ASTM E2421-05
(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
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.
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.
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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation:E2421–05
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. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope Data Quality Objectives
E1892 Guide for Preparing Characterization Plans for De-
1.1 This guide addresses the development of waste manage-
commissioning Nuclear Facilities
ment plans for potential waste streams resulting from decom-
E1893 Guide for Selection and Use of Portable Radiologi-
missioningactivitiesatnuclearfacilities,includingidentifying,
calSurveyInstrumentsforPerformingInSituRadiological
categorizing, and handling the waste from generation to final
Assessments to Support Unrestricted Release from Further
disposal.
Regulatory Controls
1.2 This guide is applicable to potential waste streams
2.2 Code of Federal Regulations:
anticipated from decommissioning activities of nuclear facili-
10 CFR 60 Disposal of High-Level Radioactive Wastes in
ties whose operations were governed by the Nuclear Regula-
Geologic Repositories
tory Commission (NRC) or Agreement State license, under
10 CFR 61 Licensing Requirements for Land Disposal of
Department of Energy (DOE) Orders, or Department of De-
Radioactive Waste
fense (DoD) regulations.
10 CFR 71 Packaging and Transportation of Radioactive
1.3 This guide provides a description of the key elements of
Materials
waste management plans that if followed will successfully
10 CFR 830.120 Quality Assurance Requirements
allow for the characterization, packaging, transportation, and
29 CFR 1910.120 Hazardous Waste Operations and Emer-
off-site treatment or disposal, or both, of conventional, hazard-
gency Response
ous, and radioactive waste streams.
40 CFR 261 Identification and Listing of Hazardous Waste
1.4 This guide does not address the on-site treatment, long
40 CFR 262 StandardsApplicable to Generators of Hazard-
term storage, or on-site disposal of these potential waste
ous Waste
streams.
40 CFR 761 Polychlorinated Biphenyls (PCBs) Manufac-
1.5 This standard does not purport to address all of the
turing, Processing, Distribution in Commerce, and Use
safety concerns, if any, associated with its use. It is the
Prohibitions
responsibility of the user of this standard to establish appro-
40 CFR 763 Asbestos
priate safety and health practices and determine the applica-
49 CFR 172 Hazardous MaterialsTable, Special Provisions,
bility of regulatory limitations prior to use.
Hazardous Materials Communications, Emergency Re-
2. Referenced Documents sponse Information, and Training Requirements
49 CFR 173 Shippers—General Requirements for Ship-
2.1 ASTM Standards:
ments and Packagings
D5283 Practice for Generation of Environmental Data Re-
49 CFR 397 Transportation of Hazardous Materials; Driv-
lated to Waste Management Activities: Quality Assurance
ing and Parking Rules
and Quality Control Planning and Implementation
2.3 DOE Documents:
D5792 Practice for Generation of Environmental Data Re-
DOE Order 460.1A Packaging and Transportation Safety
lated to Waste Management Activities: Development of
DOE Order 460.2 Departmental Materials Transportation
and Packaging Management
DOE Order 474.1 Control and Accountability of Nuclear
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Materials
Technology and Applications and is the direct responsibility of Subcommittee
DOE Order 414.1A Quality Assurance
E10.03 on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
DOE Manual M 435.1-1 Radioactive Waste Management
Current edition approved Jan. 1, 2005. Published February 2005. DOI: 10.1520/ 3
2.4 United States Code:
E2421-05.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
the ASTM website. 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.
E2421–05
United States Code, Title 42, Section 2014 greater than 20 years and in concentrations greater than 100
4 -1 -7
2.5 USACE Documents: nanocuriespergram(3.7kBqg )(1310 Ci/g)(DOEManual
Engineering Manual EM 385-1-1.06E Ionizing Radiation (3 M 435.1-1).
Nov. 2003)
5.1.3 By-Product Material—By-product material wastes are
Radiation Protection Manual EM 385-1-80 (30 May 1997)
any radioactive material (except special nuclear material)
2.6 Other Documents:
yielded in or made radioactive by exposure to the radiation
ASME Quality Assurance Requirements for Nuclear Facil-
incident to the process of producing or utilizing special nuclear
ity Applications material, and the tailings or wastes produced by the extraction
EPAQA/R-2 Requirements for Quality Management Plans
or concentration of uranium or thorium from any ore processed
EPA QA/G-4 Guidance for Data Quality Objectives primarily for its source material content (42 U.S.C. 2014(e)).
NQA-1-2000 American Society of Mechanical Engineers,
5.1.4 Naturally Occurring and Accelerator Produced Ra-
dioactive Materials:
5.1.4.1 NORM (Naturally Occurring Radioactive
3. Terminology
Material)—Any material that contains naturally occurring
3.1 Definitions: radionuclides. By-product material and the natural radioactiv-
3.1.1 documents—instructions, procedures and drawings ity of rocks, soils, or background radiation are not to be
that control policy, administrative, and technical information. included (DOE Manual M 435.1-1).
3.1.2 records—electronic, written, printed, microfilm, pho-
5.1.4.2 NARM (Naturally Occurring or Accelerator Pro-
tographs,radiographs,oropticaldisksthatcontaindatathatare
duced Radioactive Material)—Any material that contains
retained for their future value.
NORM or accelerator-produced radioactive materials.
3.1.3 waste acceptance requirements—criteria and all other
5.1.4.3 TENORM (Technologically Enhanced Naturally Oc-
requirements that a facility receiving waste for treatment,
curring Radioactive Materials)—NORM whose composition,
storage, or disposal must meet to receive waste.
radionuclide concentrations, availability, or proximity to man
3.1.4 waste acceptance criteria—the technical and admin-
have been increased by or because of human practices.
istrative criteria that a waste must meet to be accepted at a
5.1.5 Low Level—Low level wastes are radioactive wastes
treatment, storage, or disposal facility.
that are not spent fuel, high level radioactive wastes, transu-
ranic radioactive wastes, by-product material, or naturally
4. Significance and Use
occurring radioactive materials. Low level wastes are defined
4.1 Awaste management plan based on the contents of this into categories per 10 CFR 61.55(a)(2)(i) and accompanying
guide will provide for the successful identification of potential tables. Those categories include:
waste streams anticipated from decommissioning activities,
5.1.5.1 Class A—ClassAwastes contain the lowest concen-
and provide a clear and concise methodology for the handling
trations of radioactivity and typically are composed of short-
of identified waste from generation to final disposition.
lived radionuclides that generate no decay heat, do not need to
4.2 The waste management plan will identify the general
be shielded, and decay to levels posing minimal potential
waste types, characterization, packaging, transportation, dis-
human dose within 100 years. ClassAwastes typically have an
-3 -3
posal, and quality assurance requirements for potential waste
average concentration less than 100 GBq m (2.7 Ci m ) and
streams.
constitute the majority of generated radioactive waste.
5.1.5.2 Class B—Class B wastes contain the next lowest
5. General Waste Types
concentrations of radioactivity and typically are composed of
greater quantities of short-lived radionuclides than Class A.
5.1 Radioactive—Radioactive wastes are defined as dis-
Class B wastes typically have an average concentration of 3
carded material in any form that must be managed for its
-3 -3
TBq m (81 Ci m ).
radioactive content per federal or agreement state regulations.
5.1.5.3 Class C—Class C wastes contain the highest con-
Radioactive wastes are further categorized into the following
subclasses. centrations of radioactivity acceptable for near-surface dis-
5.1.1 High Level—High level wastes are irradiated reactor posal. Class C wastes are typically composed of greater
fuel (spent nuclear fuel) and the highly radioactive material concentrations of short-lived radionuclides than Class A or B
resulting from the reprocessing of irradiated reactor fuel, wastes, and may contain long-lived radionuclides. Class C
-3
including liquid waste and any solid material derived from wastes on average have a concentration of 9 TBq m (243 Ci
-3
such liquid (10 CFR 60, DOE Manual M 435.1-1). m ) and will not decay to acceptable levels within 100 years.
5.1.2 Transuranic—Transuranic wastes are any material
5.1.5.4 Greater Than Class C—Greater Than Class C
containing alpha-emitting transuranic nuclides with half-lives
wastes are all radioactive wastes, defined as low level wastes,
that do not qualify for near-surface disposal as defined in 10
CFR 61.
5.2 Hazardous—Hazardous wastes are solid wastes as de-
United States Army Corps of Engineers, USACE Publications Depot, ATTN:
CEIM-IM-PD, 2803 52nd Ave., Hyattesville, MD 20781-1102.
fined in 40 CFR 261 that meet any one of the following four
Available from American Society of Mechanical Engineers, ASME, ASME
criteria:
International Headquarters, Three Park Ave., New York, NY 10016-5990.
5.2.1 Exhibits a characteristic such as ignitable, corrosive,
U.S. Environmental Protection Agency, Quality Staff (281 1R), 1200 Pennsyl-
vania Ave., NW, Washington, DC 20460. E-mail: quality@epa.gov reactive, or toxic as defined in 40 CFR 261, Subpart C,
E2421–05
5.2.2 Is identified as a listed waste under the F, K, P, or U also checks for completeness, consistency, comparability, and
lists as defined in 40 CFR 261, Subpart D, correctness of the data set.
5.2.3 Is composed of a mixture of a solid waste and a listed (1) Averification report should be generated that identifies
waste as defined in 40 CFR 261.3(b), or any correctable and non-correctable discrepancies associated
5.2.4 Is a derived waste from the treatment, storage, or with the data set.The report should be in a standard format and
remain as part of the data package.
disposal of a listed waste as defined in 40 CFR 261.3(c)(2)(i).
5.3 Mixed Waste—Mixed Waste containing a RCRA haz- (2) Data verification should be an interactive process with
ardous material and an NRC regulated radioactive material. the laboratory. It should provide appropriate feedback to
5.4 Co-mingled Waste—Waste containing any CERCLA address correctable and non-correctable discrepancies which
result in opportunities to improve the analytical work prior to
hazardous substance other than the CERCLA radioactive
project completion.
hazardous substances and any radioactive materials.
5.5 PCB—Polychlorinated Biphenyl (PCB) wastes are 6.2.3.2 Validation is a systematic process performed exter-
nally from the data generator that addresses the reliability of
PCBs and PCB items that are subject to the disposal require-
ments of 40 CFR 761, Subpart D. the data and provides assurance of the presence or absence of
analytes. This process reviews the verification report, and
5.6 Conventional—Conventional wastes are any non-
hazardous discarded material in any form that does not contain laboratory-delivereddataset,andappliesdefinedperformance-
based criteria to qualify the data.
residual amounts of radioactivity above the limits of the
treatment or disposal facility. (1) A data validation report should be generated that
identifies all data qualified based on the performance-based
criteria. The report should be in a standardized format and
6. Characterization
remain as part of the data package.
6.1 The waste management plan should include a descrip-
6.2.3.3 Thedataqualityassessmentprocessisthe“scientific
tion of the waste characterization methodology. The waste
and statistical evaluation of data to determine if they are of the
characterization methodology should be of sufficient detail to
right type, quality, and quantity to support their intended use.”
ensure that physical, chemical, and radiological properties of
This process should not be limited to the verification and
the wastes are identified and known throughout the waste
validation of data, but should encompass the entire sample
management process and that they are characterized with
collection and analysis process and its impact on data quality
sufficient accuracy to ensure worker protection, proper segre-
and usability.
gation, treatment, storage, and disposal. Useful information
(1)Agradedapproachbasedontheintendeduseofthedata
relative to the characterization of waste streams can be found
should be applied to the data quality assessment process. This
in Guide E1892. Waste characterization methodologies should
should be done in such a manner that the three fundamental
focus on total data acquisition and be based on direct methods
premises are satisfied:
(surveys and sampling and analysis), and indirect methods
(a) Are the samples representative?
(process knowledge). Characterization data should include
(b) Are the data accurate?
information obtained from direct measurement, and from
sampling and analysis of the waste materials. Guidance on (c) Can a decision be made?
direct measurement is contained in Guide E1893. 6.3 Process Knowledge—A characterization methodology
that relies on the knowledge of the physical, chemical, and
6.2 Sampling and Analysis—The sampling and analysis of
waste streams should be conducted in accordance with a radiological constituents of the materials associated with the
waste generation process.
written plan that identifies the data life cycle process. The data
life cycle process is composed of three essential elements: 6.3.1 Process knowledge can be derived from Material
planning, implementation, and assessment. Safety Data Sheets, historical analytical data, historic records,
living memory, system descriptions, plans and drawings,
6.2.1 Planning—The planning process is a project manage-
ment tool that identifies an
...
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