ASTM E1167-15

Standard Guide for Radiation Protection Program for Decommissioning Operations

SIGNIFICANCE AND USE
4.1 A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities.  
4.2 Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed.
SCOPE
1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.  
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.  
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.  
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.  
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.  
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.  
Note 1: If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.  
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.  
1.8 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: 13.280 - Radiation protection
• ICS: 27.120.10 - Reactor engineering
• 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: E1167 − 15
Standard Guide for
Radiation Protection Program for Decommissioning
1
Operations
This standard is issued under the fixed designation E1167; 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 developed and maintained such that it satisfies all applicable
Quality Assurance requirements developed for the decommis-
1.1 Thisguideprovidesinstructiontotheindividualcharged
sioning project.
with the responsibility for developing and implementing the
radiation protection program for decommissioning operations.
NOTE 1—If the site to be decommissioned is adjacent to an operating
site,theradiologicalimpactoftheoperatingsitemustbeconsideredinthe
1.2 This guide provides a basis for the user to develop
development of the Radiation Protection Program for the decommission-
radiation protection program documentation that will support
ing site.
both the radiological engineering and radiation safety aspects
1.7 This guide does not address the subjects of emergency
of the decommissioning project.
preparedness, safeguards, accountability, waste handling,
1.3 This guide presents a description of those elements that
storage, and transportation. Each of these issues has a direct
should be addressed in a specific radiation protection plan for
interface with the radiation protection program. However, each
each decommissioning project. The plan would, in turn, form
constitutes a program in and of itself from program definition
the basis for development of the implementation procedures
through implementation.
that execute the intent of the plan.
1.8 This standard does not purport to address all of the
1.4 This guide applies to the development of radiation
safety concerns, if any, associated with its use. It is the
protection programs established to control exposures to radia- responsibility of the user of this standard to establish appro-
tion and radioactive materials associated with the decommis-
priate safety and health practices and determine the applica-
sioning of nuclear facilities. The intent of this guide is to bility of regulatory limitations prior to use.
supplement existing radiation protection programs as they may
2. Referenced Documents
pertain to decommissioning workers, members of the general
2
publicandtheenvironmentbydescribingthebasicelementsof
2.1 ASTM Standards:
a radiation protection program for decommissioning opera-
E181 Test Methods for Detector Calibration andAnalysis of
tions.
Radionuclides
E1134 Specification for Source-Separated Steel Cans (With-
1.5 This guide defines the elements of a radiation protection
3
drawn 2001)
program that will ensure that the goals and objectives of a
E1168 Guide for Radiological Protection Training for
decommissioning activity are attained within the radiological
Nuclear Facility Workers
limits and restrictions imposed by applicable governing and
E1893 Guide for Selection and Use of Portable Radiological
regulating agencies. The implementation of such a program
Survey Instruments for Performing In Situ Radiological
will provide radiological protection to personnel and the
Assessments to Support Unrestricted Release from Fur-
environment. This guide should be used for developing the
ther Regulatory Controls
documentation that defines the intent and implementation of
the radiation protection program for a specific decommission- 2.2 ANSI Standards:
ANSI N13.6 Practice for Occupational Radiation Exposure
ing project.
4
Records System
1.6 The Radiation Protection Program should address the
following elements (see Note 1). This program shall be
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
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Standards volume information, refer to the standard’s Document Summary page on
Technology and Applicationsand is the direct responsibility of Subcommittee the ASTM website.
3
E10.03 on Radiological Protection for Decontamination and Decommissioning of The last approved version of this historical standard is referenced on
Nuclear Facilities and Components. www.astm.org.
4
Current edition approved Jan. 1, 2015. Published January 2015. Last previous Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
edition approved in 2008 as D1167–87(08). DOI: 10.1520/E1167-15. 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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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: E1167 − 87 (Reapproved 2008) E1167 − 15
Standard Guide for
Radiation Protection Program for Decommissioning
1
Operations
This standard is issued under the fixed designation E1167; 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 guide provides instruction to the individual charged with the responsibility for developing and implementing the
radiation protection program for decommissioning operations.
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the
radiological engineering and radiation safety aspects of the decommissioning project.
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each
decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute
the intent of the plan.
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and
radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing
radiation protection programs as they may pertain to decommissioning workers, members of the general public and the
environment by describing the basic elements of a radiation protection program for decommissioning operations.
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a
decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and
regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment.
This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection
program for a specific decommissioning project.
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and
maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.
NOTE 1—If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the
development of the Radiation Protection Program for the decommissioning site.
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and
transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a
program in and of itself from program definition through implementation.
1.8 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:
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
3
E1134 Specification for Source-Separated Steel Cans (Withdrawn 2001)
E1168 Guide for Radiological Protection Training for Nuclear Facility Workers
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 Jan. 1, 2008Jan. 1, 2015. Published February 2008January 2015. Last previous edition approved in 20022008 as D1167–87(02).–87(08). DOI:
10.1520/E1167-87R08.10.1520/E1167-15.
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
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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E1167 − 15
E1893 Guide for
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