ASTM E1167-15(2021)

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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.9 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

General Information

• Status: Published
• Publication Date: 31-Jan-2021
• 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

Relations

• Refers: ASTM E1168-95(2020) - Standard Guide for Radiological Protection Training for Nuclear Facility Workers
• Effective Date: 01-Jul-2020
• Refers: ASTM E1168-95(2013) - Standard Guide for Radiological Protection Training for Nuclear Facility Workers
• Effective Date: 01-Jan-2013
• Refers: ASTM E181-10 - Standard Test Methods for Detector Calibration and Analysis of Radionuclides
• Effective Date: 01-Jan-2010
• Refers: ASTM E1893-08a - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Nov-2008
• Refers: ASTM E1893-08 - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Jun-2008
• Refers: ASTM E1168-95(2008) - Standard Guide for Radiological Protection Training for Nuclear Facility Workers
• Effective Date: 15-Feb-2008
• Refers: ASTM E181-98(2003) - Standard Test Methods for Detector Calibration and Analysis of Radionuclides
• Effective Date: 10-Jun-1998
• Refers: ASTM E181-98 - Standard Test Methods for Detector Calibration and Analysis of Radionuclides
• Effective Date: 10-Jun-1998
• Refers: ASTM E1893-97(2003) - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments in Support of Decommissioning
• Effective Date: 10-Jun-1997
• Refers: ASTM E1168-95(2001) - Standard Guide for Radiological Protection Training for Nuclear Facility Workers
• Effective Date: 10-Oct-1995
• Refers: ASTM E1168-95e1 - Standard Guide for Radiological Protection Training for Nuclear Facility Workers
• Effective Date: 10-Oct-1995

Overview

ASTM E1167-15(2021): Standard Guide for Radiation Protection Program for Decommissioning Operations provides comprehensive guidance for developing and implementing effective radiation protection programs during the decommissioning of nuclear facilities. Issued by ASTM International, this standard ensures radiological safety for workers, the general public, and the environment throughout the decommissioning process. It does not cover subjects such as emergency preparedness, waste handling, or safeguards, each of which requires separate dedicated programs.

Adhering to this guide helps organizations meet the requirements of regulatory bodies, supports radiological engineering and safety documentation, and aligns with internationally recognized standardization principles under the WTO Technical Barriers to Trade (TBT) Committee.

Key Topics

• Program Development and Implementation: Outlines instruction for those responsible for establishing radiation protection programs, with an emphasis on documentation supporting both engineering and safety outcomes.
• Elements of Radiation Protection Plans: Identifies specific items to be addressed, such as radiological survey plans, control of exposures, ALARA (As Low As Reasonably Achievable) principles, and quality assurance.
• Control of Radiation Exposures: Stresses methods for limiting exposures to radiation and radioactive materials for decommissioning workers, the general public, and the environment, in alignment with applicable regulations.
• Roles and Responsibilities: Describes the radiation safety organization hierarchy, responsibilities, and reporting processes across all project levels.
• Training Requirements: Establishes the need for formal radiological protection training for all personnel associated with decommissioning projects.
• Monitoring and Calibration: Highlights the importance of instrument calibration, environmental and operational radiological surveys, and regular audits and reviews to ensure ongoing protection and program effectiveness.
• Recordkeeping and Documentation: Specifies minimum recordkeeping requirements to support audits, regulatory compliance, and knowledge management.

Applications

ASTM E1167-15(2021) is vital for a range of stakeholders involved in nuclear facility decommissioning and radiological protection, including:

• Facility Operators and Managers: To develop tailored, site-specific radiation protection programs ensuring legal compliance and safe execution of decommissioning tasks.
• Radiological Safety Officers and Health Physicists: For assessment, planning, and implementation of exposure controls, monitoring, and documentation systems.
• Regulatory Agencies and Auditors: To verify that decommissioning operations sufficiently address radiation protection requirements and maintain environmental safety.
• Contractors and Service Providers in Decommissioning: As a baseline for training, operational procedures, and safety culture.

Following this guide helps minimize radiological risks through robust program structure, continuous training, and rigorous environmental and personnel monitoring. It also facilitates successful completion of decommissioning projects within prescribed radiological limits and supports stakeholder assurance.

Related Standards

Several key documents and standards complement or are referenced by ASTM E1167-15(2021):

• ASTM E1168: Guide for Radiological Protection Training for Nuclear Facility Workers
• ASTM E181: Test Methods for Detector Calibration and Analysis of Radionuclides
• ASTM E1893: Guide for Selection and Use of Portable Radiological Survey Instruments
• ANSI N13.6: Practice for Occupational Radiation Exposure Records System
• ANSI N323AB: Standard for Radiation Protection Instrumentation Test and Calibration
• USNRC Regulatory Guides 8.8, 8.10, 8.13, 8.15, 8.29: Provide federal guidance for occupational radiation exposure, radiological training, and ALARA program development

These standards collectively ensure comprehensive radiation protection during complex decommissioning tasks, supporting regulatory adherence, radiological engineering, and effective organizational safety practices.

Keywords: decommissioning, radiation protection program, radiation safety, radiological engineering, nuclear facility, exposure control, ALARA, radiological survey

Standards Content (Sample)

This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: E1167 − 15 (Reapproved 2021)
Standard Guide for
Radiation Protection Program for Decommissioning
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, health, and environmental practices and deter-
sioning of nuclear facilities. The intent of this guide is to mine the applicability of regulatory limitations prior to use.
supplement existing radiation protection programs as they may
1.9 This international standard was developed in accor-
pertain to decommissioning workers, members of the general dance with internationally recognized principles on standard-
publicandtheenvironmentbydescribingthebasicelementsof ization established in the Decision on Principles for the
a radiation protection program for decommissioning opera-
Development of International Standards, Guides and Recom-
tions. mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
1.5 This guide defines the elements of a radiation protection
program that will ensure that the goals and objectives of a
2. Referenced Documents
decommissioning activity are attained within the radiological
limits and restrictions imposed by applicable governing and 2.1 ASTM Standards:
regulating agencies. The implementation of such a program
E181 Test Methods for Detector Calibration andAnalysis of
will provide radiological protection to personnel and the Radionuclides
environment. This guide should be used for developing the
E1134 Specification for Source-Separated Steel Cans (With-
documentation that defines the intent and implementation of drawn 2001)
the radiation protection program for a specific decommission-
E1168 Guide for Radiological Protection Training for
ing project. Nuclear Facility Workers
E1893 Guide for Selection and Use of Portable Radiological
1.6 The Radiation Protection Program should address the
Survey Instruments for Performing In Situ Radiological
following elements (see Note 1). This program shall be
1 2
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Technology and Applicationsand is the direct responsibility of Subcommittee contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
E10.03 on Radiological Protection for Decontamination and Decommissioning of Standards volume information, refer to the standard’s Document Summary page on
Nuclear Facilities and Components. the ASTM website.
Current edition approved Feb. 1, 2021. Published February 2021. Last previous The last approved version of this historical standard is referenced on
edition approved in 2015 as D1167–15. DOI: 10.1520/E1167-15R21. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E1167 − 15 (2021)
Assessments to Support Unrestricted Release from Fur- 3.1.3 decommission, vt—to remove nuclear facilities safely
ther Regulatory Controls from service and reduce residual radioactivity to a level that
2.2 ANSI Standards: permits release of the property for unrestricted use and
ANSI N13.6 Practice for Occupational Radiation Exposure termination of any applicable licenses.
Records System
3.1.4 decontamination, n—those activities employed to re-
ANSI N323AB American National Standard for Radiation
duce the levels of (radioactive) contamination in or on
Protection Instrumentation Test and Calibration, Portable
structures, equipment, materials and personnel. Five levels of
Survey Instruments
decontamination are defined as follows:
2.3 NRC Documents:
USNRC Regulatory Guide 8.8 Information Relevant to In- 3.1.5 decontamination for decommissioning, n—at facilities
such as nuclear reactors or accelerators, where high radiation
suring that Occupational Radiation Exposure at Nuclear
Power Stations will be as Low as is Reasonably Achiev- fluxes have been present, structural materials may have be-
able come radioactive through activation. Removal of such radio-
USNRC Regulatory Guide 8.10 Operating Philosophy for activematerial(suchasareactorvesselorinternals)constitutes
Maintaining Occupational Radiation Exposures as Low as “decontamination.” Removal of intact equipment or structures
Reasonably Achievable
containing radioactive material (such as internally contami-
USNRC Regulatory Guide 8.13 Instruction Concerning Pre- nated pipes, valves, pumps, tanks, etc.) also constitutes“
natal Radiation Exposure
decontamination.”
USNRC Regulatory Guide 8.15 Acceptable Programs for
3.1.6 decontamination to reduce radiation levels,
Respiratory Protection
n—examples of this type of decontamination would be the use
USNRCRegulatoryGuide8.29 InstructionConcerningRisk
of chemicals to dissolve radioactive corrosion product deposits
from Occupational Radiation Exposure
from the inside of a piping system or the removal of the top
2.4 DOE Document:
layer of a concrete floor into which contaminants had been
DOE/EV/1830-T5 GuidetoReducingRadiationExposureto
embedded and had become a part of the concrete matrix.
as Low as Reasonably Achievable (ALARA)
DOE/IG G-10CFR835/E1 Implementation Guide, Instru-
3.1.7 decontamination supporting radiological protection,
ment Calibration for Portable Survey Instruments n—this category includes the“ housekeeping” type of decon-
DOE Standard 1070-94 Guidelines for Evaluation of
tamination intended to reduce the spread of contamination, to
Nuclear Facility Training Programs
reduce the amount of protective clothing required, or to reduce
2.5 INPO Document: the probability or amount of airborne contamination.
INPO 82-004 General Employee Training
3.1.8 decontamination for unrestricted release, n—involves
2.6 USEPA Document:
reducing radioactive contamination from material, tools, or
U.S. Environmental Protection Agency (EPA), 1972 Envi-
equipmenttolevelsthatsatisfy“RadiologicalReleaseCriteria”
ronmental Radioactivity Surveillance Guide, ORP/SID
(see section 3.1.18).
72-2
2.7 ICRP Document: 3.1.9 personneldecontamination,n—removalofradioactive
material from workers.
ICRPPublication 43 Principles of Monitoring for the Radia-
tion Protection of the Public;Annals of the ICRPVolume
3.1.10 nuclear facility, n—facility whose operations involve
15/1, December 1984
(or involved) radioactive materials in such form and quantity
that a radiological hazard potentially exists (or existed) to the
3. Terminology
employees and the general public.
3.1 Definitions of Terms Specific to This Standard:
3.1.10.1 Discussion—Included are facilities that are (or
3.1.1 audit, n—formal systematic examination to verify
were) used to produce, process, or store radioactive materials.
adequate implementation.
Some examples are as follows:
3.1.2 certified radioactivity standard source, n—calibrated
(1) Nuclear reactor (power or research),
radioactive source, with stated accuracy, whose calibration is
(2) Fuel fabrication plant,
certified by the source supplier, as traceable to the National
(3) Fuel reprocessing plant,
Radioactivity Measurements System (see Test Methods E181).
(4) Uranium or thorium mill,
(5) UF production plant,
(6) Radiochemical laboratory, and
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036, http://www.ansi.org.
(7) Radioactive waste processing or disposal site, or both.
Available from Nuclear Regulatory Commission, Public Document Room,
1717 H St. NW, Washington, DC 20555. 3.1.11 review, n—critical evaluation to ensure inclusion of
Available from Department of Energy, NationalTechnical Information Service,
appropriate principles.
U.S. Dept. of Commerce, Springfield, VA 22161.
Available from Institute of Nuclear Power Operations, 1100 Circle, 75
3.1.12 survey plan, n—document that describes the tech-
Parkway, Atlanta, GA 30339-3064.
niques and procedures to be used to provide sufficient radiation
Available from Office of Radiation Programs, 401 M St., SW, Washington, DC
measurements to describe the radiation source present within a
20460.
Available from Comitato Nazionale Per L’Energia Nucleare, Rome, Italy. predefined area.
E1167 − 15 (2021)
3.1.13 radiation protection plan, n—document developed shall require a radiation work procedure. The Radiation Pro-
for a specific decommissioning project that describes the goals tection Program should include procedures to determine the
and intent of the radiation protection program. radiological conditions within the area, that identify the anti-
3.1.13.1 Discussion—The radiation protection plan is an contamination clothing, dosimetry, and respiratory protection
element of the radiation protection program and shall become required for RCA entry and that define the limitations for
an integral part of the decommissioning plan. working within the RCA.These procedures should include any
restrictions for workers whose physical condition may limit
3.1.14 radiation protection procedures, n— documents used
entry into or ability to operate within an RCA. The procedures
to implement the radiation protection plan.
should describe the requirements for egress and checkout from
3.1.15 Radiation Protection Program, n—actions applied to
the RCA.
a decommissioning project whose intent is to limit the expo-
NOTE 2—USNRC Regulatory Guides 8.8 and 8.10 provide guidance on
sure of workers, members of the general public, and the
describing the relationships that should exist between radiation safety and
environment from radiation or radioactive materials, or both,
the operating function and the importance of high level management
and the written documentation supporting these actions.
support of the radiation safety program.
3.1.16 radiation work procedure, n—documentation used to
7. Sources and Types of Radiation
specify protective measures and to specify personnel access
requirements to radiation or radioactive materials, or both.
7.1 The radiation sources, to be encountered during decom-
3.1.16.1 Discussion—Control may be achieved through use
missioning activities, shall be defined. Reviews of the operat-
of a single document such as a Radiation Work Permit, which
ing history of the facility (including interviews with past and
specifiestheprotectivemeasuresforparticularworktasks,orit
present employees), coupled with nuclear analysis and detailed
maybeachievedthroughapplicationofgenericproceduresand
radiologicalcharacterizationsurveys(seeSection9),shouldbe
instructions.
used to provide this information. This description of radiation
3.1.17 radiological control areas (RCA), n— area of a sourcesshouldincludethetypeofradiationsuchasalpha,beta,
nuclear facility or area being decommissioned where access is gamma, or neutron; the isotopic composition, the physical and
controlled for purposes of radiological protection. chemical form of the radioactive material, and the magnitude
and location of the radiation sources. This information is
3.1.18 radiological release criteria, n— levels of residual
necessary for developing the instructions relating to radiation
radioactivity at the completion of a decommissioning activity
instrumentation selection, radiation measurement techniques,
below which the object of the decommissioning may be
shielding requirements, selection of decontamination methods,
released for unrestricted use to the general public.
contamination control methods, and personnel dosimetry sys-
tems.
4. Significance and Use
4.1 Aprogram based on this guide will provide assurance to
8. Radiological Release Criteria
all concerned that the appropriate elements of radiation safety
8.1 The radiation protection plan should include a discus-
have been included to protect workers, the general public, and
sionoftheradiologicalcriteriathatwillbeusedasthebasisfor
the environment in proximity to the decommissioning activi-
determining the completion of decommissioning. These crite-
ties.
ria should be based upon applicable limits for unrestricted
4.2 Implementation of such a program will provide assur-
release. Decontamination for unrestricted release, if needed,
ance to those agencies responsible for review or audit of the
should consider the specific radionuclides present, the material
decommissioning project that the requirements for radiation
contaminated such as soil or facility, and the potential end uses
protection have been addressed.
of the item or area being decontaminated. The development of
the criteria should consider the type of measurement to be
RADIATION PROTECTION PROGRAM
performed, such as surface versus volume, and the medium to
be measured, such as air or water.
5. Radiation Safety Organization and Responsibilities
5.1 The radiation protection plan should include a descrip-
9. Radiological Survey Plans
tion of the radiological protection organization and the radia-
9.1 There are many phases of a decommissioning project
tion safety responsibilities of each level of the decommission-
that require a radiological survey plan. Surveys generally fall
ing project organization from the individual worker to the
into three categories: planning surveys, operational surveys,
project manager. This description should show the radiation
and release surveys. The survey plan for each should include
safety organization interfaces and reporting responsibilities at
the description of where the measurements are made, how they
all levels of the project (see Note 2).
are made (direct measurement or samples), and what is to be
6. Radiological Control Areas (RCA) measured (examples include soil samples, vegetation samples,
air samples, surfaces, and bore hole logging).The survey plans
6.1 The Radiation Protection Program should define the
should emphasize any unique features requiring special proce-
conditionsfordesignationofanRCA,thephysicalbarriersand
dures.
administrative methods to control the spread of radioactive
material, and the requirements to restrict personnel access for 9.2 An environmental monitoring plan should also be pre-
purposes of radiation exposure control. Access to these areas pared to support the decommissioning project. This plan
E1167 − 15 (2021)
should be an independent document covering the environmen- missioning activities to ensure that radiological material re-
tal protection program from predecommissioning through un- leased from the decommissioning site are within project goals.
restricted release of the facility or conclusion of the decom- The surveys will also be used by the health physicist and
missioning project. The environmental monitoring plan should nuclear engineer to perform an engineering analysis of the
become an integral part of the radiation protection plan. tradeoffs among alternative methods of reducing exposure, to
predict changes in radiological conditions that will occur
9.3 Since there are many factors that may influence the
during the decommissioning task, and to specify exposure
method and procedures to be used in support of an environ-
management techniques for workers performing the task.
mental monitoring plan, a detailed description of the environ-
9.3.2.2 The radiation monitoring during a task must con-
mental monitoring plan content is outside the scope of this
sider the isotopic composition, the physical and chemical
guide (see Note 3).
forms, the radiation levels expected, and the activities of the
9.3.1 Planning Surveys:
task which may alter these parameters. The survey plan should
9.3.1.1 The primary objective of the planning surveys is to
include the monitoring techniques and the actions to be taken
define the radiation source terms with respect to isotopic
if the radiation environment changes unexpectedly during the
identification, location, physical and chemical configuration,
task operation.At the completion of tasks involving changes to
and radiation level.
the radiation environment, a complete radiation survey should
9.3.1.2 The results of this survey must also be in sufficient
be conducted and the results compared to pre-task surveys to
detail to permit an engineering evaluation for selecting an
assess the effects of the operation.
appropriate decommissioning option. These results then form
9.3.3 Release Surveys—The objective of the release survey
the basis for input into the engineering plan for decommission-
is to ensure that the goals and objectives of the decommission-
ing and for defining elements of the radiation protection plan
ing program have been met. The release survey plan would be
necessary to ensure that adequate environmental monitoring
implemented when operational surveys indicate that the objec-
and radiation exposure management procedures are imple-
tives of the decommissioning operation have been achieved.
mented for the isotopic and physical forms present. Elements
Thereleasesurveywouldbesimilartotheplanningsurveyand
of the engineering plan that have a direct bearing on the
should use a grid system to locate the radiation measurement
radiation protection plan include selection of the methods and
points. This survey may be sufficiently different to change the
extent of decontamination to reduce radiation and contamina-
requirements on the instrument selection, measurement
tion levels, analysis and design of temporary and semi-
technique, and sampling analysis. The types of measurements
permanent radiation shielding, selection and evaluation of
and samples to be taken and the depth beneath the surfaces for
remote tooling techniques, and the performance of tradeoff
sampling must take into account changes in the surfaces that
studies among various radiation exposure reduction alterna-
resulted from the decontamination operation. The number and
tives.
sensitivity of the measurements must be sufficient to evalu
...