Each certificate of approval issued by a competent authority for a special arrangement shall include
the following information:
(a) Type of certificate;
(b) The competent authority identification mark;
(c) The issue date and an expiry date;
(d) Mode(s) of carriage;
(e) Any restrictions on the modes of carriage, type of vehicle, container, and any necessary
routeing instructions;
(f) List of applicable national and international regulations, including the edition of the IAEA
Regulations for the Safe Transport of Radioactive Material under which the special
arrangement is approved;
(g) The following statement:
"This certificate does not relieve the consignor from compliance with any requirement of the
government of any country through or into which the package will be carried.";
(h) References to certificates for alternative radioactive contents, other competent authority
validation, or additional technical data or information, as deemed appropriate by the competent
authority;
(i) Description of the packaging by a reference to the drawings or a specification of the design. If
deemed appropriate by the competent authority, a reproducible illustration, not larger than 21
cm by 30 cm, showing the make-up of the package shall also be provided, accompanied by a
brief description of the packaging, including materials of manufacture, gross mass, general
outside dimensions and appearance;
(j) A specification of the authorized radioactive contents, including any restrictions on the
radioactive contents which might not be obvious from the nature of the packaging. This shall
include the physical and chemical forms, the activities involved (including those of the various
isotopes, if appropriate), mass in grams (for fissile material or for each fissile nuclide when
appropriate), and whether special form radioactive material, low dispersible radioactive
material or fissile material excepted under 2.2.7.2.3.5 (f) if applicable;
(k) Additionally, for packages containing fissile material:
(i) a detailed description of the authorized radioactive contents;
(ii) the value of the criticality safety index;
(iii) reference to the documentation that demonstrates the criticality safety of the contents;
(iv) any special features, on the basis of which the absence of water from certain void spaces
has been assumed in the criticality assessment;
(v) any allowance (based on 6.4.11.5 (b)) for a change in neutron multiplication assumed in
the criticality assessment as a result of actual irradiation experience; and
(vi) the ambient temperature range for which the special arrangement has been approved;
(l) A detailed listing of any supplementary operational controls required for preparation, loading,
carriage, unloading and handling of the consignment, including any special stowage provisions
for the safe dissipation of heat;
(m) If deemed appropriate by the competent authority, reasons for the special arrangement;
(n) Description of the compensatory measures to be applied as a result of the shipment being under
special arrangement;
(o) Reference to information provided by the applicant relating to the use of the packaging or
specific actions to be taken prior to the shipment;
(p) A statement regarding the ambient conditions assumed for purposes of design if these are not
in accordance with those specified in 6.4.8.5, 6.4.8.6, and 6.4.8.15, as applicable;
(q) Any emergency arrangements deemed necessary by the competent authority;
(r) A specification of the applicable management system as required in 1.7.3;
(s) If deemed appropriate by the competent authority, reference to the identity of the applicant and
to the identity of the carrier;
(t) Signature and identification of the certifying official.

 

Each certificate of approval for a shipment issued by a competent authority shall include the following
information:
(a) Type of certificate;
(b) The competent authority identification mark(s);
(c) The issue date and an expiry date;
(d) List of applicable national and international regulations, including the edition of the IAEA
Regulations for the Safe Transport of Radioactive Material under which the shipment is
approved;
(e) Any restrictions on the modes of carriage, type of vehicle, container, and any necessary
routeing instructions;
(f) The following statement:
"This certificate does not relieve the consignor from compliance with any requirement of the
government of any country through or into which the package will be carried.";
(g) A detailed listing of any supplementary operational controls required for preparation, loading,
carriage, unloading and handling of the consignment, including any special stowage provisions
for the safe dissipation of heat or maintenance of criticality safety;
(h) Reference to information provided by the applicant relating to specific actions to be taken prior
to shipment;
(i) Reference to the applicable certificate(s) of approval of design;
(j) A specification of the actual radioactive contents, including any restrictions on the radioactive
contents which might not be obvious from the nature of the packaging. This shall include the
physical and chemical forms, the total activities involved (including those of the various
isotopes, if appropriate), mass in grams (for fissile material or for each fissile nuclide when
appropriate), and whether special form radioactive material, low dispersible radioactive
material or fissile material excepted under 2.2.7.2.3.5 (f) if applicable;;
(k) Any emergency arrangements deemed necessary by the competent authority;
(l) A specification of the applicable management system as required in 1.7.3;
(m) If deemed appropriate by the competent authority, reference to the identity of the applicant;
(n) Signature and identification of the certifying official.

Each certificate of approval of the design of a package issued by a competent authority shall include
the following information:
(a) Type of certificate;
(b) The competent authority identification mark;
(c) The issue date and an expiry date;
(d) Any restriction on the modes of carriage, if appropriate;
(e) List of applicable national and international regulations, including the edition of the IAEA
Regulations for the Safe Transport of Radioactive Material under which the design is
approved;
(f) The following statement;
"This certificate does not relieve the consignor from compliance with any requirement of the
government of any country through or into which the package will be carried.";
(g) References to certificates for alternative radioactive contents, other competent authority
validation, or additional technical data or information, as deemed appropriate by the competent
authority;
(h) A statement authorizing shipment where approval of shipment is required under 5.1.5.1.2, if
deemed appropriate;
(i) Identification of the packaging;
(j) Description of the packaging by a reference to the drawings or specification of the design.
If deemed appropriate by the competent authority, a reproducible illustration, not larger
than 21 cm by 30 cm, showing the make-up of the package shall also be provided,
accompanied by a brief description of the packaging, including materials of manufacture, gross
mass, general outside dimensions and appearance;
(k) Specification of the design by reference to the drawings;
(l) A specification of the authorized radioactive content, including any restrictions on the
radioactive contents which might not be obvious from the nature of the packaging. This shall
include the physical and chemical forms, the activities involved (including those of the various
isotopes, if appropriate), mass in grams (for fissile material the total mass of fissile nuclides or
the mass for each fissile nuclide, when appropriate) and whether special form radioactive
material, low dispersible radioactive material or fissile material excepted under 2.2.7.2.3.5 (f),
if applicable;
(m) A description of the containment system;
(n) For package designs containing fissile material which require multilateral approval of the
package design in accordance with 6.4.22.4:
(i) a detailed description of the authorized radioactive contents;
(ii) a description of the confinement system;
(iii) the value of the criticality safety index;
(iv) reference to the documentation that demonstrates the criticality safety of the contents;
(v) any special features, on the basis of which the absence of water from certain void spaces
has been assumed in the criticality assessment;
(vi) any allowance (based on 6.4.11.5 (b)) for a change in neutron multiplication assumed in
the criticality assessment as a result of actual irradiation experience; and
(vii) the ambient temperature range for which the package design has been approved;
(o) For Type B(M) packages, a statement specifying those requirements of 6.4.7.5, 6.4.8.4, 6.4.8.5,
6.4.8.6 and 6.4.8.9 to 6.4.8.15 with which the package does not conform and any amplifying
information which may be useful to other competent authorities;
(p) For packages containing more than 0.1 kg of uranium hexafluoride, a statement specifying
those prescriptions of 6.4.6.4 which apply if any and any amplifying information which may be
useful to other competent authorities;
(q) A detailed listing of any supplementary operational controls required for preparation, loading,
carriage, unloading and handling of the consignment, including any special stowage provisions
for the safe dissipation of heat;
(r) Reference to information provided by the applicant relating to the use of the packaging or
specific actions to be taken prior to shipment;
(s) A statement regarding the ambient conditions assumed for purposes of design if these are not
in accordance with those specified in 6.4.8.5, 6.4.8.6 and 6.4.8.15, as applicable;
(t) A specification of the applicable management system as required in 1.7.3;
(u) Any emergency arrangements deemed necessary by the competent authority;
(v) If deemed appropriate by the competent authority, reference to the identity of the applicant;
(w) Signature and identification of the certifying official.

Each certificate issued by a competent authority for alternative activity limits for an exempt
consignment of instruments or articles according to 5.1.5.2.1 (d) shall include the following
information:
(a) Type of certificate;
(b) The competent authority identification mark;
(c) The issue date and an expiry date;
(d) List of applicable national and international regulations, including the edition of the IAEA
Regulations for the Safe Transport of Radioactive Material under which the exemption is
approved;
(e) The identification of the instrument or article;
(f) A description of the instrument or article;
(g) Design specifications for the instrument or article;
(h) A specification of the radionuclide(s), the approved alternative activity limit(s) for the exempt
consignment(s) of the instrument(s) or article(s);
(i) Reference to documentation that demonstrates compliance with 2.2.7.2.2.2 (b);
(j) If deemed appropriate by the competent authority, reference to the identity of the applicant;
(k) Signature and identification of the certifying official.

The competent authority shall be informed of the serial number of each packaging manufactured to a
design approved by them under 1.6.6.2.1, 1.6.6.2.2, 6.4.22.2, 6.4.22.3 and 6.4.22.4.

Multilateral approval may be by validation of the original certificate issued by the competent authority
of the country of origin of the design or shipment. Such validation may take the form of an
endorsement on the original certificate or the issuance of a separate endorsement, annex, supplement,
etc., by the competent authority of the country through or into which the shipment is made.

6.5

REQUIREMENTS FOR THE CONSTRUCTION AND TESTING OF INTERMEDIATE BULK CONTAINERS (IBCs)

General requirements

Scope

The requirements of this Chapter apply to intermediate bulk containers (IBCs) the use of which is
expressly authorized for the carriage of certain dangerous goods according to the packing instructions
indicated in Column (8) of Table A in Chapter 3.2. Portable tanks and tank-containers which meet the
requirements of Chapter 6.7 or 6.8 respectively are not considered to be IBCs. IBCs which meet the
requirements of this Chapter are not considered to be containers for the purposes of ADR. The letters
IBC only will be used in the rest of the text to refer to intermediate bulk containers.

Exceptionally, IBCs and their service equipment not conforming strictly to the requirements herein,
but having acceptable alternatives, may be considered by the competent authority for approval. In
addition, in order to take into account progress in science and technology, the use of alternative
arrangements which offer at least equivalent safety in use in respect of compatibility with the
properties of the substances carried and equivalent or superior resistance to impact, loading and fire,
may be considered by the competent authority.

The construction, equipment, testing, marking and operation of IBCs shall be subject to acceptance by
the competent authority of the country in which the IBCs are approved.
NOTE: Parties performing inspections and tests in other countries, after the IBC has been put into
service, need not be accepted by the competent authority of the country in which the IBC has been
approved, but the inspections and tests have to be performed according to the rules specified in the
IBC’s approval.

Manufacturers and subsequent distributors of IBCs shall provide information regarding procedures to
be followed and a description of the types and dimensions of closures (including required gaskets) and
any other components needed to ensure that IBCs as presented for carriage are capable of passing the
applicable performance tests of this Chapter.

(Reserved)

(Reserved)

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