ASTM E1167-87(1996)e1
(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.
General Information
Relations
Standards Content (Sample)
e1
Designation: E 1167 – 87 (Reapproved 1996)
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.
e NOTE—Keywords were added and editorial changes were made throughout in January 1996.
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 This guide provides instruction to the individual charged
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 1034 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-
sioning project.
Annual Book of ASTM Standards, Vol 12.01.
1 3
This guide is under the jurisdiction of ASTM Committee E-10 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, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
E 1167
USNRC Regulatory Guide 8.10 Operating Philosophy for 3.1.7 decontamination supporting radiological protection,
Maintaining Occupational Radiation Exposures as Low as n—this category includes the“ housekeeping” type of decon-
Reasonably Achievable tamination intended to reduce the spread of contamination, to
USNRC Regulatory Guide 8.13 Instruction Concerning Pre- reduce the amount of protective clothing required, or to reduce
natal Radiation Exposure the probability or amount of airborne contamination.
USNRC Regulatory Guide 8.15 Acceptable Programs for 3.1.8 decontamination for unrestricted release, n—involves
Respiratory Protection
reducing radioactive contamination from material, tools, or
USNRC Regulatory Guide 8.29 Instruction Concerning equipment to levels that satisfy “Radiological Release Criteria”
Risk from Occupational Radiation Exposure
(see section 3.1.18).
2.4 DOE Document:
3.1.9 personnel decontamination, n—removal of radioac-
DOE/EV/1830-T5 Guide to Reducing Radiation Exposure
tive material from workers.
to as Low as Reasonably Achievable (ALARA)
3.1.10 nuclear facility, n—facility whose operations involve
2.5 INPO Document:
(or involved) radioactive materials in such form and quantity
INPO 82-004 General Employee Training
that a radiological hazard potentially exists (or existed) to the
2.6 ORP Document:
employees and the general public.
ORP/SID 72-2 Environmental Radioactivity Surveillance
3.1.10.1 Discussion—Included are facilities that are (or
Guide
were) used to produce, process, or store radioactive materials.
2.7 ICRP Document:
Some examples are as follows:
ICRP-43 Principles of Monitoring for the Radiation Protec-
(1) Nuclear reactor (power or research),
tion of the Public
(2) Fuel fabrication plant,
(3) Fuel reprocessing plant,
3. Terminology
(4) Uranium or thorium mill,
3.1 Descriptions of Terms Specific to This Standard:
(5)UF production plant,
3.1.1 audit, n—formal systematic examination to verify
(6) Radiochemical laboratory, and
adequate implementation.
(7) Radioactive waste processing or disposal site, or both.
3.1.2 certified radioactivity standard source, n—calibrated
3.1.11 review, n—critical evaluation to ensure inclusion of
radioactive source, with stated accuracy, whose calibration is
appropriate principles.
certified by the source supplier, as traceable to the National
3.1.12 survey plan, n—document that describes the tech-
Radioactivity Measurements System (see Test Methods E 181).
niques and procedures to be used to provide sufficient radiation
3.1.3 decommission, vt—to remove nuclear facilities safely
measurements to describe the radiation source present within a
from service and reduce residual radioactivity to a level that
predefined area.
permits release of the property for unrestricted use and
3.1.13 radiation protection plan, n—document developed
termination of any applicable licenses.
for a specific decommissioning project that describes the goals
3.1.4 decontamination, n—those activities employed to re-
and intent of the radiation protection program.
duce the levels of (radioactive) contamination in or on struc-
3.1.13.1 Discussion—The radiation protection plan is an
tures, equipment, materials and personnel. Five levels of
element of the radiation protection program and shall become
decontamination are defined as follows:
an integral part of the decommissioning plan.
3.1.5 decontamination for decommissioning, n—at facilities
3.1.14 radiation protection procedures, n—documents used
such as nuclear reactors or accelerators, where high radiation
to implement the radiation protection plan.
fluxes have been present, structural materials may have be-
3.1.15 Radiation Protection Program, n—actions applied to
come radioactive through activation. Removal of such radio-
a decommissioning project whose intent is to limit the expo-
active material (such as a reactor vessel or internals) constitutes
sure of workers, members of the general public, and the
“decontamination.” Removal of intact equipment or structures
environment from radiation or radioactive materials, or both,
containing radioactive material (such as internally contami-
and the written documentation supporting these actions.
nated pipes, valves, pumps, tanks, etc.) also constitutes“
decontamination.” 3.1.16 radiation work procedure, n—documentation used to
specify protective measures and to specify personnel access
3.1.6 decontamination to reduce radiation levels,
n—examples of this type of decontamination would be the use requirements to radiation or radioactive materials, or both.
of chemicals to dissolve radioactive corrosion product deposits 3.1.16.1 Discussion—Control may be achieved through use
from the inside of a piping system or the removal of the top of a single document such as a Radiation Work Permit, which
specifies the protective measures for particular work tasks, or it
layer of a concrete floor into which contaminants had been
embedded and had become a part of the concrete matrix. may be achieved through application of generic procedures and
instructions.
3.1.17 radiological control areas (RCA), n—area of a
Available from Department of Energy, National Technical Information Service,
nuclear facility or area being decommissioned where access is
U.S. Dept. of Commerce, Springfield, VA 22161.
Available from Institute of Nuclear Power Operations, 1100 Circle, 75
controlled for purposes of radiological protection.
Parkway, Atlanta, GA 30339-3064.
3.1.18 radiological release criteria, n—levels of residual
Available from Office of Radiation Programs, 401 M St., SW, Washington, DC
radioactivity at the completion of a decommissioning activity
20460.
Available from Comitato Nazionale Per L’Energia Nucleare, Rome, Italy. below which the object of the decommissioning may be
E 1167
released for unrestricted use to the general public. 8. Radiological Release Criteria
8.1 The radiation protection plan should include a discus-
4. Significance and Use
sion of the radiological criteria that will be used as the basis for
4.1 A program based on this guide will provide assurance to
determining the completion of decommissioning. These crite-
all concerned that the appropriate elements of radiation safety
ria should be based upon applicable limits for unrestricted
have been included to protect workers, the general public, and
release. Decontamination for unrestricted release, if needed,
the environment in proximity to the decommissioning activi-
should consider the specific radionuclides present, the material
ties.
contaminated such as soil or facility, and the potential end uses
4.2 Implementation of such a program will provide assur-
of the item or area being decontaminated. The development of
ance to those agencies responsible for review or audit of the
the criteria should consider the type of measurement to be
decommissioning project that the requirements for radiation
performed, such as surface versus volume, and the medium to
protection have been addressed.
be measured, such as air or water.
RADIATION PROTECTION PROGRAM
5. Radiation Safety Organization and Responsibilities 9. Radiological Survey Plans
5.1 The radiation protection plan should include a descrip- 9.1 There are many phases of a decommissioning project
tion of the radiological protection organization and the radia- that require a radiological survey plan. Surveys generally fall
tion safety responsibilities of each level of the decommission- into three categories: planning surveys, operational surveys,
ing project organization from the individual worker to the and release surveys. The survey plan for each should include
the description of where the measurements are made, how they
project manager. This description should show the radiation
safety organization interfaces and reporting responsibilities at are made (direct measurement or samples), and what is to be
measured (examples include soil samples, vegetation samples,
all levels of the project (see Note 2).
air samples, surfaces, and bore hole logging). The survey plans
6. Radiological Control Areas (RCA)
should emphasize any unique features requiring special proce-
6.1 The Radiation Protection Program should define the
dures.
conditions for designation of an RCA, the physical barriers and
9.2 An environmental monitoring plan should also be pre-
administrative methods to control the spread of radioactive
pared to support the decommissioning project. This plan
material, and the requirements to restrict personnel access for
should be an independent document covering the environmen-
purposes of radiation exposure control. Access to these areas
tal protection program from predecommissioning through un-
shall require a radiation work procedure. The Radiation Pro-
restricted release of the facility or conclusion of the decom-
tection Program should include procedures to determine the
missioning project. The environmental monitoring plan should
radiological conditions within the area, that identify the anti-
become an integral part of the radiation protection plan.
contamination clothing, dosimetry, and respiratory protection
9.3 Since there are many factors that may influence the
required for RCA entry and that define the limitations for
method and procedures to be used in support of an environ-
working within the RCA. These procedures should include any
mental monitoring plan, a detailed description of the environ-
restrictions for workers whose physical condition may limit
mental monitoring plan content is outside the scope of this
entry into or ability to operate within an RCA. The procedures
guide (see Note 3).
should describe the requirements for egress and checkout from
9.3.1 Planning Surveys:
the RCA.
9.3.1.1 The primary objective of the planning surveys is to
NOTE 2—USNRC Regulatory Guides 8.8 and 8.10 provide guidance on
define the radiation source terms with respect to isotopic
describing the relationships that should exist between radiation safety and
identification, location, physical and chemical configuration,
the operating function and the importance of h
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.