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 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-May-2009
Current Stage
Ref Project

Relations

Buy Standard

Guide
ASTM E1892-09 - Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
English language
4 pages
sale 15% off
Preview
sale 15% off
Preview
Guide
REDLINE ASTM E1892-09 - Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
English language
4 pages
sale 15% off
Preview
sale 15% off
Preview

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 − 09
StandardGuide 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 3.1.1 Characterization, n—A systematic identification of
the types, quantities, forms, and locations of contamination
1.1 This standard guide applies to developing nuclear facil-
within a facility.
ity characterization plans to define the type, magnitude,
location, and extent of radiological and chemical contamina- 3.1.2 Decommission,vt—Toremovesafelyfromserviceand
tion within the facility to allow decommissioning planning. to reduce residual contamination to a level that permits
This guide amplifies guidance regarding facility characteriza- termination of any applicable licenses and release of the
property for unrestricted use.
tion indicated in ASTM Standard E1281 on Nuclear Facility
Decommissioning Plans. This guide does not address the
3.1.3 Decontamination, n—Activities employed to reduce
methodology necessary to release a facility or site for uncon-
the levels of (radioactive or hazardous chemical) contamina-
ditional use. This guide specifically addresses:
tion in or on structures, equipment, materials and personnel.
1.1.1 the data quality objective for characterization as an
3.1.4 Facility, n—As applied to a decommissioning project
initial step in decommissioning planning.
includes the structure and the soil around and under the
1.1.2 sampling methods,
structure to an agreed upon distance.
1.1.3 the logic involved (statistical design) to ensure ad-
equate characterization for decommissioning purposes; and
4. Requirements
1.1.4 essential documentation of the characterization infor-
mation. 4.1 General:
4.1.1 As an initial part of facility decommissioning
1.2 This standard does not purport to address all of the
planning, a characterization plan is developed to define the
safety concerns, if any, associated with its use. It is the
nature, extent and location of contaminants, determine sam-
responsibility of the user of this standard to establish appro-
pling locations and protocols, determine quality assurance
priate safety and health practices and determine the applica-
objectives for characterization, and define documentation re-
bility of regulatory limitations prior to use.
quirements. The characterization plan considers the historic
use of the facility to identify the likely contaminants due to the
2. Referenced Documents
2 radiological process involved, the chemicals introduced during
2.1 ASTM Standards:
the processing, and any resulting contaminants that may be
E1167 Guide for Radiation Protection Program for Decom-
formed during the processing. Records or recounting of any
missioning Operations
process upsets or spills that may have occurred during the
E1281 Guide for Nuclear Facility Decommissioning Plans
operating life of the facility should be considered to help
determine the likely location of contaminants. In addition to
3. Terminology
examining process records, interviews should be conducted
3.1 Definitions:
with personnel knowledgeable in the past operation of the
facility to identify conditions that may not have been recorded.
During this pre-characterization data collection phase, an
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
approach for the characterization plan is developed.
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.03 on Radiological Protection for Decontamination and Decommissioning of
4.2 Methodology:
Nuclear Facilities and Components.
4.2.1 The actual characterization of a facility is an iterative
Current edition approved June 1, 2009. Published June 2009. Originally
process that involves initial sampling according to the charac-
approved in 1997. Last previous edition approved in 2003 as E1892-97(2003). DOI:
10.1520/E1892-09.
terization plan, field management (such as labeling, packaging,
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
storing, and transport) of the samples, laboratory analysis,
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
conformance to the data quality objectives (DQOs), and then
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. identifying any additional sampling required, refining the
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1892
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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:E 1892–97 (Reapproved 2003) Designation:E 1892–09
Standard Guide for
Preparing Characterization Plans for Decommissioning
1
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 (´) 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
guidanceregardingfacilitycharacterizationindicatedinASTMStandardE1281onNuclearFacilityDecommissioningPlans.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
2.1 ASTM Standards:
E 1167Standard Guide for Radiation Protection Program for Decommissioning Operations
2 2
E 1278Standard Guide for Radioactive Pathway Methodology for Release of Sites Following Decommissioning
E 1167 Guide for Radiation Protection Program for Decommissioning Operations
E 1281 Standard Guide for Nuclear Facility Decommissioning Plans
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—Toremovesafelyfromserviceandtoreduceresidualcontaminationtoalevelthatpermitstermination
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:
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
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.03 on
Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.
Current edition approved June 10, 1997. Published October 1997.
Current edition approved June 1, 2009. Published June 2009. Originally approved in 1997. Last previous edition approved in 2003 as E 1892-97(2003).
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
, Vol 12.02.volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 1892–09
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 personnel knowledgeable in the past operation of
the facility to identify conditions th
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.