ASTM E1892-15

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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 31-Dec-2014
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E1892 − 15
Standard Guide for
Preparing Characterization Plans for Decommissioning
1
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.
3
1. Scope 2.2 ANSI Standard:
ANSI N323AB American National Standard for Radiation
1.1 This standard guide applies to developing nuclear facil-
Protection Instrumentation Test and Calibration, Portable
ity characterization plans to define the type, magnitude,
Survey Instruments
location, and extent of radiological and chemical contamina-
tion within the facility to allow decommissioning planning.
3. Terminology
This guide amplifies guidance regarding facility characteriza-
3.1 Definitions:
tion indicated in ASTM Standard E1281 on Nuclear Facility
3.1.1 Characterization, n—A systematic identification of
Decommissioning Plans. This guide does not address the
the types, quantities, forms, and locations of contamination
methodology necessary to release a facility or site for uncon-
within a facility.
ditional use. This guide specifically addresses:
3.1.2 Decommission,vt—Toremovesafelyfromserviceand
1.1.1 the data quality objective for characterization as an
to reduce residual contamination to a level that permits
initial step in decommissioning planning.
termination of any applicable licenses and release of the
1.1.2 sampling methods,
property for unrestricted use.
1.1.3 the logic involved (statistical design) to ensure ad-
equate characterization for decommissioning purposes; and
3.1.3 Decontamination, n—Activities employed to reduce
1.1.4 essential documentation of the characterization infor-
the levels of (radioactive or hazardous chemical) contamina-
mation.
tion in or on structures, equipment, materials and personnel.
1.2 This standard does not purport to address all of the
3.1.4 Facility, n—As applied to a decommissioning project
safety concerns, if any, associated with its use. It is the
includes the structure and the soil around and under the
responsibility of the user of this standard to establish appro-
structure to an agreed upon distance.
priate safety and health practices and determine the applica-
4. Requirements
bility of regulatory limitations prior to use.
4.1 General:
2. Referenced Documents
4.1.1 As an initial part of facility decommissioning
2
2.1 ASTM Standards:
planning, a characterization plan is developed to define the
E1167 Guide for Radiation Protection Program for Decom-
nature, extent and location of contaminants, determine sam-
missioning Operations
pling locations and protocols, determine quality assurance
E1281 Guide for Nuclear Facility Decommissioning Plans
objectives for characterization, and define documentation re-
quirements. The characterization plan considers the historic
1
use of the facility to identify the likely contaminants due to the
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee radiological process involved, the chemicals introduced during
E10.03 on Radiological Protection for Decontamination and Decommissioning of
the processing, and any resulting contaminants that may be
Nuclear Facilities and Components.
formed during the processing. Records or recounting of any
Current edition approved Jan. 1, 2015. Published January 2015. Originally
process upsets or spills that may have occurred during the
approved in 1997. Last previous edition approved in 2009 as E1892-09. DOI:
10.1520/E1892-15.
operating life of the facility should be considered to help
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
3
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
1

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E1892 − 15
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 objectiv
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: E1892 − 09 E1892 − 15
Standard Guide for
Preparing Characterization Plans for Decommissioning
1
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
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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
E1167 Guide for Radiation Protection Program for Decommissioning Operations
E1281 Guide for Nuclear Facility Decommissioning Plans
3
2.2 ANSI Standard:
ANSI N323AB American National Standard for Radiation Protection Instrumentation Test and Calibration, Portable Survey
Instruments
3. Terminology
3.1 Definitions:
3.1.1 Characterization, n—A systematic identification of the types, quantities, forms, and locations of contamination within a
facility.
3.1.2 Decommission, vt—To remove safely from service and to reduce residual contamination to a level that permits termination
of any applicable licenses and release of the property for unrestricted use.
3.1.3 Decontamination, n—Activities employed to reduce the levels of (radioactive or hazardous chemical) contamination in or
on structures, equipment, materials and personnel.
3.1.4 Facility, n—As applied to a decommissioning project includes the structure and the soil around and under the structure
to an agreed upon distance.
4. Requirements
4.1 General:
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.03 on
Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.
Current edition approved June 1, 2009Jan. 1, 2015. Published June 2009January 2015. Originally approved in 1997. Last previous edition approved in 20032009 as
E1892-97(2003).E1892-09. DOI: 10.1520/E1892-09.10.1520/E1892-15.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 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
1

---------------------- Page: 1 ----------------------
E1892 − 15
4.1.1 As an initial part of facility decommissioning planning, a characterization plan is developed to define the nature, extent
and location of contaminants, determine sampling locations and protocols, determine quality assurance objectives for
characterization, and define documentation requirements. The characterization plan considers the historic use of the facility to
identify the likely contaminants due to the radiological process involved, the chemicals introduced during the processing, and any
resulting contaminants that may be formed during the processing. Records or recounting of any process upsets or spills that may
have occurred during the operating life of the facility should be considered to help determine the likely location of contaminants.
In addition to examining process records, interviews should be conducted with pe
...