ASTM E1892-97
(Guide)Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
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 E 1281 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 planing.
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 and health practices and determine the applicability of regulatory limitations prior to use.
General Information
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Standards Content (Sample)
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
Designation: E 1892 – 97
Standard Guide for
Preparing Characterization Plans for Decommissioning
Nuclear Facilities
This standard is issued under the fixed designation E 1892; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope and to reduce residual contamination to a level that permits
termination of any applicable licenses and release of the
1.1 This standard guide applies to developing nuclear facil-
property for unrestricted use.
ity characterization plans to define the type, magnitude, loca-
3.1.3 Decontamination, n—Activities employed to reduce
tion, and extent of radiological and chemical contamination
the levels of (radioactive or hazardous chemical) contamina-
within the facility to allow decommissioning planning. This
tion in or on structures, equipment, materials and personnel.
guide amplifies guidance regarding facility characterization
3.1.4 Facility, n—As applied to a decommissioning project
indicated in ASTM Standard E 1281 on Nuclear Facility
includes the structure and the soil around and under the
Decommissioning Plans. This guide does not address the
structure to an agreed upon distance.
methodology necessary to release a facility or site for uncon-
ditional use. This guide specifically addresses:
4. Requirements
1.1.1 the data quality objective for characterization as an
4.1 General:
initial step in decommissioning planning.
4.1.1 As an initial part of facility decommissioning plan-
1.1.2 sampling methods,
ning, a characterization plan is developed to define the nature,
1.1.3 the logic involved (statistical design) to ensure ad-
extent and location of contaminants, determine sampling loca-
equate characterization for decommissioning purposes; and
tions and protocols, determine quality assurance objectives for
1.1.4 essential documentation of the characterization infor-
characterization, and define documentation requirements. The
mation.
characterization plan considers the historic use of the facility to
1.2 This standard does not purport to address all of the
identify the likely contaminants due to the radiological process
safety concerns, if any, associated with its use. It is the
involved, the chemicals introduced during the processing, and
responsibility of the user of this standard to establish appro-
any resulting contaminants that may be formed during the
priate safety and health practices and determine the applica-
processing. Records or recounting of any process upsets or
bility of regulatory limitations prior to use.
spills that may have occurred during the operating life of the
2. Referenced Documents facility should be considered to help determine the likely
location of contaminants. In addition to examining process
2.1 ASTM Standards:
records, interview should be conducted with personnel knowl-
E 1167 Standard Guide for Radiation Protection Program
edgeable in the past operation of the facility to identify
for Decommissioning Operations
conditions that may not have been recorded. During this
E 1278 Standard Guide for Radioactive Pathway Method-
pre-characterization data collection phase, an approach for the
ology for Release of Sites Following Decommissioning
characterization plan is developed.
E 1281 Standard Guide for Nuclear Facility Decommission-
4.2 Methodology:
ing Plans
4.2.1 The actual characterization of a facility is an iterative
3. Terminology
process that involves initial sampling according to the charac-
terization plan, field management (such as labeling, packaging,
3.1 Definitions:
storing, and transport) of the samples, laboratory analysis,
3.1.1 Characterization, n—A systematic identification of
conformance to the data quality objectives (DQOs), and then
the types, quantities, forms, and locations of contamination
identifying any additional sampling required, refining the
within a facility.
DQOs, and modifying the characterization plan accordingly.
3.1.2 Decommission, vt—To remove safely from service
The final product of the facility characterization is a document
that describes the type, amount, and location of contaminants
This guide is under the jurisdiction of ASTM Committee E-10 on Nuclear
that will require consideration and removal during the decom-
Technology and Applicationsand is the direct responsibility of Subcommittee E
missioning operations sufficient to prepare a decommissioning
10.03on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
plan. Sufficient information must be provided to:
Current edition approved June 10, 1997. Published October 1997.
1) estimate volumes for various waste types
Annual Book of ASTM Standards, Vol 12.02.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
E 1892
2) plan work to keep radiation exposure as low as reasonably other decommissioning activities. As described in the U. S.
achievable (ALARA) Department of Energy document, A Guide for Radiological
3) plan work to keep exposures to hazardous materials Characterization and Measurement for Decommissioning of U.
ALARA S. Department of Energy Surplus Facilities, site characteristics
that should be addressed include topography, soils and geology,
5. Significance and Use 3
hydrology, seismology, demography, and meteorology. Spe-
5.1 Knowledge of the nature and extent of contamination in
cific details such as those found in safety analysis reports may
a nuclear facility to be decommissioned is crucial to choosing
be provided in appendices or by reference. Facility character-
the optimum methods for decontamination and decommission-
istics that should be addressed include a general facility
ing, and estimating the resulting waste volumes and personnel
description, a facility structures description, and a facility
exposures. Implementing a characterization plan, developed in
systems description. Radiological and hazardous material char-
accordance with this standard, will result in obtaining or
acteristics of the nuclear facility shall be included as well. The
deriving the above information.
radionuclide and hazardous chemical inventory for the facility
5.2 Information on the proposed decommissioning methods,
should be presented with all of the major contributors identified
waste volumes, and estimated personnel radiation exposures
and quantified. Environmental as well as radiological charac-
can be used to define the overall work scope, costs, schedules,
teristics of the site should be discussed as they affect exposure
and manpower needs for the decommissioning project. This
pathways.
information may be included in the Decommissioning Plan.
6.1.3.3 Facility Uses—The history of uses for the facility
The extent of over- or under-estimating these project param-
should be stated to give a perspective of the possible contami-
eters will be a function of the sampling plan and statistical
nants that may be found in the characterization process.
designs, described in Sections 6.1.4 and 6.1.5. Included should be a description of any process upsets or spills
that may have occurred.
6. Elements of Characterization Plan
6.1.3.4 Information Sources—Sources of information
6.1 Radiological and hazardous constituent characterization
should be identified and summarized, especially those relevant
of a facility shall be conducted in accordance with a written
to possible contaminants, contaminating events, cleanup is-
plan. The plan must provide direction for the performance of
sues, and suspect areas. Previous samplings, facility waste
effective sampling and inform concerned individuals as to the
plans, radiations surveys, and local sampling problems should
intent and methods used in the characterization process.
also be included.
Guidance on possible content and structure of such a written
6.1.4 Sampling Plan and Survey Methodology—As de-
plan follows:
scribed in the EPA document, Test Methods for Evaluating
6.1.1 Characterization Objectives—The overall objective
Solid Waste, the sampling plan should provide specific loca-
of the characterization task is to obtain information on the
tions within the facility for instrument measurements and
location, type, and amount of contaminants. This information
physical sampling. Examples are radiation field measurements
will assist in the planning and performance of decommission-
in all areas of the facility, scraping inside of piping, pumps, and
ing operations; and, the data collected during the characteriza-
other equipment, surface wipes for loose contamination, and
tion activity is valuable for source term evaluations to support
coring samples from concrete surfaces, as practical. The
risk assessments. Specific objectives must be clearly stated in
sampling plan should be devised to minimize errors but must
the characterization plan to ensure obtaining information that is
meet the practical objective of providing only information that
relevant to the decommissioning process.
is relevant to decommissioning planning and operations. In-
6.1.2 Data Quality Objectives—Data quality objectives
cluded in the sampling plan must be a consideration of ALARA
(DQO) are quantitative and qualitative statements developed
for personnel exposure, contamination, and the costs associated
by data users to specify the quality of data needed from a
with laboratory analyses and the possible benefit that may be
particular data collection activity. The development of DQOs is
obtained by additional samples.
an iterative process involving both the data users and the
6.1.4.1 The MARSSIM document provides information on
technical staff. Establishment of the characterization objective
instrument selection, measurement protocols, and sample ac-
leads to defining DQOs in the characterization plan. These
quisition. This document is intended to provide guidance in
DQOs are typically specified in terms of six characteristics:
these areas for EPA, NRC, DOE, D&D and environmental
precision, accuracy, represen
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