ASTM D5608-94
(Practice)Standard Practice for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites
Standard Practice for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites
SCOPE
1.1 This practice covers the decontamination of field equipment used in the sampling of soils, soil gas, sludges, surface water, and ground water at waste sites known or suspected of containing low level radioactive wastes.
1.2 This practice is applicable at sites where low level radioactive wastes are known or suspected to exist. This practice may also be applicable for the decontamination of equipment used in known or suspected transuranic, or mixed wastes when used by itself or in conjunction with Practice D5088.
1.3 Procedures are contained in this practice for the decontamination of equipment that comes into contact with the sample matrix (sample contacting equipment), and for ancillary equipment that has not contacted the sample, but may have become contaminated during use (non-contacting equipment).
1.4 This practice is applicable to most conventional sampling equipment constructed of metallic and hard, smooth synthetic materials. Materials with rough or porous surfaces, or having a high sorption rate should not be used in radioactive waste sampling due to the difficulties with decontamination.
1.5 In those cases where sampling will be periodically performed, such as sampling of wells, consideration should be given to the use of dedicated sampling equipment if legitimate concerns exist for the production of undesirable or unmanageable waste byproducts, or both, during the decontamination of tools and equipment.
1.6 This practice does not address regulatory requirements for personnel protection or decontamination, or for the handling, labeling, shipping or storing of wastes, or samples. Specific radiological release requirements and limits must be determined by users in accordance with local, state and federal regulations.
1.7 For additional information see DOE Publication DOE/EH-0256T, DOE Order 5480.5, DOE Order 5480.11, and 10CFR, Part 834.
1.8 The values stated in SI units are to be regarded as the standard.
1.9 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. Specific precautionary statements are given in Section 6.
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Designation: D 5608 – 94
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Practice for
Decontamination of Field Equipment Used at Low Level
Radioactive Waste Sites
This standard is issued under the fixed designation D 5608; 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.
1. Scope safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
1.1 This practice covers the decontamination of field equip-
priate safety and health practices and determine the applica-
ment used in the sampling of soils, soil gas, sludges, surface
bility of regulatory limitations prior to use. Specific precau-
water, and ground water at waste sites known or suspected of
tionary statements are given in Section 6.
containing low level radioactive wastes.
1.2 This practice is applicable at sites where low level
2. Referenced Documents
radioactive wastes are known or suspected to exist. This
2.1 ASTM Standards:
practice may also be applicable for the decontamination of
D 5088 Practice for the Decontamination of Field Equip-
equipment used in known or suspected transuranic, or mixed
ment Used at Nonradioactive Waste Sites
wastes when used by itself or in conjunction with Practice
E 1168 Guide for Radiological Protection Training for
D 5088.
Nuclear Facility Workers
1.3 Procedures are contained in this practice for the decon-
2.2 United States Department of Energy Standards:
tamination of equipment that comes into contact with the
DOE Publication DOE/EH-0256T Radiological Control
sample matrix (sample contacting equipment), and for ancil-
Manual
lary equipment that has not contacted the sample, but may have
DOE Order 5480.5 Radiation Protection of the Public and
become contaminated during use (non-contacting equipment).
the Environment
1.4 This practice is applicable to most conventional sam-
DOE Order 5480.11 Radiological Protection for Occupa-
pling equipment constructed of metallic and hard, smooth
tional Workers
synthetic materials. Materials with rough or porous surfaces, or
2.3 United States Code of Federal Regulations:
having a high sorption rate should not be used in radioactive
10CFR, Part 834, “Radiological Protection for Occupa-
waste sampling due to the difficulties with decontamination.
tional Workers”
1.5 In those cases where sampling will be periodically
performed, such as sampling of wells, consideration should be
3. Terminology
given to the use of dedicated sampling equipment if legitimate
3.1 Definitions of Terms Specific to This Standard:
concerns exist for the production of undesirable or unmanage-
3.1.1 as low as reasonable achievable (ALARA)—an ap-
able waste byproducts, or both, during the decontamination of
proach to radiological control to manage exposures to the work
tools and equipment.
force and to the general public at levels as low as is reasonable,
1.6 This practice does not address regulatory requirements
taking into account social, technical, economic, practical and
for personnel protection or decontamination, or for the han-
public policy. ALARA has the objective of maintaining doses
dling, labeling, shipping or storing of wastes, or samples.
at a level far below applicable controlling limits.
Specific radiological release requirements and limits must be
3.1.2 barrier—a physical separation, such as a fence, wall,
determined by users in accordance with local, state and federal
or temporary enclosure to prevent uncontrolled access and
regulations.
release from an area.
1.7 For additional information see DOE Publication DOE/
3.1.3 contamination—either fixed or removable radioactive
EH-0256T, DOE Order 5480.5, DOE Order 5480.11, and
materials in or on an item.
10CFR, Part 834.
3.1.4 contamination reduction corridor—a defined pathway
1.8 The values stated in SI units are to be regarded as the
through a hazardous waste site where decontamination occurs.
standard.
3.1.5 decontamination—the process of removing or reduc-
1.9 This standard does not purport to address all of the
ing to a known level undesirable physical, chemical, or
1 2
This practice is under the jurisdiction of ASTM Committee D-18 on Soil and Annual Book of ASTM Standards, Vol 04.09.
Rock and is the direct responsibility of Subcommittee D18.14 on Geotechnics of Annual Book of ASTM Standards, Vol 12.02.
Waste Management. Available from Superintendent of Documents, U.S. Government Printing
Current edition approved Sept., 15, 1994. Published October 1994. Office, Washington, DC 20402.
D 5608
radiological constituents from equipment. Decontamination of 3.1.14 rinse water—water having a known chemistry.
sample contacting equipment maximizes the representative- Deionized or distilled water may be used when small quantities
ness of the physical, chemical, or radioactive analyses pro- are required. When large quantities are required, potable water
posed for a given sample. of a chemistry known to be free (below detection levels) of
radioactive or chemical constituents can be used.
3.1.6 fixed contamination—radioactive material that cannot
3.1.15 sample contacting equipment—equipment and tools
be readily removed from surfaces by nondestructive means,
that physically come in contact with a sample and that could
such as casual contact, wiping, brushing, or washing.
allow cross-contamination from one sample to another. Ex-
3.1.7 inorganic desorbing agents—acid rinse solutions,
amples include drive cylinders, bailers, sample handling,
typically of 10 % nitric or hydrochloric acid solutions made
equipment, pumps, and sampling tubes.
from reagent grade nitric or hydrochloric acid and deionized
3.1.16 survey—a radiation measurement with instrumenta-
water (1 % should be applied to low-carbon steel equipment).
tion to evaluate and assess the presence of radioactive materials
3.1.8 mixed wastes—wastes containing both radioactivity
or other sources of radiation under a specific set of conditions,
(as defined by the Atomic Energy Act) and quantities of
(also known as frisking).
Resource Conservation and Recovery Act (RCRA) listed
3.1.17 unrestricted release limit—the maximum contamina-
wastes.
tion that an item may exhibit to be released for uncontrolled
3.1.9 non-contacting equipment—equipment used in and
use by the public. Release limits differ, based on the type of
around the sampling that may become contaminated, but that
radioactive materials and the amount and type of emissions
does not contact the sample at anytime. Examples would
(gamma, alpha, beta).
include drilling rigs, hand tools, drill rods, excavation equip-
3.1.18 wipe test—a radiation detection test performed to
ment, or barrier materials.
determine the amount of removable radioactive material per
3.1.10 organic desorbing agents—solvent rinse solutions of
100 cm surface area by wiping with a dry filter or soft
isopropanol, acetone, hexane, or methanol; pesticide grade.
absorbent paper with moderate pressure and then assessing the
3.1.11 QC water (control rinse water)—water having a
amount of radioactivity with an instrument of appropriate
known chemistry, free (below detection levels) of organic or
efficiency. A radiological survey and a wipe test is generally
radiological constituents. Deionized water of reagent grade is
required for release of any equipment from a radiological area
normally sufficient.
to an uncontrolled area or for unrestricted use, (also known as
3.1.12 radioactive waste—waste containing radioactive el-
swipe test).
ements or activation regulated under the Atomic Energy Act,
and is of negligible economic value, considering the cost of
4. Summary of Practice
recovery. Waste is classified into three levels, all of which are
4.1 This practice provides guidance and details for the
harmful. The classifications are:
development of a site and sampling event specific decontami-
3.1.12.1 low level waste—wastes usually containing small
nation plan for use in the decontamination of field equipment
amounts of radioactivity in a large amount of material. Typi-
used during sampling or other activities in areas known, or
cally the radioactivity dissipates in a relatively short period of
suspected of containing low-level radioactive wastes. Four
time, anywhere between 500 and 600 years, although some low
techniques or test methods are provided, with the selection and
level wastes may remain radioactive for longer periods. Ex-
use based on the type of contamination and the difficulty of
amples of Low Level Wastes are Uranium mining and mill
removal.
tailings, soils, equipment, sludges, or liquids contaminated
4.2 Approaches and procedures are provided for decontami-
with or mixed with radioactive materials. Naturally Occurring
nation of two classifications of equipment, sample-contacting
Radioactive Materials (NORM) also fall into this classification.
and non-contacting.
Typical examples of NORM low level wastes include uranium
4.3 This practice includes the principles of ALARA and
and thorium bearing sludges from water purification plants,
waste minimization as well as the protection of sample data
high grade uranium ores, and petroleum pipeline sludges.
quality.
3.1.12.2 mid level (transuranic) wastes—wastes containing
5. Significance and Use
contamination with radioactive man-made elements having
atomic weights greater than uranium (hence the name trans (or
5.1 The primary objectives of work at low-level radioactive
beyond) uranic). Examples of mid level wastes include liquids,
waste sites are the protection of personnel, prevention of the
sludges, resins, or soils and equipment contaminated or mixed
spread of contamination, minimization of additional wastes,
with plutonium or other man-made alpha emitting radionu-
protection of sample data quality, and the unconditional release
clides with half-lives of greater than 20 years and concentra-
of equipment used.
tions greater than 100 nCi/g at the time of assay.
5.2 Preventing the contamination of equipment used at
3.1.12.3 high level wastes—wastes of highly concentrated low-level radioactive waste sites and the decontamination of
radionuclides with long half-lives. Examples of high level
contaminated equipment are key aspects of achieving these
wastes include spent nuclear fuels, nuclear fuel reprocessing
goals.
wastes, syrups, and resins.
5.3 This practice provides guidance in the planning of work
3.1.13 removable contamination—radioactive material that to prevent contamination and when necessary, for the decon-
can be removed from surfaces by nondestructive means, such tamination of equipment that has become contaminated. The
as brushing, wiping, or washing. benefits include:
D 5608
5.3.1 Minimizing the spread of contamination within a site selected for wet work involving the specific chemicals and
and preventing the spread outside of the work area. solutions to be used.
5.3.2 Reducing the potential exposure of workers during the 6.7 Chemicals and solutions used during decontamination
work and the subsequent decontamination of equipment. may be hazardous. Personnel involved should be properly
trained and provided with Material Safety Data Sheets (MS-
5.3.3 Minimizing the amounts of additional wastes gener-
DSs), and the appropriate emergency equipment.
ated during the work, including liquid, or mixed wastes,
6.8 Some equipment will degrade or produce deleterious
including separation of the waste types, such as protective
clothing, cleaning equipment, cleaning solutions, and protec- reactions when in contact with decontamination solutions.
tive wraps and drapes. Equipment and decontamination solution compatibility and
resistance should be considered when selecting equipment and
5.3.4 Improving the quality of sample data and reliability.
the decontamination method.
5.4 This practice may not be applicable to all low-level
6.9 Decontamination methods may be incompatible with
radioactive waste sites, such as sites containing low-level
hazardous substances being removed and cause reactions that
radioactive wastes mixed with chemical or reactive wastes.
produce heat, toxic fumes, or explosions. The potential for
Field personnel, with assistance from trained radiological
incompatible material reactions should be evaluated as a part of
control professionals, should have the flexibility to modify the
the decontamination process selection.
decontamination procedures with due consideration for the
sampling objectives, or if past experience supports alternative
7. General Procedures
procedures for contamination protection or decontamination.
5.5 This practice does not address the monitoring, protec-
7.1 Adequate planning is required prior to any activity in an
tion, or decontamination of personnel working with low-level
area known or suspected to contain low-level radioactive or
radioactive wastes.
other wastes and contamination. The development of an
5.6 This practice does not address regulatory requirements
equipment decontamination plan should be a part of the
that may control or restrict work, the need for permits or
activity planning. All personnel involved in the work should be
regulatory approvals, or the accumulation or handling of
familiar with the plan and trained in the specific decontamina-
generated wastes.
tion procedures. Work and decontamination planning should
include the following:
6. Hazards
7.1.1 The site location, conditions, known areas of surface
and subsurface contamination.
6.1 Equipment decontamination activities involving radio-
7.1.2 The type, activity level, potential locations of mixed,
active constituents provide numerous opportunities for person-
chemical, or reactive contamination or wastes,
nel contamination and radiation exposure, the uncontrolled
spread of contamination, and the unnecessary generation of 7.1.3 The location of other physical hazards, such as under-
ground utilities, overhead powerlines, and existing waste
additional radioactive or mixed wastes.
storage locations.
6.2 Personnel involved in the decontamination of field
equipment used in a known or suspected radiologically con- 7.1.4 Emergency responses plans, including emergency de-
contamination of personnel or equipment, site evacuation and
taminated site must be trained and qualified in the work being
performed and in emergency procedures. accountability, and response to fire, explosion, or other situa-
tions that may occur.
6.3 Any work performed in a know
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