ASTM E1892-15(2021)
(Guide)Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
SIGNIFICANCE AND USE
5.1 Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information.
5.2 Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.
SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:
1.1.1 the data quality objective for characterization as an initial step in decommissioning planning.
1.1.2 sampling methods,
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and
1.1.4 essential documentation of the characterization information.
1.2 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.
1.3 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: E1892 − 15 (Reapproved 2021)
Standard Guide for
Preparing Characterization Plans for Decommissioning
Nuclear Facilities
This standard is issued under the fixed designation E1892; 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 E1167 Guide for Radiation Protection Program for Decom-
missioning Operations
1.1 This standard guide applies to developing nuclear facil-
E1281 Guide for Nuclear Facility Decommissioning Plans
ity characterization plans to define the type, magnitude,
2.2 ANSI Standard:
location, and extent of radiological and chemical contamina-
ANSI N323AB American National Standard for Radiation
tion within the facility to allow decommissioning planning.
Protection Instrumentation Test and Calibration, Portable
This guide amplifies guidance regarding facility characteriza-
Survey Instruments
tion indicated in ASTM Standard E1281 on Nuclear Facility
Decommissioning Plans. This guide does not address the
3. Terminology
methodology necessary to release a facility or site for uncon-
ditional use. This guide specifically addresses: 3.1 Definitions:
1.1.1 the data quality objective for characterization as an 3.1.1 characterization, n—a systematic identification of the
initial step in decommissioning planning. types, quantities, forms, and locations of contamination within
1.1.2 sampling methods, a facility.
1.1.3 the logic involved (statistical design) to ensure ad-
3.1.2 decommission, vt—to remove safely from service and
equate characterization for decommissioning purposes; and
to reduce residual contamination to a level that permits
1.1.4 essential documentation of the characterization infor-
termination of any applicable licenses and release of the
mation.
property for unrestricted use.
1.2 This standard does not purport to address all of the
3.1.3 decontamination, n—activitiesemployedtoreducethe
safety concerns, if any, associated with its use. It is the
levels of (radioactive or hazardous chemical) contamination in
responsibility of the user of this standard to establish appro-
or on structures, equipment, materials and personnel.
priate safety, health, and environmental practices and deter-
3.1.4 facility, n—as applied to a decommissioning project,
mine the applicability of regulatory limitations prior to use.
includes the structure and the soil around and under the
1.3 This international standard was developed in accor-
structure to an agreed upon distance.
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the
4. Requirements
Development of International Standards, Guides and Recom-
4.1 General:
mendations issued by the World Trade Organization Technical
4.1.1 As an initial part of facility decommissioning
Barriers to Trade (TBT) Committee.
planning, a characterization plan is developed to define the
nature, extent and location of contaminants, determine sam-
2. Referenced Documents
pling locations and protocols, determine quality assurance
2.1 ASTM Standards:
objectives for characterization, and define documentation re-
quirements. The characterization plan considers the historic
use of the facility to identify the likely contaminants due to the
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
radiological process involved, the chemicals introduced during
Technology and Applicationsand is the direct responsibility of Subcommittee
the processing, and any resulting contaminants that may be
E10.03 on Radiological Protection for Decontamination and Decommissioning of
formed during the processing. Records or recounting of any
Nuclear Facilities and Components.
Current edition approved Feb. 1, 2021. Published February 2021. Originally
process upsets or spills that may have occurred during the
approved in 1997. Last previous edition approved in 2015 as E1892-15. DOI:
operating life of the facility should be considered to help
10.1520/E1892-15R21.
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 Available from American National Standards Institute (ANSI), 25 W. 43rd St.,
the ASTM website. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E1892 − 15 (2021)
determine the likely location of contaminants. In addition to risk assessments. Specific objectives must be clearly stated in
examining process records, interviews should be conducted thecharacterizationplantoensureobtaininginformationthatis
with personnel knowledgeable in the past operation of the relevant to the decommissioning process.
facility to identify conditions that may not have been recorded. 6.1.2 Data Quality Objectives—Data quality objectives
During this pre-characterization data collection phase, an (DQO) are quantitative and qualitative statements developed
approach for the characterization plan is developed. by data users to specify the quality of data needed from a
particulardatacollectionactivity.ThedevelopmentofDQOsis
4.2 Methodology:
an iterative process involving both the data users and the
4.2.1 The actual characterization of a facility is an iterative
technical staff. Establishment of the characterization objective
process that involves initial sampling according to the charac-
leads to defining DQOs in the characterization plan. These
terization plan, field management (such as labeling, packaging,
DQOs are typically specified in terms of six characteristics:
storing, and transport) of the samples, laboratory analysis,
precision, accuracy, representativeness, completeness,
conformance to the data quality objectives (DQOs), and then
comparability, and detection limit. For decommissioning plan-
identifying any additional sampling required, refining the
ning the DQOs ensure that sufficient information is obtained to
DQOs, and modifying the characterization plan accordingly.
prepare required National Environmental Policy Act (NEPA)
The final product of the facility characterization is a document
documentation and to support the detailed engineering.
that describes the type, amount, and location of contaminants
6.1.3 Background Information:
that will require consideration and removal during the decom-
6.1.3.1 Site Location—The location and a description of the
missioning operations sufficient to prepare a decommissioning
facility relative to other facilities on the site and surrounding
plan. Sufficient information must be provided to:
communities or environment should be described.
(1) estimate volumes for various waste types,
6.1.3.2 Site Characteristics—A description of the entire
(2) plan work to keep radiation exposure as low as reason-
nuclear facility to be decommissioned should be provided
ably achievable (ALARA),
including results of surveys performed prior to initiation of
(3) plan work to keep exposures to hazardous materials
other decommissioning activities. The multi-agency document
ALARA, and
MARSSIM describes site characteristics that should be ad-
(4) support development of a decommissioning radiation
dressed including topography, soils and geology, hydrology,
protection program based on guidance from E1167.
seismology, demography, and meteorology. Specific details
such as those found in safety analysis reports may be provided
5. Significance and Use
in appendices or by reference. Facility characteristics that
5.1 Knowledge of the nature and extent of contamination in
should be addressed include a general facility description, a
a nuclear facility to be decommissioned is crucial to choosing
facility structures description, and a facility systems descrip-
the optimum methods for decontamination and
tion. Radiological and hazardous material characteristics of the
decommissioning, and estimating the resulting waste volumes
nuclear facility shall be included as well. The radionuclide and
and personnel exposures. Implementing a characterization
hazardous chemical inventory for the facility should be pre-
plan, developed in accordance with this standard, will result in
sented with all of the major contributors identified and quan-
obtaining or deriving the above information.
tified. Environmental as well as radiological characteristics of
5.2 Informationontheproposeddecommissioningmethods,
the site should be discussed as they affect exposure pathways.
waste volumes, and estimated personnel radiation exposures
6.1.3.3 Facility Uses—The history of uses for the facility
can be used to define the overall work scope, costs, schedules,
should be stated to give a perspective of the possible contami-
and manpower needs for the decommissioning project. This
nants that may be found in the characterization process.
information may be included in the Decommissioning Plan.
Included should be a description of any process upsets or spills
The extent of over- or under-estimating these project param-
that may have occurred.
eters will be a function of the sampling plan and statistical
6.1.3.4 Information Sources—Sources of information
designs, described in Sections 6.1.4 and 6.1.5.
should be identified and summarized, especially those relevant
to possible contaminants, contaminating events, cleanup
6. Elements of Characterization Plan
issues, and suspect areas. Previous samplings, facility waste
6.1 Radiological and hazardous constituent characterization
plans, radiations surveys, and local sampling problems should
of a facility shall be conducted in accordance with a written
also be included.
plan. The plan must provide direction for the performance of
6.1.4 Sampling Plan and Survey Methodology—As de-
effective sampling and inform concerned individuals as to the
scribed in the EPA document, Test Methods for Evaluating
intent and methods used in the characterization process.
Solid Waste, the sampling plan should provide specific loca-
Guidance on possible content and structure of such a written
tions within the facility for instrument measurements and
plan follows:
physicalsampling. Examplesareradiationfieldmeasurements
6.1.1 C
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