Uranium Concentrates Industry Good Practices for ISO Containers
in Multimodal Transports– Revision 0
WNTI STANDARD
Dedicated to the safe, efficient and reliable transport of radioactive materials
WORLD NUCLEAR TRANSPORT INST I TUTE
WNTI
1. Introduction 5
2. Objectives and Scope 6
3. Terminology 7
4. Drum Features 11
5. ISO Container Features 13
6. Loading and Securing (Packaging) Drums into ISO Containers 15
7. Release of ISO Containers 17
8. Bibliography 19
Appendix 1 20
Appendix 2 21
Appendix 3 22
Appendix 4 26
Contributors and credits 27
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Uranium Concentrates Industry Good Practices for ISO Containers in Multimodal Transports– Revision 0
Table of contents
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This publication is intended as a guide only. The official documentscited in the text must be consulted for a definitive description of theirpurpose and contents.
First Edition published in February 2008by World Nuclear Transport Institute, Remo House, 310-312, Regent Street, London, W1B 3AX
© World Nuclear Transport Limited, 2008
home contents 1. introduct ion
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This document is specific for natural uranium concentrates,
which are transported as Class 7 (radioactive) materials
and identified as UN2912. These uranium concentrates are
shipped from uranium mine/mill or other facilities worldwide
to commercial toll uranium conversion or other facilities
globally. This document reflects the packing aspects that
are applicable to producer and converter tooling.
Uranium concentrates are typically packaged in open
head steel drums and shipped in dry sea (ISO) containers.
This publication covers transports that typically include a
marine logistic component. This document provides
information about good industry practices,
which are intended to complement the regulations
that are applicable to specific shipment logistics.
1. Introduction
The scope of this document is to describe common industry
good practices for packaging and loading dry ISO containers
for shipment by marine, road and/or rail modes of transport.
It reflects current packaging and shipping methods that are
compatible with the processes existing at the conversion
facilities in the toll conversion business. The aspects of
shipping that are covered in this document are as follows:
2.1 Drums
2.2 ISO Containers
2.3 Loading and Securing (Packing) Drums into ISO
Containers
2.4 ISO Container Release
This document is intended for use by WNTI Member
companies as well as all other stakeholders in the
transportation of uranium concentrates.
2. Objectives and Scope
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These are the terms that are used throughout this
document. In the document the word “shall”
indicates a requirement, the word “should” indicates a
recommendation and the word “may” indicates permission.
3.1 ACEP – Approved Container Examination
Program (under the CSC).
3.2 Activity – Measure of radioactive disintegrations
per unit time, the SI unit of activity is the
Becquerel.
3.3 Anchor Points – Securing devices located at the
base structure of the container at the top and
bottom with a restraint capacity of 1000 kg
in any direction [reference 8.7].
3.4 Background Instrument Count Rate – The normal
level of radioactivity within the location not
originating from the object to be measured.
3.5 Becquerel – The SI unit for activity.
One Becquerel is equal to one disintegration
per second (dps).
3.6 Bulk Density – Weight per unit volume for
the uranium concentrate powder.
3.7 Bung Hole – Hole in the centre of the lid through
which the drum is filled.
3.8 Centre Load Lid – Drum lid with bung hole in the
centre that is sealed for handling and transport.
3.9 Chine – Circumferential ridge(s) in a drum profile.
3.10 Corded Polyester Rated Strapping – Strapping
of this type with a specific strength rating.
3.11 Clip Ring – Type of metal drum lid ring with a
torsion clip arrangement to hold the ring in place.
3.12 Consignee – Receiver of ISO container
of uranium concentrate cargo.
3.13 Consignor – Dispatcher of ISO container
of uranium concentrate cargo.
3.14 Contamination (fixed) – This is contamination
other than non-fixed contamination
[reference 8.1].
3.15 Contamination (non-fixed) – This is
contamination that can be removed from a
surface during routine conditions of transport
[reference 8.1].
3.16 Converter – Facility that processes natural
uranium concentrates, typically to natural
uranium hexafluoride (UF6).
3.17 CSC – International Convention for Safe
Containers, 1972 [reference 8.3].
3.18 CSC Plate – A safety approval plate fixed to the
external surface of an ISO container (usually
the door) bearing construction, loading, and
maintenance information [reference 8.3].
3.19 Dedicated Use – A container in this use is utilised
solely for radioactive materials transport and it
is not released back into the general container
pool. This definition is provided to distinguish
dedicated use from exclusive use.
3.20 Detection Efficiency – The percent efficiency
with which a radiation meter detects.
3.21 Direct Fixed Point Measurement – Measurement
of specified points within the ISO container.
Direct measurement will measure both fixed
and non-fixed contamination.
3.22 Double Tier Loading – Where a second layer of
drums is loaded on top of the first layer within
the ISO container.
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3. Terminology
3.23 Drum – A good quality metal drum, examples
of the drum styles are as follows:
3.24 Dunnage – Materials of various types, usually
timber, placed into the ISO container to brace the
drums to prevent damage due to movement of
the drums during transport. Wood dunnage shall
be phytosanitary compliant in most jurisdictions.
3.25 Exclusive use – In this application, a container
is in exclusive use when it is loaded by the
consignor and it travels to the consignee under
the direction of either the consignor or consignee
[reference 8.1].
3.26 Filling – The process of filling the drums with
uranium concentrate.
3.27 Free Release – Release of an uncontaminated
ISO container that can be sent back for use with
general cargo and that does not require transport
under the radioactive materials regulations.
By definition the ISO container is free released
when it is uncontaminated [reference 8.1,
paragraph 214].
3.28 Galvanized – Zinc coated.
3.29 Gross Weight Capacity – The total approved
weight including the ISO container and contents
as marked on the CSC plate.
3.30 IAEA – International Atomic Energy Agency.
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Conventional style drum,complete with a double chine:
Nesting style drum (i.e. will nest when stacked empty, no lower chine):
boltedring
chine
chine
boltring
chin
chin
chine
boltedring
chine
boltedring
chine
chine
3.31 IMDG – International Maritime Dangerous Goods
Code.
3.32 IMO – International Maritime Organization.
3.33 ISO – International Organization for
Standardization.
3.34 ISO Container – A freight container constructed
to the specifications of ISO 1496-1 and that is
CSC compliant [references 8.3 and 8.7].
3.35 Lashing Points – Securing devices located in
any part of the container other than the base
structure (other than anchor points) with restraint
capacity of 500 kg in any direction [reference 8.7].
3.36 Lid – Steel lid of drum.
3.37 Lid Centre Hole – Filling hole in Centre Load Lid.
3.38 Open Head – Removable lid that is the entire
circumference of the drum.
3.39 Packaging – Receptacles in which material is
contained. Both drums and ISO containers
can be packaging.
3.40 Phytosanitary Compliant – Meets the relevant
national regulations covering the import of
lumber dunnage [reference 8.6].
3.41 Producer – Facility (or facilities), which processes
natural uranium ore to uranium concentrates.
Typically this is a mill associated with a mining
operation.
3.42 Product Identification Marking – Marking on
a drum to identify specific Lot and/or Batch
of concentrate.
3.43 Rated Design Maximum – Maximum Net weight
of concentrate that the drum is designed to
contain (alternately this may also be expressed
as a maximum gross weight capacity).
3.44 Responsible Person – Suitably authorized and
qualified person.
3.45 Restraint Longitudinal/Lateral/Vertical – This is
described in reference 8.2 (Appendix V tables)
and reference 8.5.
3.46 Ring – Semi circular metal fastening which holds
the lid to the drum.
3.47 Ring Gauge – Thickness of the metal ring.
3.48 Routine Conditions of Transport – This is
described in reference 8.1.
3.49 Seal – Anti-tamper device on container door
to indicate unauthorized access in transport.
3.50 Secular Equilibrium – Following chemical
purification, uranium concentrates achieve
a stable level of radioactivity (activity) referred
to as secular equilibrium within less than six
months of production.
3.51 Single Tier Loading – Where only a single layer
of drums is loaded within the ISO container.
3.52 Structural Member – Support that is a constituent
part of any structure or building.
3.53 Top Bolted Ring – Type of lid ring where bolt sits
above drum lid rather than the side, thus
preventing stacking.
3.54 Traceable Calibration Source – Radioactive source
of certified activity used to check the monitoring
equipment.
3.55 Uranium Concentrates – Chemical compounds
of natural uranium originating from natural ores.
Usually in dry powder form. Term includes
yellowcake, uranium oxide and uranium ore
concentrate (UOC).
3.56 Wafering – Use of boards or equivalent materials
within the ISO container to spread any point loads.
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3.57 Wipe Papers – Paper that is used to rub (wipe)
the surface to be measured for non-fixed
contamination.
3.58 Wipe Samples – See Wipe Papers, samples taken
by this method.
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Drums are typically handled a number of times (may be up
to 10 times) in a single fill-to-empty life cycle for one drum
(producer to converter) and they may also be recycled for
reuse. Some national regulations may have particular
requirements for the style of these drums, such as the use
of centre load type lids. Drums shall be filled to weights
no greater than the rated design maximum for the drum.
4.1 Lids and Rings
4.1.1 Bolted ring style lids shall only be used.
4.1.2 Welding shall not be used on the bolts on
the rings nor top bolted rings, examples are
illustrated as follows:
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4. Drum Features
Top bolted locking ring (unwelded) Side bolted locking ring (welded)
� weld materialweld material �
4.1.3 Clip rings shall not be used. These rings tend
to be less reliable and can potentially open
on impact during transport.
4.1.4 The drum ring profile (“C” or “U”) shall be
matched to the profile of the drum rim and lid.
4.1.5 For drums that are loaded through a centre hole
in the lids, the lids shall have effective water
proof seals on the bung holes that will last for
long term (multiple months) of storage time.
4.1.6 The rings shall have sufficient strength and
durability for re-use (this allows for the in-life
cycle opening and closing of a drum ring for
activities such as sampling).
4.2 Drums
4.2.1 Drum style shall be open head steel.
4.2.2 Both nesting and non-nesting types are in routine
use by industry, but may be specified by the
parties.
4.2.3 The drum size shall be a nominal 210L
(45 imperial gallon/55 US gallon) per drum.
Alternate drum sizes such as 140L (30 imperial
gallon/37 US gallon) may be used as agreed
by the parties.
4.2.4 The drums shall not have galvanized interiors
or other (including organic) coatings on the
interior surface.
4.2.5 In addition to label(s) and marking that may be
required to be compliant with the applicable
transport regulations, for convenience in
handling, the drums should have uniform product
identification marking (as a minimum the lot
number, drum number as well as gross, tare
and net weight) at two sides, 180˚ apart.
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“C” or “U” section locking rings with high durability and re-usage capability Centre fill lids with effective waterproof seals
5.1 Type of ISO Container
5.1.1 Twenty foot (20’) dry van type, full height heavy
duty ISO containers.
5.1.2 Minimum gross weight capacity greater than
24 tonnes (48,000 pounds).
5.2 Features of the ISO Container
5.2.1 Containers shall be compliant with ISO 1496-1
[reference 8.7].
5.2.2 Container features shall include a minimum of
10 anchor points as specified in reference 8.7.
Containers are preferred to have a total of 20
anchor points and an equal number of anchor
points on the top and bottom (5 bottom and 5
top on each side). The preference for 20 anchor
points is related to the use of chorded strapping.
5.2.3 Containers shall be equipped with fork pockets
for fork lift truck tynes (forks) and with the
design capacity for lifting a fully loaded container.
5.2.4 Containers shall be free of holes or cracks that
may allow the entry or discharge of material
or moisture into or from within the container.
See the Checklist in Appendix 3.
5.2.5 Containers shall have adequate door seals that
prevent the entry or discharge of material or
moisture into or from within the container.
5.2.6 At least one of the locking handles on each
container door shall have a hole capable of
allowing the placement of a container seal.
5.2.7 Containers shall be compliant with the
International Convention for Safe Containers
(CSC), including having a current CSC plate
or ACEP marking attached.
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5. ISO Container Features
CSC plate with current examination date markingsCSC plate with ACEP marking
APPROVED FOR TRANSPORTUNDER CUSTOMS SEAL
MANUFACTURER’S NO.OF THE CONTAINERTYPE XXX-XXXXXXXXXX XXX-XXXXXXXXXX
MANUFACTURED BY:
OWNER:XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
TIMBER COMPONENT TREATMENTXXXXXXXXXX XX-XX/XXXX
CSC SAFETY APPROVALX/XX/XXXX/XX
DATE MANUFACTURED
IDENTIFICATION NO.
MAXIMUM GROSS WEIGHT
ALLOW STACK WT. FOR 1.8G
RACKING TEST LOAD VALUE
XX/XXXX
XXXX XX XXXX XX
XX,XXX KGS XX,XXX LBS
XXX,XXX KGS XXX,XXX LBS
XX,XXX KGS XX,XXX LBS
ACEP
XX
XXXX
XXXX
XXX
XXXXXXXXXXXXXXX XXXXX XXXXXXXX XX XXX
XX/X XXXX XX/XXXX
XXXX
APPROVED FOR TRANSPORTUNDER CUSTOMS SEAL
XX/X XXXX XX/XXXX
MANUFACTURER’S NO.OF THE CONTAINERTYPE XXX-XXXXXXXXXX XXX-XXXXXXXXXX
MANUFACTURED BY: MANAGED AND OPERATED BY:
XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
TIMBER COMPONENT TREATMENT XX/XXXXXXXX XX-XX/XXXX
CSC SAFETY APPROVALX/XX/XXXX/XX
DATE MANUFACTURED
IDENTIFICATION NO.
MAXIMUM GROSS WEIGHT
ALLOW STACK WT. FOR 1.8G
RACKING TEST LOAD VALUE
XX/XXXX
XXXX XX
XX,XXX KGS XX,XXX LBS
XXX,XXX KGS XXX,XXX LBS
XX,XXX KGS XX,XXX LBS
FIRST MAINTE-NANCE EXAMI-NATION DATE
/200XX X
(PLACERE-EXAMINATIONDECAL HERE)
XXXX XX
XXXX XXXXXXXX XXX XXXXXXXXXXXXXXX XXX XXXXXXXXXXX
5.3 Receipt Handling and Preparation for Loading
(Packing) of the ISO Container
5.3.1 Before loading the consignor shall carry out
a receipt inspection of the ISO container.
5.3.2 If the ISO containers are repaired or modified,
this shall be done in accordance with CSC and
ISO 1496-1 requirements. A sample pre-use
inspection checklist is shown in Appendix 3.
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The consignor shall check drums for non-fixed
contamination prior to loading. The non-fixed radioactivity
shall be less than 0.4 Bq/cm2 for loading into ISO containers
that are not in dedicated service. This is to avoid cross
contamination and the need for additional cleaning by the
consignee prior to the release of the container (the container
is released as uncontaminated by definition when it is
returned to the owner and it is not in dedicated service).
This may be done by using either alpha or beta
measurement.
In taking wipe samples particular attention should be given
to the bottom of the drum at the seam.
In determining load configurations, packers shall consider
the relationship between maximum road Gross Container
Weights (GCW) and the converter capabilities relating to
their maximum handling capacity for loaded drums.
Drums may be secured into the ISO container in either a
single or double tier configuration. Uranium concentrates
typically have a high bulk density hence the second tier is
normally not fully loaded by volume with drums due to
container and/or road weight limitations.
6.1 Preparation for Loading
6.1.1 The consignor shall ensure that there are written
procedures for packing the ISO container and the
procedures shall be followed by the facility
carrying out the packing.
6.1.2 Any ISO container that is not in dedicated service
shall be checked on receipt to ensure that it is
uncontaminated prior to loading (less than 0.4
Bq/cm2 fixed plus non-fixed). As a minimum,
the internal surfaces of the container should be
checked according to section 7 of this document.
6.2 Loading and Securing in the ISO Container
6.2.1 Drums shall be loaded with dunnage and/or
lashing to effectively restrain them from shifting
under routine conditions of transport.
6.2.2 The drums shall be evenly distributed in the ISO
container, especially for a partial second tier.
6.2.3 The second tier shall be separated from the
first (lower) tier using wafering to improve skid
resistance and to minimize the opportunity for
movement during transit.
6.2.4 Chorded polyester (or equivalent) rated strapping
is typically used to secure drums.
6.2.5 Wherever timber dunnage is used, the securing
shall be done only with lumber that is
phytosanitary compliant.
6.2.6 Timber dunnage may be used in combination
with chorded strapping. It is preferable to limit
the use of timber dunnage to the extent practical.
6.2.7 Additional anchor and/or lashing points may
be added but shall be done in compliance with
reference 8.3 and 8.7 and with consideration for
the commercial arrangements (and restrictions)
for the use of the container. Any modification
and repair of CSC containers shall be carried
out by an authorised party.
6.2.8 The drums shall be handled to prevent loss
of containment (e.g. prevent puncture, etc.)
during loading and related handling. If a drum
is punctured on loading, it shall be removed
and any resulting contamination cleaned up.
6.2.9 If a drum is deformed (including puncture) such
that it poses a risk to the integrity of the drum, it
shall be removed and any contamination cleaned
up. For example, a significant crease in a drum
may result in loss of containment during transport.
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6. Loading and Securing (Packing) Drums into ISO Containers
6.2.10 Drums shall be restrained to meet the
longitudinal, lateral and vertical requirements of
the applicable transport regulations. In particular,
consideration shall be given to prevent drums
from locking and hanging on each other during
transport because this can cause damage
(including displacement of the lid and drum
deformation).
6.2.11 The void space shall be blocked with dunnage
between the cargo and the container doors in
order to allow the container doors to be opened
safely following transport; alternatively other
methods of equivalent securing may be utilised.
6.2.12 The tires of mobile equipment that travel over the
container floor for loading drums shall be free of
contamination in order to prevent the container
floor from becoming contaminated. In addition,
a good practice is to lay down material such as
conveyor belting for the mobile equipment to
travel on.
6.2.13 Cargo restraint shall be compliant with the
requirements of reference 8.5 listings for g force
restraint minimums with particular attention to
the logistic being used, especially when the
logistic includes rail shunting.
6.2.14 Samples of uranium concentrate may be
transported in the same container as the
drummed uranium concentrate cargo.
They shall be packaged according to the
appropriate regulations and secured
in the container.
6.3 Post Loading (Pre-shipment) Inspection
6.3.1 The ISO container shall be pre-shipment
inspected to ensure compliance with the
requirements for placarding, labeling, cleanliness
and damage to the outside of the container.
See Appendix 4 for a sample pre-shipment
inspection checklist.
6.3.2 The ISO container doors shall be fully and
securely closed with all locking bolts engaged.
6.3.3 When closed, ISO container doors shall be sealed
shut with at least one numbered seal. In some
jurisdictions certified seals and or consecutive
numbered seals may be required to be fitted
to each door with numbering details recorded
within the transport documentation.
6.4. Converter (Consignee) Receipt Inspection
6.4.1 As a minimum, the consignee shall check every
ISO container with a visual examination for load
shift and/or loss of containment.
6.4.2 If a load shift or loss of containment is identified,
it is recommended that photographs be taken
and provided to the consignor in addition to
any other reporting that is done.
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Typically ISO containers are returned empty and free released
as uncontaminated back to the owner after unloading by
the consignee (for general container pool use).
Alternately, ISO containers may be transported empty but
not free released provided they remain in dedicated use and
they are transported as required under the regulations for
the transport of radioactive materials.
For free release as uncontaminated, the container shall be
checked and certified by the consignee to have fixed plus
non-fixed contamination that is less than 0.4 Bq/cm2.
Uranium concentrates are comprised primarily of two (2)
alpha emitters, 238U and 234U and two (2) beta emitters,234Pam and 234Th. Once secular equilibrium is established,
the total alpha activity will equal the total beta activity;
therefore, radioactivity measurements may be conducted
by either direct alpha measurement or by direct beta
measurements (these measurements are not additive).
Site specific considerations will determine which method
is used by a particular site.
7.1 Container Free Release Procedure
Prior to release of a container from the consignee for
general use (free release), the following activities shall be
conducted and survey results recorded:
7.1.1 If any packages are found to be leaking on
receipt by the consignee, reporting shall be
done as required by commercial and regulatory
reporting requirements.
7.1.2 A thorough inspection of the container shall
be conducted including a check for visible
contamination and a measurement (scan) of the
whole floor surface. In addition, direct fixed
point measurements shall also be done at other
representative surfaces for total radioactivity.
These measurements shall be done to determine
compliance with the IMDG Code for exempted
values (release as uncontaminated). Non-
compliance will result in decontamination
activities and a repeat inspection survey.
7.1.3 The direct fixed point measurements of total
radioactivity shall be conducted in at least six (6)
prescribed locations and the maximum observed
total radioactivity value is documented in Bq/cm2
(as averaged over 300 cm2). The prescribed
minimum locations are the floor at the front,
floor at the center, floor at the back, inside wall
of the container facing right, inside wall of the
container facing left and an external wall of the
container near the doors. A diagram showing
these locations is attached in Appendix 1.
7.1.4 Wipe samples for non-fixed contamination
shall also be collected at the six (6) prescribed
locations and analysed by either alpha or
beta counting.
7.1.5 Using the radiation surveyor’s documentation,
the responsible person shall indicate compliance
on the release certification documentation.
A sample release certificate form is attached
in Appendix 2.
7.1.6 Any value showing fixed plus non-fixed
contamination greater than 0.4 Bq/cm2
(as averaged over 300 cm2) shall result
in decontamination activities and a repeat
inspection survey.
7.2 Requirements for Measurement of
Total Radioactivity
Facility procedures for surface scans and direct fixed point
measurements for determination of total radioactivity shall
comply with the following requirements:
7.2.1 Survey instruments shall be calibration checked
at least annually using a traceable calibration
source.
7.2.2 A performance check of the survey instrument
shall be performed prior to the clearance survey,
on the day of the survey, to confirm proper
instrument operation.
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7. Release of ISO Containers
7.2.3 An instrument background reading shall
be determined prior to instrument use.
7.2.4 Surveyors shall be trained in the use of the survey
meter. Training and qualifications for surveyors
shall be documented.
7.2.5 Background instrument count rate shall be
subtracted from the total count rate when
determining total activity.
7.2.6 Calculations of activity shall take the detection
efficiency of the instrument into account.
7.2.7 If floor scan results and the individual fixed point
measurements are less than 50% of the release
level, this provides a good assurance for release.
Values above this should be cause to investigate
by increasing the number of fixed point checks.
7.3 Requirements for Measurement of Removable
Radioactivity
Facility procedures for determination of removable
(non-fixed) radioactivity shall comply with the following
requirements:
7.3.1 Survey instruments shall be calibration checked
at least annually using a traceable calibration
source.
7.3.2 Wipes shall be assumed to have a pick-up
efficiency of 10% [reference 8.2, paragraph
508.2].
7.3.3 Wipe papers shall be provided by a commercial
supplier.
7.3.4 A performance check of the survey instrument
shall be performed prior to the clearance survey,
on the day of the survey, to confirm proper
instrument operation.
7.3.5 An instrument background reading shall be
determined prior to instrument use.
7.3.6 Surveyors shall be trained in the use of the survey
meter. Training and qualifications for surveyors
shall be documented.
7.3.7 Wipes shall be taken by applying gentle pressure
over the surface being wiped.
7.3.8 The surface area wiped shall be reported on
a per cm2 basis and as averaged over an
area of 300 cm2.
7.3.9 Each wipe sample shall be counted for
a minimum of one minute.
7.3.10 The activity of each wipe sample shall be
calculated taking into account the efficiency
of the scaler as well as the wipe efficiency.
7.3.11 If wipe sample results are less than 25% of the
release levels, this provides good assurance for
release. Values above this should be cause to
investigate by taking additional wipe samples.
home contents 7. release of ISO containers
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8.1 IAEA Transport Regulations TS-R-1, 2005 edition,
International Atomic Energy Agency, Vienna,
August 2005, www.iaea.org/books
8.2 IAEA Advisory Material TS-G-1.1, 2002 edition,
International Atomic Energy Agency, Vienna,
June 2002, www.iaea.org/books
8.3 International Convention for Safe Containers,
1972, CSC 1996 edition, International Maritime
Organization, publication number IA282E,
www.imo.org
8.4 IMDG Code, Volumes 1 and 2, 2006 edition,
incorporating amendment 33-06, International
Maritime Organization, publication number
IF200E, www.imo.org
8.5 IMO/ILO/UN ECE Guidelines for Packing of
Cargo Transport Units, IMDG Code Supplement,
amendment 33-06, publication number IF210E,
www.imo.org
8.6 International Standard for Phytosanitary
Measures, Guidelines for Regulating Wood
Packaging Material in International Trade,
ISPM 15, Secretariat of the International Plant
Protection Convention Food and Agriculture
Organization of the United Nations, Rome, 2002,
www.ippc.int
8.7 ISO 1496-1, International Standard for Series 1
freight containers - Specification and testing -
Part 1: General cargo containers for general
purposes, 1990 and amendments 1-5,
www.iso.org
8.8 Institute of International Container Lessors,
Guide for Container Equipment Inspection, 2005,
www.iicl.org
8.9 Container Handbook, Volume I, II, III; Cargo loss
prevention information from German marine
insurers, GDV Die Deutschen Versicherer,
www.containerhandbook.de
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8. Bibliography
1. Floor at front of container.
2. Centre of floor inside container.
3. Floor at back of container.
4. Inside right hand wall of container near doors.
5. Inside left hand wall of container near doors.
6. Outside of doors at lower edge.
home contents appendix 1
2 0
Appendix 1 – Six Minimum Prescribed Locations in an ISO Container
3
2
1
6
5 4
Insert company logo here
CONTAINER CERTIFICATE OF INSPECTION
Container: __________________________________________________ Date: _________________________________
The freight container identified above has been monitored at the insert facility location here and found to be free of radioactive
contamination as defined in the latest applicable edition of the IMDG Code.
CONTAMINATION means the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm2, fixed
plus non-fixed, for beta and gamma emitters and low-toxicity alpha emitters. Natural uranium is a low-toxicity alpha emitter.
Natural uranium concentrates are comprised primarily of two (2) alpha emitters, 238U and 234U and two (2) beta emitters, 234Pam and 234Th. Once secular equilibrium is established, the total alpha activity will equal the total beta activity therefore
radioactivity measurements may be conducted by either alpha measurement or by beta measurements. Contamination
is measured as averaged over 300 cm2, reference the applicable edition of the IAEA TS-R-1 Regulations for the
Safe Transport of Radioactive Material.
Signature:
Insert name and title
Insert email address
Insert telephone number
home contents appendix 2
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Appendix 2 – Sample Container Release Certificate Form (variable text shown in italics)
EXTERIOR INSPECTION
A3.1 Examination of the CSC plate:
– correct fixation (cannot be removed easily);
– approval number;
– date of manufacture;
– identification number (shall be that of the container);
– maximum gross weight;
– allowed stacking weight for 1.8 G;
– racking testing load value;
– either last dates of examination (valid for 5 years for less 5 year old containers,
valid for 30 months for more 5 years old containers) or confirmed ACEP approval
scheme of the owner.
A3.2 Examination of the main framework (corner posts, corner fittings, bottom and top
side rails, bottom and top end rails, door sill and header) – no major defects:
– dents or bends in structural members (including under floor cross members)
greater than 19 mm in depth, regardless of length;
– cracks or breaks in structural members (including under floor cross members);
– more than one splice or an improper splice (e.g. a lapped splice) in top or
bottom end rails or door headers or more than two splices in any one top
or bottom side rail or any splice in a door sill or corner post;
– door hinges and hardware that are seized, twisted, broken,
missing or otherwise inoperative;
– non-closing gaskets and seals;
– any distortion of the overall configuration sufficient to undermine proper
alignment of handling equipment, mounting and securing on a chassis or vehicle.
A3.3 Examination of the doors: they shall work properly and be capable of being securely
locked and sealed in the closed position, and properly secured in the open position;
gaskets shall be in good condition and be tight when doors are closed.
A3.4 Examination of the marking and labelling: irrelevant markings, labels, placards, orange
panels, signs and marine pollutant marks shall be removed or masked.
Signature and date
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Appendix 3 – Pre-use Inspection Checklist for ISO Containers
INTERIOR INSPECTION
A3.5 The interior surfaces shall be clean, dry and free of residue and persistent odours
from previous cargo. Walls, roof and floor shall be exempt of rust.
A3.6 The floor shall be in good condition to facilitate its decontamination at consignee’s
place and to avoid any escape of uranium concentrate in case of failure of on or more
packages during the voyage: no cracks, breaks, holes, protruding nails or screws.
A3.7 Examination of anchor points and lashing points: not seized, twisted, broken,
missing or inoperative (irrelevant if not used for stowage of the cargo).
A3.8 Check the waterproof of the container: Potential point of leakage can be detected
by observing if any light enters the closed container.
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Signature and date
home contents appendix 3
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Container closed
corner posts
dooandhard
side rails
corner fittings door silland header
doors c
container open (REV)
corner posts
door hingesand hardware
side rails
corner fittings door silland header
door open
door closeddoor sill and header
corner fittings
side rails
door hingesand hardware
corner posts
corner posts
door open
door hinges and hardware
door sill and header
corner fittings
side rails
Container open
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Lashing point
Anchor point
The purpose of this checklist is to guide in the safe and contamination free handling and transport of containers packed
with drums of uranium concentrates (cargo). The containers may be loaded on to either road or rail conveyances
(e.g. road trailers or directly on to rail wagons), depending on the logistics being deployed.
A4.1 After packing of a container, it shall be visually inspected for secure loading,
then closed and sealed with numbered seal(s) – seal number(s):
__________________________________________________________________
__________________________________________________________________.
A4.2 Measure and record maximum dose rates and units of measurement (e.g. mSv)
for container surface contact and one (1) meter away from the container.
The one (1) meter value is used to calculate the transport index for the container.
Alternately values for each drum may be used to calculate per the regulations.
A4.3 Check external container marking and labeling (possibly repeat sections of Appendix 3).
A4.4 If the container has been inside a facility area or removed from a road chassis or
flatbed or a rail wagon where there is a risk of contamination – before the full
container leaves this area, a designated person is to ensure that container is cleaned
on sides, top and bottom with high pressure cleaner or appropriate equipment.
Dirt and sand shall be removed from the container bottom seams.
A4.5 If the container was removed from a road or rail conveyance (trailer or wagon), inspect
the empty road or rail conveyance for cleanliness before loading the container.
A4.6 Check the outside surfaces of the container for non-fixed contamination
(wipe sampling) and record the measured values.
A4.7 Record the container and conveyance number.
A4.8 Place placards on road or rail conveyance (if applicable).
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Appendix 4 – Pre-Shipment Inspection Checklist, ISO Container with cargo
Signature and date
home contents contr ibutors
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Catherine Green Cameco Corporation
Chair
Individuals from the following participated
in the development of the paper:
AREVA NC
AREVA Resources Canada
BHP Billiton Ltd
Cameco Corporation
ConverDyn
Electricité de France (EDF)
Honeywell
International Nuclear Services
NUFCOR International Ltd
Paladin Resources
Pebble Bed Modular Reactor (Pty) Ltd (PBMR)
Rio Tinto plc
Rössing Uranium Ltd
RSB Logistic Projektspedition GmbH
TAM International
TN International
Uranium Asset Management Ltd, Westinghouse, UK
World Nuclear Transport Institute (WNTI)
Contributors and credits
Remo House310-312 Regent Street
London W1B 3AXUnited Kingdom
Tel: +44 (0)20 7580 1144Fax: +44 (0)20 7580 5365
Web: www.wnti.co.ukEmail: [email protected]
S1_EN_MAR13_V1
WORLD NUCLEAR TRANSPORT INST I TUTE
WNTI