ASTM E1167-87(2002)
(Guide)Standard Guide for Radiation Protection Program for Decommissioning Operations
Standard Guide for Radiation Protection Program for Decommissioning Operations
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.
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Designation:E1167–87(Reapproved 2002)
Standard Guide for
Radiation Protection Program for Decommissioning
1
Operations
This standard is issued under the fixed designation E 1167; 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.
NOTE 1—If the site to be decommissioned is adjacent to an operating
1. Scope
site, the radiological impact of the operating site must be considered in the
1.1 Thisguideprovidesinstructiontotheindividualcharged
development of the Radiation Protection Program for the decommission-
with the responsibility for developing and implementing the
ing site.
radiation protection program for decommissioning operations.
1.7 This guide does not address the subjects of emergency
1.2 This guide provides a basis for the user to develop
preparedness, safeguards, accountability, waste handling, stor-
radiation protection program documentation that will support
age, and transportation. Each of these issues has a direct
both the radiological engineering and radiation safety aspects
interface with the radiation protection program. However, each
of the decommissioning project.
constitutes a program in and of itself from program definition
1.3 This guide presents a description of those elements that
through implementation.
should be addressed in a specific radiation protection plan for
1.8 This standard does not purport to address all of the
each decommissioning project. The plan would, in turn, form
safety concerns, if any, associated with its use. It is the
the basis for development of the implementation procedures
responsibility of the user of this standard to establish appro-
that execute the intent of the plan.
priate safety and health practices and determine the applica-
1.4 This guide applies to the development of radiation
bility of regulatory limitations prior to use.
protection programs established to control exposures to radia-
tion and radioactive materials associated with the decommis-
2. Referenced Documents
sioning of nuclear facilities. The intent of this guide is to
2.1 ASTM Standards:
supplement existing radiation protection programs as they may
C 986 Guide for Developing Training Programs in the
pertain to decommissioning workers, members of the general
2
Nuclear Fuel Cycle
public and the environment by describing the basic elements of
E 181 Test Methods for Detector Calibration and Analysis
a radiation protection program for decommissioning opera-
3
of Radionuclides
tions.
E 1134 Specification for Nuclear Facility Transient Worker
1.5 This guide defines the elements of a radiation protection
3
Records
program that will ensure that the goals and objectives of a
E 1168 Guide for Radiological Protection Training for
decommissioning activity are attained within the radiological
3
Nuclear Facility Workers
limits and restrictions imposed by applicable governing and
2.2 ANSI Standards:
regulating agencies. The implementation of such a program
N13.6 Practice for Occupational Radiation Exposure
will provide radiological protection to personnel and the
4
Records System
environment. This guide should be used for developing the
N323 Radiation Protection Instrumentation Test and Cali-
documentation that defines the intent and implementation of
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bration
the radiation protection program for a specific decommission-
2.3 NRC Document:
ing project.
USNRC Regulatory Guide 8.8 Information Relevant to
1.6 The Radiation Protection Program should address the
Insuring that Occupational Radiation Exposure at Nuclear
following elements (see Note 1). This program shall be
Power Stations will be as Low as is Reasonably Achiev-
developed and maintained such that it satisfies all applicable
5
able
Quality Assurance requirements developed for the decommis-
USNRC Regulatory Guide 8.10 Operating Philosophy for
sioning project.
2
Annual Book of ASTM Standards, Vol 12.01.
1 3
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Annual Book of ASTM Standards, Vol 12.02.
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Technology and Applicationsand is the direct responsibility of Subcommittee Available from American National Standards Institute, 11 W. 42nd St., 13th
E10.03on Radiological Protection for Decontamination and Decommissioning of Floor, New York, NY 10036.
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Nuclear Facilities and Components.Current edition approved July 9, 1987. Pub- Available from Nuclear Regulatory Commission, Public Document Room,
lished September 1987. 1717 H St. NW, Washington, DC 20555.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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