ASTM E1167-87(2008)
(Guide)Standard Guide for Radiation Protection Program for Decommissioning Operations
Standard Guide for Radiation Protection Program for Decommissioning Operations
SIGNIFICANCE AND USE
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.
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. RADIATION PROTECTION PROGRAM Top
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
Relations
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 (Reapproved2008)
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 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
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
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.
Records System
1.6 The Radiation Protection Program should address the
following elements (see Note 1). This program shall be
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
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.
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.
Current edition approved Jan. 1, 2008. Published February 2008. Last previous Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
edition approved in 2002 as D1167–87(02). DOI: 10.1520/E1167-87R08. 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
E1167 − 87 (2008)
ANSI N323A Radiation Protection Instrumentation Test and 3.1.4 decontamination, n—those activities employed to re-
Calibration: Portable Survey Instruments duce the levels of (radioactive) contamination in or on
ANSI N323B Radiation Protection Instrumentation Test and structures, equipment, materials and personnel. Five levels of
Calibration, Portable Survey Instrumentation for Near decontamination are defined as follows:
Background Operation
3.1.5 decontamination for decommissioning, n—at facilities
2.3 NRC Documents:
such as nuclear reactors or accelerators, where high radiation
USNRC Regulatory Guide 8.8 Information Relevant to In-
fluxes have been present, structural materials may have be-
suring that Occupational Radiation Exposure at Nuclear
come radioactive through activation. Removal of such radio-
Power Stations will be as Low as is Reasonably Achiev-
activematerial(suchasareactorvesselorinternals)constitutes
able
“decontamination.” Removal of intact equipment or structures
USNRC Regulatory Guide 8.10 Operating Philosophy for
containing radioactive material (such as internally contami-
Maintaining Occupational Radiation Exposures as Low as
nated pipes, valves, pumps, tanks, etc.) also constitutes“
Reasonably Achievable
decontamination.”
USNRC Regulatory Guide 8.13 Instruction Concerning Pre-
3.1.6 decontamination to reduce radiation levels,
natal Radiation Exposure
n—examples of this type of decontamination would be the use
USNRC Regulatory Guide 8.15 Acceptable Programs for
of chemicals to dissolve radioactive corrosion product deposits
Respiratory Protection
from the inside of a piping system or the removal of the top
USNRCRegulatoryGuide8.29 InstructionConcerningRisk
layer of a concrete floor into which contaminants had been
from Occupational Radiation Exposure
embedded and had become a part of the concrete matrix.
2.4 DOE Document:
3.1.7 decontamination supporting radiological protection,
DOE/EV/1830-T5 GuidetoReducingRadiationExposureto
n—this category includes the“ housekeeping” type of decon-
as Low as Reasonably Achievable (ALARA)
tamination intended to reduce the spread of contamination, to
DOE/IG G-10CFR835/E1 Implementation Guide, Instru-
reduce the amount of protective clothing required, or to reduce
ment Calibration for Portable Survey Instruments
the probability or amount of airborne contamination.
DOE Standard 1070-94 Guidelines for Evaluation of
Nuclear Facility Training Programs
3.1.8 decontamination for unrestricted release, n—involves
2.5 INPO Document: reducing radioactive contamination from material, tools, or
INPO 82-004 General Employee Training equipmenttolevelsthatsatisfy“RadiologicalReleaseCriteria”
(see section 3.1.18).
2.6 USEPA Document:
U.S. Environmental Protection Agency (EPA), 1972 Envi-
3.1.9 personnel decontamination, n—removalofradioactive
ronmental Radioactivity Surveillance Guide, ORP/SID
material from workers.
72-2
3.1.10 nuclear facility, n—facility whose operations involve
2.7 ICRP Document:
(or involved) radioactive materials in such form and quantity
ICRPPublication 43 Principles of Monitoring for the Radia-
that a radiological hazard potentially exists (or existed) to the
tion Protection of the Public;Annals of the ICRPVolume
employees and the general public.
15/1, December 1984
3.1.10.1 Discussion—Included are facilities that are (or
were) used to produce, process, or store radioactive materials.
3. Terminology
Some examples are as follows:
3.1 Definitions of Terms Specific to This Standard:
(1) Nuclear reactor (power or research),
3.1.1 audit, n—formal systematic examination to verify
(2) Fuel fabrication plant,
adequate implementation.
(3) Fuel reprocessing plant,
3.1.2 certified radioactivity standard source, n—calibrated
(4) Uranium or thorium mill,
radioactive source, with stated accuracy, whose calibration is
(5)UF production plant,
certified by the source supplier, as traceable to the National
(6) Radiochemical laboratory, and
Radioactivity Measurements System (see Test Methods E181).
(7) Radioactive waste processing or disposal site, or both.
3.1.3 decommission, vt—to remove nuclear facilities safely
3.1.11 review, n—critical evaluation to ensure inclusion of
from service and reduce residual radioactivity to a level that
appropriate principles.
permits release of the property for unrestricted use and
3.1.12 survey plan, n—document that describes the tech-
termination of any applicable licenses.
niques and procedures to be used to provide sufficient radiation
measurements to describe the radiation source present within a
predefined area.
Available from Nuclear Regulatory Commission, Public Document Room,
1717 H St. NW, Washington, DC 20555.
3.1.13 radiation protection plan, n—document developed
Available from Department of Energy, NationalTechnical Information Service,
for a specific decommissioning project that describes the goals
U.S. Dept. of Commerce, Springfield, VA 22161.
Available from Institute of Nuclear Power Operations, 1100 Circle, 75
and intent of the radiation protection program.
Parkway, Atlanta, GA 30339-3064.
3.1.13.1 Discussion—The radiation protection plan is an
Available from Office of Radiation Programs, 401 M St., SW, Washington, DC
element of the radiation protection program and shall become
20460.
Available from Comitato Nazionale Per L’Energia Nucleare, Rome, Italy. an integral part of the decommissioning plan.
E1167 − 87 (2008)
3.1.14 radiation protection procedures, n— documents used restrictions for workers whose physical condition may limit
to implement the radiation protection plan. entry into or ability to operate within an RCA. The procedures
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-
sure of workers, members of the general public, and the
NOTE 2—USNRC Regulatory Guides 8.8 and 8.10 provide guidance on
environment from radiation or radioactive materials, or both, describing the relationships that should exist between radiation safety and
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
specify protective measures and to specify personnel access
7. Sources and Types of Radiation
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
3.1.18 radiological release criteria, n— levels of residual
and location of the radiation sources. This information is
radioactivity at the completion of a decommissioning activity
necessary for developing the instructions relating to radiation
below which the object of the decommissioning may be
instrumentation selection, radiation measurement techniques,
released for unrestricted use to the general public.
shielding requirements, selection of decontamination methods,
contamination control methods, and personnel dosimetry sys-
4. Significance and Use
tems.
4.1 Aprogram based on this guide will provide assurance to
all concerned that the appropriate elements of radiation safety
8. Radiological Release Criteria
have been included to protect workers, the general public, and
8.1 The radiation protection plan should include a discus-
the environment in proximity to the decommissioning activi-
sionoftheradiologicalcriteriathatwillbeusedasthebasisfor
ties.
determining the completion of decommissioning. These crite-
4.2 Implementation of such a program will provide assur-
ria should be based upon applicable limits for unrestricted
ance to those agencies responsible for review or audit of the
release. Decontamination for unrestricted release, if needed,
decommissioning project that the requirements for radiation
should consider the specific radionuclides present, the material
protection have been addressed.
contaminated such as soil or facility, and the potential end uses
of the item or area being decontaminated. The development of
RADIATION PROTECTION PROGRAM
the criteria should consider the type of measurement to be
performed, such as surface versus volume, and the medium to
5. Radiation Safety Organization and Responsibilities
be measured, such as air or water.
5.1 The radiation protection plan should include a descrip-
tion of the radiological protection organization and the radia-
9. Radiological Survey Plans
tion safety responsibilities of each level of the decommission-
9.1 There are many phases of a decommissioning project
ing project organization from the individual worker to the
that require a radiological survey plan. Surveys generally fall
project manager. This description should show the radiation
into three categories: planning surveys, operational surveys,
safety organization interfaces and reporting responsibilities at
and release surveys. The survey plan for each should include
all levels of t
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.