ASTM E1167-87(2002)

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.

General Information

• Status: Historical
• Publication Date: 08-Jul-1987
• 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

• Replaces: ASTM E1167-87(1996)e1 - Standard Guide for Radiation Protection Program for Decommissioning Operations
• Effective Date: 09-Jul-1987
• Replaced By: ASTM E1167-87(2008) - Standard Guide for Radiation Protection Program for Decommissioning Operations
• Effective Date: 01-Jan-2008
• Referred By: ASTM E1281-15(2021) - Standard Guide for Nuclear Facility Decommissioning Plans
• Effective Date: 09-Jul-1987
• Referred By: ASTM E1819-15(2021) - Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities
• Effective Date: 09-Jul-1987
• Referred By: ASTM E1892-15(2021) - Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
• Effective Date: 09-Jul-1987
• Referred By: ASTM E2420-15(2021) - Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities
• Effective Date: 09-Jul-1987

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:E1167–87(Reapproved 2002)
Standard Guide for
Radiation Protection Program for Decommissioning
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
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-
of Radionuclides
tions.
E 1134 Specification for Nuclear Facility Transient Worker
1.5 This guide defines the elements of a radiation protection
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
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
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
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
able
Quality Assurance requirements developed for the decommis-
USNRC Regulatory Guide 8.10 Operating Philosophy for
sioning project.
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.
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.
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.
E1167
Maintaining Occupational Radiation Exposures as Low as 3.1.7 decontamination supporting radiological protection,
Reasonably Achievable n—this category includes the“ housekeeping” type of decon-
USNRCRegulatoryGuide8.13 InstructionConcerningPre- tamination intended to reduce the spread of contamination, to
natal Radiation Exposure reduce the amount of protective clothing required, or to reduce
USNRC Regulatory Guide 8.15 Acceptable Programs for the probability or amount of airborne contamination.
Respiratory Protection 3.1.8 decontamination for unrestricted release, n—involves
USNRC Regulatory Guide 8.29 Instruction Concerning
reducing radioactive contamination from material, tools, or
Risk from Occupational Radiation Exposure equipmenttolevelsthatsatisfy“RadiologicalReleaseCriteria”
2.4 DOE Document:
(see section 3.1.18).
DOE/EV/1830-T5 Guide to Reducing Radiation Exposure
3.1.9 personnel decontamination, n—removal of radioac-
to as Low as Reasonably Achievable (ALARA)
tive material from workers.
2.5 INPO Document:
3.1.10 nuclear facility, n—facilitywhoseoperationsinvolve
INPO 82-004 General Employee Training
(or involved) radioactive materials in such form and quantity
2.6 ORP Document:
that a radiological hazard potentially exists (or existed) to the
ORP/SID 72-2 Environmental Radioactivity Surveillance
employees and the general public.
Guide
3.1.10.1 Discussion—Included are facilities that are (or
2.7 ICRP Document:
were) used to produce, process, or store radioactive materials.
ICRP-43 Principles of Monitoring for the Radiation Protec-
Some examples are as follows:
tion of the Public
(1) Nuclear reactor (power or research),
(2) Fuel fabrication plant,
3. Terminology
(3) Fuel reprocessing plant,
3.1 Descriptions of Terms Specific to This Standard:
(4) Uranium or thorium mill,
3.1.1 audit, n—formal systematic examination to verify
(5)UF production plant,
adequate implementation.
(6) Radiochemical laboratory, and
3.1.2 certified radioactivity standard source, n—calibrated
(7) Radioactive waste processing or disposal site, or both.
radioactive source, with stated accuracy, whose calibration is
certified by the source supplier, as traceable to the National
3.1.11 review, n—critical evaluation to ensure inclusion of
RadioactivityMeasurementsSystem(seeTestMethodsE 181).
appropriate principles.
3.1.3 decommission, vt—to remove nuclear facilities safely
3.1.12 survey plan, n—document that describes the tech-
from service and reduce residual radioactivity to a level that
niques and procedures to be used to provide sufficient radiation
permits release of the property for unrestricted use and
measurements to describe the radiation source present within a
termination of any applicable licenses.
predefined area.
3.1.4 decontamination, n—those activities employed to re-
3.1.13 radiation protection plan, n—document developed
duce the levels of (radioactive) contamination in or on struc-
for a specific decommissioning project that describes the goals
tures, equipment, materials and personnel. Five levels of
and intent of the radiation protection program.
decontamination are defined as follows:
3.1.13.1 Discussion—The radiation protection plan is an
3.1.5 decontamination for decommissioning, n—at facilities
element of the radiation protection program and shall become
such as nuclear reactors or accelerators, where high radiation
an integral part of the decommissioning plan.
fluxes have been present, structural materials may have be-
3.1.14 radiation protection procedures, n—documents used
come radioactive through activation. Removal of such radio-
to implement the radiation protection plan.
activematerial(suchasareactorvesselorinternals)constitutes
3.1.15 Radiation Protection Program, n—actions applied to
“decontamination.” Removal of intact equipment or structures
a decommissioning project whose intent is to limit the expo-
containing radioactive material (such as internally contami-
sure of workers, members of the general public, and the
nated pipes, valves, pumps, tanks, etc.) also constitutes“
environment from radiation or radioactive materials, or both,
decontamination.”
and the written documentation supporting these actions.
3.1.6 decontamination to reduce radiation levels,
3.1.16 radiation work procedure, n—documentation used to
n—examples of this type of decontamination would be the use
specify protective measures and to specify personnel access
of chemicals to dissolve radioactive corrosion product deposits
requirements to radiation or radioactive materials, or both.
from the inside of a piping system or the removal of the top
3.1.16.1 Discussion—Control may be achieved through use
layer of a concrete floor into which contaminants had been
of a single document such as a Radiation Work Permit, which
embedded and had become a part of the concrete matrix.
specifiestheprotectivemeasuresforparticularworktasks,orit
maybeachievedthroughapplicationofgenericproceduresand
instructions.
Available from Department of Energy, NationalTechnical Information Service,
3.1.17 radiological control areas (RCA), n—area of a
U.S. Dept. of Commerce, Springfield, VA 22161.
Available from Institute of Nuclear Power Operations, 1100 Circle, 75
nuclear facility or area being decommissioned where access is
Parkway, Atlanta, GA 30339-3064.
controlled for purposes of radiological protection.
Available from Office of Radiation Programs, 401 M St., SW, Washington, DC
3.1.18 radiological release criteria, n—levels of residual
20460.
Available from Comitato Nazionale Per L’Energia Nucleare, Rome, Italy. radioactivity at the completion of a decommissioning activity
E1167
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
9.2 An environmental monitoring plan should also be pre-
material, and the requirements to restrict personnel access for
pared to support the decommissioning project. This plan
purposes of radiation exposure control. Access to these areas
should be an independent document covering the environmen-
shall require a radiation work procedure. The Radiation Pro-
tal protection program from predecommissioning through un-
tection Program should include procedures to determine the
restricted release of the facility or conclusion of the decom-
radiological conditions within the area, that identify the anti-
missioning project. The environmental monitoring plan should
contamination clothing, dosimetry, and respiratory protection
become an integral part of the radiation protection plan.
required for RCA entry and that define the limitations for
9.3 Since there are many factors that may influence the
working within the RCA.These procedures should include any
method and procedures to be used in support of an environ-
restrictions for workers whose physical condition may limit
mental monitoring plan, a detailed description of the environ-
entry into or ability to operate within an RCA. The procedures
mental monitoring plan content is outside the scope of this
should describe the requirements for egress and checkout from
guide (see Note 3).
the RCA.
9.3.1 Planning Surveys:
NOTE 2—USNRC Regulatory Guides 8.8 and 8.10 provide guidance on
9.3.1.1 The primary objective of the planning surveys is to
describing the relationships that should exist between radiation safety and
define the radiation source
...