ASTM E1167-15(2021)

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 service@astm.org. 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
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