ASTM E1892-97(2003)
(Guide)Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
SIGNIFICANCE AND USE
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.
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 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.
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Designation:E 1892–97 (Reapproved 2003)
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 3.1.2 Decommission, vt—To remove safely from service
and to reduce residual contamination to a level that permits
1.1 This standard guide applies to developing nuclear facil-
termination of any applicable licenses and release of the
ity characterization plans to define the type, magnitude, loca-
property for unrestricted use.
tion, and extent of radiological and chemical contamination
3.1.3 Decontamination, n—Activities employed to reduce
within the facility to allow decommissioning planning. This
the levels of (radioactive or hazardous chemical) contamina-
guide amplifies guidance regarding facility characterization
tion in or on structures, equipment, materials and personnel.
indicated in ASTM Standard E 1281 on Nuclear Facility
3.1.4 Facility, n—As applied to a decommissioning project
Decommissioning Plans. This guide does not address the
includes the structure and the soil around and under the
methodology necessary to release a facility or site for uncon-
structure to an agreed upon distance.
ditional use. This guide specifically addresses:
1.1.1 the data quality objective for characterization as an
4. Requirements
initial step in decommissioning planning.
4.1 General:
1.1.2 sampling methods,
4.1.1 As an initial part of facility decommissioning plan-
1.1.3 the logic involved (statistical design) to ensure ad-
ning, a characterization plan is developed to define the nature,
equate characterization for decommissioning purposes; and
extent and location of contaminants, determine sampling loca-
1.1.4 essential documentation of the characterization infor-
tions and protocols, determine quality assurance objectives for
mation.
characterization, and define documentation requirements. The
1.2 This standard does not purport to address all of the
characterizationplanconsidersthehistoricuseofthefacilityto
safety concerns, if any, associated with its use. It is the
identify the likely contaminants due to the radiological process
responsibility of the user of this standard to establish appro-
involved, the chemicals introduced during the processing, and
priate safety and health practices and determine the applica-
any resulting contaminants that may be formed during the
bility of regulatory limitations prior to use.
processing. Records or recounting of any process upsets or
2. Referenced Documents spills that may have occurred during the operating life of the
facility should be considered to help determine the likely
2.1 ASTM Standards:
location of contaminants. In addition to examining process
E 1167 Standard Guide for Radiation Protection Program
records, interview should be conducted with personnel knowl-
for Decommissioning Operations
edgeable in the past operation of the facility to identify
E 1278 Standard Guide for Radioactive Pathway Method-
conditions that may not have been recorded. During this
ology for Release of Sites Following Decommissioning
pre-characterization data collection phase, an approach for the
E1281 StandardGuideforNuclearFacilityDecommission-
characterization plan is developed.
ing Plans
4.2 Methodology:
3. Terminology
4.2.1 The actual characterization of a facility is an iterative
process that involves initial sampling according to the charac-
3.1 Definitions:
terization plan, field management (such as labeling, packaging,
3.1.1 Characterization, n—A systematic identification of
storing, and transport) of the samples, laboratory analysis,
the types, quantities, forms, and locations of contamination
conformance to the data quality objectives (DQOs), and then
within a facility.
identifying any additional sampling required, refining the
DQOs, and modifying the characterization plan accordingly.
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
The final product of the facility characterization is a document
Technology and Applications and is the direct responsibility of Subcommittee E
that describes the type, amount, and location of contaminants
10.03 on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
Current edition approved June 10, 1997. Published October 1997.
Annual Book of ASTM Standards, Vol 12.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E 1892–97 (2003)
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)planworktokeepradiationexposureaslowasreasonably
nuclear facility to be decommissioned should be provided
achievable (ALARA)
including results of surveys performed prior to initiation of
3) plan work to keep exposures to hazardous materials
other decommissioning activities. As described in the U. S.
ALARA
Department of Energy document, A Guide for Radiological
Characterization and Measurement for Decommissioning of U.
5. Significance and Use
S. Department of Energy Surplus Facilities, site characteristics
thatshouldbeaddressedincludetopography,soilsandgeology,
5.1 Knowledge of the nature and extent of contamination in
hydrology, seismology, demography, and meteorology. Spe-
a nuclear facility to be decommissioned is crucial to choosing
cific details such as those found in safety analysis reports may
the optimum methods for decontamination and decommission-
ing, and estimating the resulting waste volumes and personnel be provided in appendices or by reference. Facility character-
exposures. Implementing a characterization plan, developed in istics that should be addressed include a general facility
accordance with this standard, will result in obtaining or
description, a facility structures description, and a facility
deriving the above information.
systems description. Radiological and hazardous material char-
5.2 Informationontheproposeddecommissioningmethods,
acteristics of the nuclear facility shall be included as well. The
waste volumes, and estimated personnel radiation exposures
radionuclide and hazardous chemical inventory for the facility
can be used to define the overall work scope, costs, schedules,
shouldbepresentedwithallofthemajorcontributorsidentified
and manpower needs for the decommissioning project. This
and quantified. Environmental as well as radiological charac-
information may be included in the Decommissioning Plan.
teristics of the site should be discussed as they affect exposure
The extent of over- or under-estimating these project param-
pathways.
eters will be a function of the sampling plan and statistical
6.1.3.3 Facility Uses—The history of uses for the facility
designs, described in Sections 6.1.4 and 6.1.5.
should be stated to give a perspective of the possible contami-
nants that may be found in the characterization process.
6. Elements of Characterization Plan
Included should be a description of any process upsets or spills
6.1 Radiological and hazardous constituent characterization
that may have occurred.
of a facility shall be conducted in accordance with a written
6.1.3.4 Information Sources—Sources of information
plan. The plan must provide direction for the performance of
should be identified and summarized, especially those relevant
effective sampling and inform concerned individuals as to the
to possible contaminants, contaminating events, cleanup is-
intent and methods used in the characterization process.
sues, and suspect areas. Previous samplings, facility waste
Guidance on possible content and structure of such a written
plans, radiations surveys, and local sampling problems should
plan follows:
also be included.
6.1.1 Characterization Objectives—The overall objective
6.1.4 Sampling Plan and Survey Methodology—As de-
of the characterization task is to obtain information on the
scribed in the EPA document, Test Methods for Evaluating
location, type, and amount of contaminants. This information
Solid Waste, the sampling plan should provide specific loca-
will assist in the planning and performance of decommission-
ing operations; and, the data collected during the characteriza- tions within the facility for instrument measurements and
tion activity is valuable for source term evaluations to support physicalsampling. Examplesareradiationfieldmeasurements
risk assessments. Specific objectives must be clearly stated in
inallareasofthefacility,scrapinginsideofpiping,pumps,and
thecharacterizationplantoensureobtaininginformationthatis
other equipment, surface wipes for loose contamination, and
relevant to the decommissioning process.
coring samples from concrete surfaces, as practical. The
6.1.2 Data Quality Objectives—Data quality objectives
sampling plan should be devised to minimize errors but must
(DQO) are quantitative and qualitative statements developed meet the practical objective of providing only information that
by data users to specify the quality of data needed from a
is relevant to decommissioning planning and operations. In-
particulardatacollectionactivity.ThedevelopmentofDQOsis
cludedinthesamplingplanmustbeaconsiderationofALARA
an iterative process involving both the data users and the
forpersonnelexposure,contamination,andthecostsassociated
technical staff. Establishment of the characterization objective
with laboratory analyse
...
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