management, Subpart A,
hazardous, and radioactive waste streams.
“Quality Assurance Requirements”
29 CFR Subpart H, “Hazardous Materials: Section
1.4 This guide does not address the on-site treatment, long
1910.120, “Hazardous Waste Operations and Emergency
term storage, or on-site disposal of these potential waste
Response”
streams.
40 CFR 261Identification and Listing of Hazardous Waste
1.5 This standard does not purport to address all of the
40 CFR 262StandardsApplicable to Generators of Hazard-
safety concerns, if any, associated with its use. It is the ous Waste
responsibility of the user of this standard to establish appro-
40 CFR 761 Polychlorinated Biphenyls (PCBs)
priate safety, health, and environmental practices and deter- Manufacturing, Processing, Distribution in Commerce,
mine the applicability of regulatory limitations prior to use. and Use Prohibitions
40 CFR 763Asbestos
1.6 This international standard was developed in accor-
49 CFR 172Hazardous Materials Table, Special Provisions,
dance with internationally recognized principles on standard-
Hazardous Materials Communications, Emergency Re-
ization established in the Decision on Principles for the
sponse Information, and Training Requirements
Development of International Standards, Guides and Recom-
49 CFR 173Shippers—General Requirements for Ship-
mendations issued by the World Trade Organization Technical
ments and Packagings
Barriers to Trade (TBT) Committee.
49CFR397TransportationofHazardousMaterials;Driving
and Parking Rules
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee For referenced ASTM standards, visit the ASTM website, www.astm.org, or
E10.03 on Radiological Protection for Decontamination and Decommissioning of contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Nuclear Facilities and Components. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Feb. 1, 2021. Published February 2021. Originally the ASTM website.
approved in 2005. Last previous edition approved in 2015 as E2421-15. DOI: AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
10.1520/E2421-15R21. 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E2421 − 15 (2021)
2.3 DOE Documents: radioactive content per federal or agreement state regulations.
DOE Order 460.1APackaging and Transportation Safety Radioactive wastes are further categorized into the following
DOE Order 460.2ADepartmental Materials Transportation subclasses.
and Packaging Management
5.1.1 High Level—High level wastes are irradiated reactor
DOE Order 414.1CQuality Assurance
fuel (spent nuclear fuel) and the highly radioactive material
DOE Manual M 435.1-1Radioactive Waste Management
resulting from the reprocessing of irradiated reactor fuel,
Manual
including liquid waste and any solid material derived from
such liquid (10 CFR 60, DOE Manual M 435.1-1).
2.4 United States Code:
USC 2014Definitions
5.1.2 Transuranic—Transuranic wastes are any material
containing alpha-emitting transuranic nuclides with half-lives
2.5 NRC Standards and Guides:
greater than 20 years and in concentrations greater than 100
NUREG-1575Multi-Agency Radiation Survey and Site In-
-1 -7
nanocuriespergram(3.7kBqg )(1×10 Ci/g)(DOEManual
vestigation Manual (MARSSIM)
M 435.1-1).
NUREG-1575, Supplement 1Multi-Agency Radiation Sur-
5.1.3 By-Product Material—By-product material wastes are
vey and Assessment of Materials and Equipment (MAR-
SAME) any radioactive material (except special nuclear material)
yielded in or made radioactive by exposure to the radiation
NUREG-1576Multi-Agency Radiologial Laboratory Ana-
lytical Protocols (MARLAP) incidenttotheprocessofproducingorutilizingspecialnuclear
material, and the tailings or wastes produced by the extraction
2.6 Other Documents:
orconcentrationofuraniumorthoriumfromanyoreprocessed
EPAQA/R-2Requirements for Quality Management Plans
primarily for its source material content (42 USC 2014(e)).
EPA QA/G-4Guidance on Systematic Planning Using the
5.1.4 Naturally Occurring and Accelerator Produced Ra-
Data Quality Objectives Process
dioactive Materials:
NQA-1-2000American Society of Mechanical Engineers,
2008 5.1.4.1 NORM (Naturally Occurring Radioactive
Material)—Any material that contains naturally occurring
3. Terminology radionuclides. By-product material and the natural radioactiv-
ity of rocks, soils, or background radiation are not to be
3.1 Definitions:
included (DOE Manual M 435.1-1).
3.1.1 documents—instructions, procedures and drawings
5.1.4.2 NARM (Naturally Occurring or Accelerator Pro-
that control policy, administrative, and technical information.
duced Radioactive Material)—Any material that contains
3.1.2 records—electronic, written, printed, microfilm,
NORM or accelerator-produced radioactive materials.
photographs,radiographs,oropticaldisksthatcontaindatathat
5.1.4.3 TENORM (Technologically Enhanced Naturally Oc-
are retained for their future value.
curring Radioactive Materials)—NORM whose composition,
3.1.3 waste acceptance requirements—criteria and all other
radionuclide concentrations, availability, or proximity to man
requirements that a facility receiving waste for treatment,
have been increased by or because of human practices.
storage, or disposal must meet to receive waste.
5.1.5 Low Level—Low level wastes are radioactive wastes
3.1.4 waste acceptance criteria—the technical and admin-
that are not spent fuel, high level radioactive wastes, tran-
istrative criteria that a waste must meet to be accepted at a
suranic radioactive wastes, by-product material, or naturally
treatment, storage, or disposal facility.
occurring radioactive materials. Low level wastes are defined
into categories per 10 CFR 61.55(a)(2)(i) and accompanying
4. Significance and Use
tables. Those categories include:
4.1 Awaste management plan based on the contents of this
5.1.5.1 Class A—ClassAwastes contain the lowest concen-
guide will provide for the successful identification of potential
trations of radioactivity and typically are composed of short-
waste streams anticipated from decommissioning activities,
lived radionuclides that generate no decay heat, do not need to
and provide a clear and concise methodology for the handling
be shielded, and decay to levels posing minimal potential
of identified waste from generation to final disposition.
humandosewithin100years.ClassAwastestypicallyhavean
-3 -3
average concentration less than 100 GBq m (2.7 Ci m ) and
4.2 The waste management plan will identify the general
constitute the majority of generated radioactive waste.
waste types, characterization, packaging, transportation,
disposal, and quality assurance requirements for potential
5.1.5.2 Class B—Class B wastes contain the next lowest
waste streams.
concentrations of radioactivity and typically are composed of
greater quantities of short-lived radionuclides than Class A.
5. General Waste Types
Class B wastes typically have an average concentration of 3
-3 -3
TBq m (81 Ci m ).
5.1 Radioactive—Radioactive wastes are defined as dis-
5.1.5.3 Class C—Class C wastes contain the highest con-
carded material in any form that must be managed for its
centrations of radioactivity acceptable for near-surface dis-
posal. Class C wastes are typically composed of greater
concentrations of short-lived radionuclides than Class A or B
U.S. Environmental ProtectionAgency, Quality Staff (281 1R), 1200 Pennsyl-
vania Ave., NW, Washington, DC 20460. E-mail: quality@epa.gov wastes, and may contain long-lived radionuclides. Class C
E2421 − 15 (2021)
-3
wastes on average have a concentration of 9 TBq m (243 Ci quantitative statements that define the data quality objectives
-3
m ) and will not decay to acceptable levels within 100 years. process (for example, Practice D5792). A graded approach to
the planning process should be considered based on the size,
5.1.5.4 Greater Than Class C—Greater Than Class C
wastes are all radioactive wastes, defined as low level wastes, complexity, available resources, and level of quality control.
that do not qualify for near-surface disposal as defined in 10 6.2.2 Implementation—Sampling and analysis plans should
CFR 61.
identify the target analyte(s), the sampling design and meth-
odologyasdeterminedduringtheplanningprocess,thequality
5.2 Hazardous—Hazardous wastes are solid wastes as de-
control parameters, and the analytical requirements per the
fined in 40 CFR 261 that meet any one of the following four
approved statement of work.
criteria:
6.2.3 Assessment—The three-step assessment process is
5.2.1 Exhibits a characteristic such as ignitable, corrosive,
based on verification, validation, and data quality assessment.
reactive, or toxic as defined in 40 CFR 261, Subpart C,
6.2.3.1 Verificationisasystematicprocessperformedexter-
5.2.2 Is identified as a listed waste under the F, K, P, or U
nally from the data generator that evaluates the laboratory
lists as defined in 40 CFR 261, Subpart D,
delivereddataset(thatis,datapackage)againstthedeliverable
5.2.3 Is composed of a mixture of a solid waste and a listed
requirements as stated in the laboratory statement of work. It
waste as defined in 40 CFR 261.3(b), or
also checks for completeness, consistency, comparability, and
5.2.4 Is a derived waste from the treatment, storage, or
correctness of the data set.
disposal of a listed waste as defined in 40 CFR 261.3(c)(2)(i).
(1)Averification report should be generated that identifies
5.3 Mixed Waste—MixedWastecontainingaRCRAhazard-
any correctable and non-correctable discrepancies associated
ous material and an NRC regulated radioactive material.
withthedataset.Thereportshouldbeinastandardformatand
remain as part of the data package.
5.4 Co-mingled Waste—Waste containing any CERCLA
hazardous substance other than the CERCLA radioactive (2)Data verification should be an interactive process with
the laboratory. It should provide appropriate feedback to
hazardous substances and any radioactive materials.
address correctable and non-correctable discrepancies which
5.5 PCB—Polychlorinated Biphenyl (PCB) wastes are
result in opportunities to improve the analytical work prior to
PCBs and PCB items that are subject to the disposal require-
project completion.
ments of 40 CFR 761, Subpart D.
6.2.3.2 Validation is a systematic process performed exter-
5.6 Conventional—Conventional wastes are any non-
nally from the data generator that addresses the reliability of
hazardousdiscardedmaterialinanyformthatdoesnotcontain
the data and provides assurance of the presence or absence of
residual amounts of radioactivity above the limits of the
analytes. This process reviews the verification report, and
treatment or disposal facility.
laboratory-delivereddataset,andappliesdefinedperformance-
based criteria to qualify the data.
6. Characterization
(1)A data validation report should be generated that
identifies all data qualified based on the performance-based
6.1 The waste management plan should include a descrip-
criteria. The report should be in a standardized format and
tion of the waste characterization methodology. The waste
remain as part of the data package.
characterization methodology should be of sufficient detail to
6.2.3.3 Thedataqualityassessmentprocessisthe“scientific
ensure that physical, chemical, and radiological properties of
and statistical evaluation of data to determine if they are of the
the wastes are identified and known throughout the waste
right type, quality, and quantity to support their intended use.”
management process and that they are characterized with
This process should not be limited to the verification and
sufficient accuracy to ensure worker protection, proper
validation of data, but should encompass the entire sample
segregation, treatment, storage, and disposal. Useful informa-
collection and analysis process and its impact on data quality
tion relative to the characterization of waste streams can be
and usability.
found in Guide E1892. Waste characterization methodologies
(1)A graded approach based on the intended use of the
should focus on total data acquisition and be based on direct
data should be applied to the data quality assessment process.
methods (surveys and sampling and analysis), and indirect
This should be done in such a manner that the three funda-
methods (process knowledge). Character
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.