1. ------IND- 2016 0081 CZ - EN- ------ 20160308 --- --- PROJET 
Draft  
 
DECREE  
dated  
concerning the Type Approval of some products in the field of peaceful use of nuclear 
energy and ionising radiation and the carriage of radioactive or fissile material  
The S tate Office for Nuclear Safety stipulates, pursuant to §  236 of Act No .../..., the Atomic 
Act (hereinafter the 'Act'), towards the implementation of §  9(4)(a) and (b), §  24(7), §  137(6), 
§ 138(6)(a) to (d), §  141(3)(a) to (e), and §  143(4) of the Act:  
§ 1 
Subject matter  
This decree incorporates relevant Euratom legislation1) and regulates  
a) rules for stipulating fissile materials whose transport is subject to authorisation, their 
classification and requirements they must meet, and identif ications of technical 
requirements for specifying packaging for the carriage of fissile material and 
requirements imposed upon it;  
b) rules for stipulating fissile material whose transport is subject to authorisation, their 
classification and requirements the y must meet, and identifications of technical 
requirements for specifying packaging for the carriage of radioactive material and 
requirements imposed upon it;  
c) requirements regarding the content of documentation for authorisation of carriage of a 
radioactiv e or fissile material;  
d) closer specification of a special form radioactive material, a low dispersible radioactive 
material, and packaging for the transport, storage, or deposit of radioactive or fissile 
materials that are subject to type approval;  
e) the scop e, content, and method of performance of tests or calculations and analyses for a 
product type approval application;  
f) the content of documentation for tests or calculations and analyses for a product type 
approval application;  
g) requirements for an authorised  corporate subject performing tests and independent 
verification of tests or calculations and analyses for a product type approval application;  
h) the scope and nature of documentation for a product type approval application;  
i) the method of stipulating and max imum permissible values of the transport index, the 
criticality safety index, non -fixed contamination and radiation level, and the manner in 
which the category of packaging with its radioactive content is specified (hereinafter a 
“package ”); 
j) technical and organisational conditions of carriage and transport of a radioactive or fissile 
material;  
                                                 
1)  Council Directive 2006/117/Euratom of 20  November  2006 on the supervision and control of shipments of 
radioactive waste and spent fuel.  
Commission Decision 2008/312/Euratom of 5 March 2008 , establishing the standard document for the 
supervision and control of shipments of radioactive waste and spent fuel referred to in Council Directive 
2006/117/Euratom.  
  - 2 - 
k) requirements regarding the content, language and availability of documentation required 
for the carriage and transport of a radioactive or fissile material;  
l) the manne r and scope of notification of administrative authorities and subjects that the 
carriage concerns, regarding carriage and when it shall take place;  
m) the manner of labelling, appearance and manner of use of safety signs for labelling a 
package, vehicle used for its carriage, and a freight container;  
n) samples of standard documents used for cross -border carriage of radioactive waste or 
spent nuclear fuel.  
 
§ 2 
Definitions  
For the purposes of this decree, the following definitions shall apply:  
a) the value A 1 is the value of activity of a special form radioactive material used to 
stipulate activity limits for purposes of carriage;  
b) the value A 2 is the value of activity of an other than special form radioactive material 
used to stipulate activity li mits for purposes of carriage;  
c) a confinement system is the organisation of fissile material in packaging or the 
organisation of part of packaging in a manner necessary to control criticality;  
d) a containment system is the organisation of part of packaging in  a manner necessary to 
prevent the escape of the radioactive or fissile material during transport;  
e) a freight container is a device for the carriage of packaged or unpackaged products via 
one or more modes of transport without the handling of individual ite ms of its contents, 
which has a permanent closure, is sufficiently rigid and durable for repeated use, and has 
equipment that permits its handling, especially transfer among means of transport from 
one mode of transport to another; freight containers are b roken down into  
1. small containers, with all external dimensions less than 1.5  m or with internal volume 
less than 3  m3; 
2. intermediate bulk containers, which are portable packages with an internal volume 
no greater than 3  m3; 
3. large containers, which are any c ontainer not meeting the definitions in Points  1 and 
2; 
f) an overpack is a protective case used by one carrier as one handling unit to facilitate the 
transport of one or more packages;  
g) a consignment is all packages or packagings or a load of radioactive or f issile substances 
handed over by the carrier for transport;  
h) exclusive use is the use of a conveyance or large container by one carrier, whose 
instructions govern all loading and unloading activity during the entire course of carriage;  
i) a low specific activi ty material is a radioactive material whose own specific activity is 
naturally limited, or a radioactive material whose mean specific activity has been 
intentionally limited;  
j) a low toxicity radionuclide source emitting alpha radiation (hereinafter a “low t oxicity 
alpha emitter ”) is natural uranium, depleted uranium, natural thorium, 235U, 238U, 232Th, 
228Th, and 230Th contained in ores or in physical or chemical concentrates, or other 
radionuclide sources emitting alpha radiation with transformation half -lives of less than 
10 days;  
k) maximum normal operating pressure is the maximum overpressure that can occur in a 
retention system over the course of one year at a temperature and sunlight corresponding  - 3 - 
to ambient conditions during transport, assuming no ventila tion, external cooling via an 
auxiliary system, or operating checks during transport occur;  
l) a surface contaminated object is a solid object that is not itself radioactive but which has 
radioactive or fissile material distributed on its surface;  
m) unirradiate d thorium is thorium containing not more than 10-7 g 233U per gram of 232Th; 
n) unirradiated uranium is uranium containing not more than 2.103 Bq of plutonium per 
gram of 235U, at most 9.106 Bq of fission products per gram of 235U, and at most 5.10-3 g 
236U per gram of 235U; 
o) uranium  
1. is natural uranium, included chemically separated uranium, containing uranium 
isotopes in the following distribution: approximately 99.28  % by mass of 238U, 
approximately 0.72  % by mass of 235U, and an insignificant mass percentage  of 234U; 
2. depleted uranium with a smaller mass percentage of 235U than natural uranium; 
depleted uranium also contains an insignificant mass percentage of 234U; 
3. enriched uranium with a higher mass percentage of 235U than 0.72  %; enriched 
uranium also conta ins an insignificant mass percentage of 234U; 
p) routine conditions of carriage is carriage without a radiation emergency;  
q) normal conditions of carriage is carriage with a radiation emergency simulated by tests 
pursuant to Points  19 to 25 of Part  II of Annex  1 to this decree;  
r) accident conditions of carriage is carriage with a radiation emergency simulated by tests 
pursuant to Points  26 to 37 of Part  II of Annex  1 to this decree.  
§ 3 
Radioactive or fissile material whose transport is subject  to authorisation  
(1) Authorisation is needed to transport a consignment  
a) of fissile material if the sum of the criticality safety indices of packages in one 
conveyance or shipping container is greater than 50;  
b) nuclear fuel.  
(2) Authorisation is also needed to tran sport a consignment  
a) containing special form radioactive material with activity greater than 3.103 A1 or 
radioactive material other than special form with activity greater than 3.103 A2 or 
radioactive material with activity grater than 1  000 TBq, depending on which of these 
values is lower;  
b) radioactive or fissile material in packaging of Type B(M) that is not designed for a 
temperature range of minus 40  ºC to plus 70  ºC or is not designed to permit occasional 
controlled ventilation;  
c) radioactive or fissile ma terial via a vessel intended for this purpose with a specified 
radiation protection programme;  
d) radioactive or fissile material containing radionuclides whose values of A 1 and A2 not 
listed in Table  2 of Annex  3 to this decree were stipulated by calculation  pursuant to 
Points  3 to 7 of Annex  3 to this decree;  
e) radioactive or fissile material contained in an instrument or product and containing 
radionuclides whose values for a package exception listed in column 5 of Table  2 of 
Annex  3 to this decree were repla ced by values calculated according to principles and 
methods stipulated in Annex  7 to this decree;  
f) fissile substances pursuant to Point  17(f) of Annex  3 to this decree.   - 4 - 
The values of A 1, A 2, and the values for exception of an package are given for individu al 
radionuclides in Table  2 of Annex  3 to this decree, or are stipulated by proceedings pursuant 
to Points  3 to 7 of Annex  3 to this decree.  
(3) International carriage of a consignment pursuant to (2)(d) to (f) also requires 
authorisation of relevant authoriti es of states that the carriage concerns.  
(4) Classification of radioactive or fissile substances and packages and requirements 
imposed on them are provided in Points  1 and 8 to 34 of Annex  3 to this decree, and in 
Annex  1 to this decree.  
§ 4 
Packaging for the carriage, storage, or deposit of radioactive or fissile material  
(1) Individual types of packagings for the carriage of a radioactive or fissile material and 
corresponding types of packages are as follows:  
1. packaging for a package exception  and a package exception;  
2. Type IP -1 packaging  and a Type IP -1 industrial package;  
3. Type IP -2 packaging  and a Type IP -2 industrial package;  
4. Type IP -3 packaging  and a Type IP -3 industrial package;  
5. Type A packaging  and a Type A package;  
6. Type B(U) packaging  and a Type B(U) industrial package;  
7. Type B(M) packaging  and a Type B(M) industrial package;  
8. Type C packaging  and a Type C industrial package.  
(2) Requirements for specification of individual types of packaging for the transport of 
radioactive or fissile material, depending on the radioactive content of the package, are 
stipulated in Annex 3 to this decree.  
(3) Packaging for the transport of radioactive material that is not fissile material must, 
depending on its type, meet applicable requirements of Part  I of Annex  1 to this decree, as 
follows:  
a) every packaging must meet the requirements of Points  7 to 18 and of Points  19 to 21, if it 
is intended for air carriage;  
b) packaging for package exceptions must meet the requirements of Point  22; 
c) Type IP -1, IP -2, and IP -3 packaging  must meet the requirements of Points  23 to 30;  
d) packaging for the transport of 0.1  kg or more of uranium hexafluoride must meet the 
requirements of Points  31 to 33, or of Point  34;l 
e) Type A packaging must meet the requirements of Points  35 to 51;  
f) Type B(U) packaging must meet the requirements of Points  52 to 66;  
g) Type B(M) packaging must meet the requirements of Points  67 and 68;  
h) Type C packaging must meet the requirements of Points  69 to 72.  
(4) Packaging for the transport of fissile material must, depending on its type, meet the 
requirements of (3)(a) to (h) and the requirements of Points  73 to 86 of Part  I of Annex  1 to 
this decree. The requirements of Points  73 to 86 of Part  I of Annex  1 to this decree do not 
apply to packages in a consignment containing only fissile material that meets the 
requirements of one of (a) through (f)  of Point  17 of Annex  3 to this decree (hereinafter 
“exceptions of fissile material ”). 
(5) Type S packaging for the storage of radioactive or fissile material and Type D 
packaging for the de posit of radioactive or fissile material must, depending on its type, meet 
the requirements of Annex  2 to this decree.   - 5 - 
§ 5 
Detailed requirements for the content of documentation for authorisation of carriage of 
radioactive or fissile ma terial  
 (1) Documentation for authorisation of carriage of radioactive or fissile material 
contained in an instrument or product, and containing radionuclides for which values for 
excepting a package have been replaced by values calculated according to pri nciples and 
methods stipulated in Annex  7 to this decree, must contain source data for the calculation of 
individual dosages for a transport worker and a representative individual, and collective 
dosages under routine conditions of carriage, normal conditi ons of carriage, and under 
accident conditions of carriage.  
(2) The source data includes  
a) the expected use of the device or product and the radionuclides it contains;  
b) the maximum activity of the radionuclides in the device or product;  
c) the maximum radiation level on the surface and at a distance of 1  m from the device or 
product;  
d) the chemical and physical form of the radionuclides in the device or product;  
e) the design of the device or product, especially the containment system and radiation 
shielding for the r adionuclides it contains;  
f) the management system used, including quality control, and that the device or product is 
manufactured according to design type specifications;  
g) verification procedures to ensure that radionuclide activity and absorbed dose equivale nt 
limits declared for the device or product are not exceeded;  
h) the maximum number of devices or products that are to be shipped in one consignment, 
annually.  
§ 6 
Transport index, criticality safety index, package category, non -fixed contamination, 
and radi ation level  
(1) The method for determining  
a) the transport index for a package, an overpack, a freight container, unpackaged material 
with low mass activity in group LSA -I, or an unpackaged surface contaminated item in 
group SCO -I is stipulated in Points  23 and 24 of Annex  4 to this decree;  
b) the criticality safety index for  
1. a consignment, a freight container, and an overpack is stipulated in Point  25 of 
Annex  4 to this decree;  
2. a package is stipulated in Points  84 to 86 of Part  I of Annex  1 to this decree;  
c) a packag e category is stipulated in Points  29 of Annex  4 to this decree.  
(2) The maximum permissible values for the transport index, criticality safety index, and 
radiation level on the surface and at a given distance from it for a package, an overpack, and a 
conveyan ce are stipulated in Points  26 to 28, 66 to 69, and 73 of Annex  4 to this decree.  
(3) The maximum permissible non -fixed contamination values for a package, an 
overpack, and a conveyance are stipulated in Points  8, 9, 13, and 14 of Annex  4 to this decree.  
§ 7  - 6 - 
Technical and organisational conditions of carriage and transport of radioactive or 
fissile material  
(1) Technical and organisational conditions that must be fulfilled  
a) prior to the initial and prior to every further carriage of radioactive or fissile material a re 
stipulated in Points  1 to 3 of Annex  4 to this decree;  
b) to secure the carriage of individual package types are stipulated in Points  4 to 22 of 
Annex  4 to this decree;  
c) for the safe separation of packages, overpacks, or containers containing radioactive or  
fissile material and some radioactive material from transport workers, the population, 
unexposed photographic film, and other dangerous items during carriage and stowage are 
stipulated in Points  62 and 63 of Annex  4 to this decree;  
d) for the safe placement of a consignment of packages on or in the means of transport and 
during stowage are listed in Points  64 to 67 of Annex  4 to this decree;  
e) for the safe mutual separation of groups of packages containing fissile material during 
carriage and during stowage are  listed in Points  68 to 70 of Annex  4 to this decree.  
(2) Further requirements to ensure safe carriage are stipulated in Annex  4 to this decree, 
and if they apply  
a) to carriage documents and marking in general, in Points  45 to 61;  
b) to carriage via rail and road, in Points  71 to 74;  
c) to carriage via vessels, in Points  75 and 76;  
d) to carriage via air, in Points  77 to 79;  
e) to carriage via post, in Point  80; 
f) to other essentials of carriage, in Points  81 to 88.  
§ 8 
Requirements for documentation necessary for carriage and  transport of radioactive 
or fissile material  
(1) Requirements  
a) for the essentials of a description of a consignment in a carriage document are stipulated 
in Point  46 of Annex  4 to this decree;  
b) for carriage documentation are stipulated in Points  47 to 53 of Ann ex 4 to this decree;  
c) for documentation and operating rules that the carrier must ensure are available to the 
consignor are stipulated in Points  54 to 56 of Annex  4 to this decree.  
(2) During the cross -border carriage of radioactive waste or spent nuclear fuel pursuant to 
§ 9(4)(d) of the Act, documentation accompanying carriage also includes relevant completed 
forms A -1 or B -1, A -4a or B -4a, and A -5 or B -5, provided in Czech in Annex  5 and in 
English in Annex  6 to this decree.  
CELEX: 32006L0117  
 
 
§ 9 
Notificati on of administrative authorities and subjects of transport concerns  
The manner, scope, and deadlines for notifying   - 7 - 
a) the Office and relevant state authorities that international transport concerns are stipulated 
in Points  57 to 60 of Annex  4 to this decree;  
b) the consignor by the carrier regarding necessary measures for carriage are stipulated in 
Points  54 to 56 of Annex  4 to this decree.  
§ 10 
The marking and labelling of a package, freight container, and conveyance for 
carriage  
(1) The marking of a package and ove rpack with UN numbers and naming pursuant to 
Table  1 of Annex  3 to this decree is stipulated in Points  30 to 37 of Annex  4 to this decree.  
(2) The use labelling to mark a package, overpack, and freight container is stipulated in 
Points  38 and 39 of Annex  4 to this decree. The completion of labels is stipulated in Points  40 
to 42 of Annex  4 to this decree.  
(3) The use of placards and tables to mark a freight container and conveyance is 
stipulated in Points  43 and 44 of Annex  4 to this decree.  
(4) The appearance and dime nsions of the trefoil radioactivity symbol, labels, placards, 
and tables are stipulated in Figures  1 to 7 of Annex  4 to this decree.  
§ 11 
Products subject to Type Approval  
(1) Type Approval applies to packaging intended for carriage, storage, or deposit of 
radioactive or fissile material, including radioactive waste, as follows:  
a) Type IP -2 and IP -3 packaging for the carriage of fissile material, except for exceptions of 
fissile material;  
b) packaging for the carriage of 0.1  kg or more of uranium hexafluoride; in th e event of 
international carriage of radioactive shipments pursuant to Point  34 of Part  I of Annex  1 
to this decree, type approval by relevant state authorities that the carriage concerns is also 
necessary;  
c) Type A packaging for the carriage of fissile mate rial, except for exceptions of fissile 
material;  
d) Type B(U), B(M), and C packaging for the carriage of radioactive or fissile material; in 
the event of international carriage of Type B(M) radioactive shipments pursuant to 
Point  67 of Part  I of Annex  1 to th is decree, type approval by the relevant State 
authorities that the carriage concerns is also necessary;  
e) packaging for the carriage of a radioactive or fissile material requiring multilateral 
approval pursuant to international treaties by which the Czech R epublic is bound;  
f) Type D packaging intended for the deposit of spent or irradiated nuclear fuel or 
radioactive waste produced by its reprocessing;  
g) Type S packages intended for the storage of radioactive or fissile material, including 
radioactive waste, spe cifically for special form radioactive material whose activity 
exceeds A 1, or for radioactive material other than special form whose activity exceeds A 2. 
(2) All special form radioactive material with properties stipulated in Points  2 to 4 of 
Part I of Annex  1 to the draft decree and low dispersible radioactive material with properties 
stipulated in Point  5 of Part  I of Annex  1 to the draft decree are subject to type approval.  
§ 12  - 8 - 
Documentation for a Type Approval application, tests or calculations and analyse s 
and their documentation, requirements for an authorised corporate entity  
(1) The scope, contents, and performance method of tests or calculations and analyses for 
a type approval application for special form radioactive material, low dispersible radioactive 
material, and packaging for the carriage, storage, or deposit of radioactive or fissile material 
are stipulated in Part  II of Annex  1 to this decree.  
(2) A corporate entity that performs tests for type approval of a special form radioactive 
material, a low dis persible radioactive material, and packaging for the transport, storage, or 
deposit of radioactive or fissile material must  
a) have a facility equipped for the performance of tests pursuant to Part  II of Annex  1 to this 
decree appropriate for the given produc t type;  
b) have drawn up procedures for the performance of tests pursuant to Part  II of Annex  1 to 
this decree appropriate for the given product type;  
c) have workers trained for the performance of tests pursuant to Part  II of Annex  1 to this 
decree appropriate for the given product type;  
d) have a quality management system in place;  
e) not be in a dependent relationship with the subject requesting the test.  
(3) A corporate entity performing calculations and analyses or independent verification 
of these calculations and an alyses instead of tests applicable to a given type of special form 
radioactive material, low dispersible radioactive material, and packaging for the carriage, 
storage, or deposit of radioactive or fissile material, must in accordance with Points  1 and 2 of  
Part II of Annex  1 to this decree:  
a) use a calculation program for such calculations and analyses or independent verification 
of these calculations and analyses that ensures sufficient precision and accuracy of 
results;  
b) must have workers trained to perform the appropriate calculations and analyses or 
independent verification of these calculations and analyses;  
c) have a quality management system in place;  
d) not be in a dependent relationship with the applicant when performing independent 
verification of calculati ons and analyses.  
(4) Documentation for an application for type approval of a special form radioactive 
material, low dispersible radioactive material, and packaging for the carriage, storage, or 
deposit of radioactive or fissile material is product test docume ntation or documentation of 
calculations, safety assays and analyses, and their independent verification (hereinafter “test 
documentation ”). Documentation for a product type approval application comprises,  
a) for packagings, test documentation pursuant to Poi nts 13 to 37 of Part  II of Annex  1 to 
this decree applicable to the given type of packaging with evaluation of results in 
accordance with Points  1 and 2 of Part  II of Annex  1 to this decree; evaluation of results 
proves compliance with requirements stipula ted for the given type of packaging in §  4(3) 
to (5);  
b) for special form radioactive material, test documentation pursuant to Points  4 to 11 of 
Part II of Annex  1 to this decree with evaluation of results in accordance with Points  1 
and 2 of Part  II of Annex  1 to this decree; evaluation of results proves compliance with 
requirements in Points  2 to 4 of Part  I of Annex  1 to this decree;  
c) for low dispersible radioactive material, test documentation pursuant to Points  3 and 12 
of Part  II of Annex  1 to this decree  with evaluation of results in accordance with Points  1  - 9 - 
and 2 of Part  II of Annex  1 to this decree; evaluation proves compliance with 
requirements of Point  5 of Part  I of Annex  1 to this decree.  
§ 13 
Samples of standard documents used for cross -border carr iage of radioactive waste or 
spent nuclear fuel  
Samples of standard documents used in the area of cross -border carriage of radioactive 
waste or spent nuclear fuel are provided in Czech in Annex  5 to this decree and in English in 
Annex  6 to this decree.  
CELEX: 32008D0312  
§ 14 
This decree was notified in accordance with Directive (EU) 2015/1535 of the European 
Parliament and of the Council of 9  September  2015 laying down a procedure for the provision 
of information in the field of technical regulations and of  rules on Information Society 
services.  
§ 15 
Effective date  
This decree shall come into effect on ...  
 
Chair:  
Engineer Dana Drábová Ph. D.  
  - 10 - 
 
Annex  1 to Decree  No ... 
 
REQUIREMENTS AND TES T PROCEDURES FOR TYP E APPROVAL  
 
PART  I 
 
REQUIREMENTS FOR RADIOACTIVE  OR FISSILE MATERIALS, PACKAGINGS, 
AND PACKAGES  
 
REQUIREMENTS FOR RADIOACTIVE OR FISSILE MATERIALS  
 
Requirements for a radioactive material with low specific activity material in group 
LSA -III 
1. (601.)) A radioactive material with low specific activity i n group LSA -III must be a solid 
material of such a nature that after the entire contents of the package are subjected 
to the test specified in Point  3 of Part  II, the activity of water does not exceed 0.1 
A2. 
 
Requirements for special form radioactive mate rial 
2. (602.)  Special form radioactive material must have at least one dimension greater than 
5 mm. 
 
3. (603.)  Special form radioactive material shall be of such a nature or shall be so designed 
that 
a) it does not break or shatter under impact or pressure t ests pursuant to Points  5 
and 6 or pursuant to Point  9(a), and during bending tests pursuant to Point  7 of 
Part II; 
b) it does not melt or disperse during heat tests pursuant to Point  8 or 9(b) of 
Part II; 
c) the activity of water during the leaching test pursua nt to Points  10 and 11 of 
Part II does not exceed 2  kBq, or for sealed sources, the leakage rate during 
volumetric leakage assessment test does not exceed the permitted limit 
pursuant to ISO 9978:1992 (E).  
 
4. (604.)  When a sealed capsule constitutes part of the special form radioactive material, 
the capsule shall be so manufactured that it can be opened only by destroying it.  
 
Requirements for low dispersible radioactive material  
5. (605.)  Low dispersible radioactive material shall be such that the total a mount of this 
radioactive material in a package shall meet the following requirements:  
a) the radiation level at 3  m from unshielded radioactive material does not exceed 
10 mSv/h;  
b) if subjected to tests specified in Points  36 and  37 of Part  II, the airborne re lease 
in gaseous and particulate forms of up to 100  m aerodynamic equivalent 
                                                 
) Note: Position numbers given in brackets beside the numbers of points, tables, and figures correspond to 
numbering in recommendations of the International Atomic Energy Agency - IAEA Safety Standards, series 
SSR-6, IAEA Regulations for the Safe Transport of Radioactive Material from 2012, International Atomic 
Energy Agency, Vienna, 2012.   - 11 - 
diameter would not exceed 100 A 2; a separate specimen may be used for each 
test; and  
c) if subjected to the test specified in Point 3 of Part II, the activity of water would 
not exc eed 100 A 2; in the application of this test, the damaging effects of the 
tests specified in (b) shall be taken into account.  
 
Requirements for exceptions of fissile material  
6. (606.)  An exceptions of fissile material pursuant to Point  17(f) of Annex  3 to this decree 
shall be subcritical without the need for accumulation control under conditions  
a) of Point  73(a);  
b) consistent with requirements for assessing a set of packages under normal 
conditions of carriage pursuant to Point  84(b) and under accident conditio ns of 
carriage pursuant to Point  85(b);  
c) of Point  83(a) for packages transported by air.  
 
 
GENERAL REQUIREMENTS  FOR PACKAGINGS AND P ACKAGES  
 
7. (607.)  A package shall be designed so that  
a) it can be easily and safely transported with regards to its mass, volu me, and 
shape, and   
b) it can be secured in or on the conveyance during transport.  
 
8. (608.)  A package shall be designed so that  
a) any lifting attachments on the package are functional, and if they fail, the 
fulfilment of other requirements of this decree is not threatened, and  
b) safety factors for snatch lifting of the package are met.  
 
9. (609.)  Attachments and any other features on the outer surface of a package that could be 
used to lift it shall be designed either to support its mass in accordance with the  
requirements of Point  8. If the requirement in the first sentence is not met, they 
shall be removable or otherwise rendered incapable of being used during 
transport.  
 
10. (610.)  As far as practicable, packaging shall be so designed and finished that the e xternal 
surfaces are free from protruding features and can be easily decontaminated.  
 
11. (611.)  As far as practicable, the outer layer of a package shall be so designed as to 
prevent the collection and retention of water.  
 
12. (612.)  Equipment carried tog ether with a package shall not reduce its safety.  
 
13. (613.)  A package shall be capable of withstanding the effects of any acceleration, 
vibration or vibration resonance that may arise under routine conditions of 
transport and repeated use so that  
a) there i s no deterioration in the effectiveness of the closing devices on the 
various receptacles of the package;  
b) its integrity is not compromised; and  
c) nuts, bolts and other securing devices do not become loose or fall off.  
  - 12 - 
14. (614.)  The material of the packagin g and any components or structures shall be 
physically and chemically compatible with each other and with the radioactive 
contents; changes in their characteristics due to irradiation must also be taken into 
account.  
 
15. (615.)  All valves through which th e radioactive contents could escape shall be protected 
against unauthori sed operation.  
 
16. (616.) The design of the package shall take into account ambient temperatures and 
pressures that are likely to be encountered in routine conditions of transport.  
 
17. (617.)  A package shall be so designed that it provides sufficient shielding to ensure that, 
under routine conditions of transport and with the maximum design activity of its 
radioactive contents, the radiation level at any point on the external surface of the 
package does not exceed the values specified in Points  16, 27, and 28 of Annex  4 
to this decree, taking into account Points  66(b) and 73 of Annex  4 to this decree.  
 
18. (618.)  The design of a package must also take into account other properties of 
radioactive or fissile material pursuant to Point  7 of Annex  4 to this decree.  
 
 
ADDITIONAL REQUIREME NTS FOR PACKAGES TRA NSPORTED BY AIR  
 
19. (619.)  For a package to be transported by air, the temperature of the accessible surfaces 
shall not exceed 50  °C at  an ambient temperature of 38  °C with no account taken 
for insolation.  
 
20. (620.)  A package to be transported by air shall be so designed that if it is exposed to 
ambient temperatures ranging from minus 40  °C to plus 55  °C, the integrity of the 
containmen t system would not be breached.  
 
21. (621.)  A package to be transported by air shall be capable of withstanding an internal 
pressure that produces a pressure differential of not less than maximum normal 
operating pressure plus 95  kPa, without loss or dispe rsal of radioactive contents.  
 
 
REQUIREMENTS FOR PAC KAGE EXCEPTIONS  
 
22. (622.)  A package exception shall be designed to meet the requirements of Points  7 to 18 
and of Points  19 to 21, if carried by air.  
 
 
REQUIREMENTS FOR IND USTRIAL PACKAGES  
 
Requirements  for Type IP -1 
23. (623.)  A package exception shall be designed to meet the requirements of Points  7 to 18 
and 36, and of Points  19 to 21, if carried by air.  
  - 13 - 
Requirements for Type IP -2 
24. (624.)  A Type IP -2 package shall be designed to meet the requireme nts for Type IP -1 as 
specified in Point  23, and so that performance of tests in Points  22 and 23 of 
Part II does not cause:  
a) loss or dispersal of the radioactive contents; and  
b) more than a 20  % increase in the maximum radiation level on an arbitrary 
location  on the external surface of the package.  
 
Requirements for Type IP -3 
25. (625.)  A Type IP -3 package shall be designed to meet the requirements for Type IP -1 as 
specified in Point  23, and requirements in Points  37 to 49.  
 
Alternative requirements for Type I P-2 and Type IP -3 
26. (626.)  A package may be used as Type IP -2 if: 
a) it meets requirements for Type IP -2 specified in Point  23; 
b) it is designed to meet requirements for UN Packing Group I or II according to 
the United Nations Recommendations on the Transport  of Dangerous Goods, 
Model Regulations; and   
c) performance of tests stipulated for UN Packing Group I or II does not result in  
1. loss or dispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary locatio n on the external surface of the package.  
 
27. (627.)  A portable tanks may be used as Type IP -2 or Type IP -3, provided that:  
a) it meets requirements for Type IP -2 specified in Point  23; 
b) it is designed so that  
1. it meets the requirements of the United Nations R ecommendations on 
the Transport of Dangerous Goods, Model Regulations, or other 
requirements guaranteeing the same or higher level of protection; and  
2. is capable of withstanding a test pressure of 265  kPa; and  
c) is designed so that any additional shielding th at is provided  
1. withstands the static and dynamic stresses resulting from handling and 
routine conditions of transport; and  
2. prevents more than a 20  % increase in the maximum radiation level on 
an arbitrary location on the external surface of the package.  
 
28. (628.)  Tanks, other than portable tanks, may be used as Type IP -2 or Type IP -3 for 
transporting LSA -I and LSA -II liquids and gases as prescribed in Table  1 of 
Annex  4 to this decree, provided that:  
a) it meets requirements for Type IP -1 specified in Point  23; 
b) it is designed so that  
1. it complies with relevant requirements of the European Agreement 
concerning the International Carriage of Dangerous Goods by Road 
(ADR)2)or other requirements guaranteeing the same or greater level of 
protection; and  
2. is capable o f withstanding a test pressure of 265  kPa; and  
c) is designed so that any additional shielding that is provided  
                                                 
2)  The European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR), 
decreed under No  64/1987, as amended.   - 14 - 
1. withstands the static and dynamic stresses resulting from handling 
under routine conditions of transport; and   
2. prevents more than a 20  % increase i n the maximum radiation level on 
an arbitrary location on the external surface of the package.  
 
29. (629.)  A freight container with the characteristics of a permanent enclosure may be used 
as Type IP -2 or Type IP -3, provided that:  
a) its radioactive contents are restricted to solid material;  
b) it meets requirements for Type IP -1 specified in Point  23; and  
c) it is designed to meet requirements pursuant to ISO 1496:1990(E), except for 
dimensions and ratings. If subjected to the tests prescribed in the first sentence  
and to acceleration occurring during routine conditions of transport it would 
prevent:  
1. loss or dispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary location on the external surface of the pack age. 
 
30. (630.)  A metal intermediate bulk container may also be used as Type IP -2 or Type IP -3, 
provided that:  
a) it meets requirements for Type IP -1 specified in Point  23; 
b) it is designed to meet requirements for UN Packing Group I or II pursuant to 
the Unit ed Nations Recommendations on the Transport of Dangerous Goods - 
Model Regulations . If subjected to the tests prescribed in the first sentence, but 
with the drop test performed with the most damaging orientation of the test 
container, it would prevent:  
1. loss or dispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary location on the external surface of the package.  
 
 
REQUIREMENTS FOR PAC KAGES CONTAINING URA NIUM HEXAFLUORIDE  
 
31. (631.)  A package inte nded for the transport of uranium hexafluoride shall meet the 
requirements that pertain to the radioactive and fissile properties of the transported 
material. Except as allowed in Point  34, uranium hexafluoride in quantities of 
0.1 kg or more shall be pack aged and transported in accordance with ISO 
7195:2005(E)  and the requirements of Points  32 and 33.  
 
32. (632.)  A package intended for contents of 0.1  kg or more of uranium hexafluoride shall 
be designed so that it shall:  
a) withstand a pressure test specified  in Point  18 of Part  II without leakage and 
without unacceptable stress, as specified in  
ISO 7195:2005(E), except for cases specified in Point  34; 
b) withstand the free drop test specified in Point  22 of Part  II without loss or 
dispersal of the uranium hexafl uoride; and  
c) withstand the thermal test specified in Point  28 of Part  II without rupture of the 
containment system, except as allowed in Point  34. 
 
33. (633.)  A package intended for contents of 0.1  kg or more of uranium hexafluoride shall 
not be equipped wi th pressure relief devices.   - 15 - 
 
34. (634.)  A package intended for contents of 0.1  kg or more of uranium hexafluoride that  
a) is designed to standards other than ISO 7195:2005(E) guaranteeing the same or 
higher degree of nuclear safety and radiation protection;  
b) withstands, without leakage and without unacceptable stress, a pressure test 
specified in Point 18 of Part II only at a pressure less than 2.76  MPa; or  
c) is designed to contain 9  000 kg or more of uranium hexafluoride and does not 
meet the requirements of Poi nt 32(c);  
may be used for carriage only if its type has been approved by the Office, and 
in the case of international carriage, also by relevant authorities of states the 
carriage concerns; other requirements in Points  31 to 33 must be fulfilled.  
 
 
REQUIRE MENTS FOR TYPE A PAC KAGES  
 
35. (635.)  A Type A package shall be designed to meet the requirements of Points  7 to 18, 
36 to 51, and of Points  19 to 21, if carried by air.  
 
36. (636.)  The smallest overall external dimension of the package shall not be less t han 
10 cm. 
 
37. (637.)  The outside of the package shall incorporate a feature such as a seal that is not 
readily breakable and which, while intact, will be evidence that the package has 
not been opened in an unauthorised manner.  
 
38. (638.)  Any tie -down at tachments on the package shall be so designed that, under normal 
and accident conditions of transport, the forces in those attachments shall not 
impair the ability of the package to meet the requirements of this decree.  
 
39. (639.)  The design of the packag e shall take into account temperatures ranging from –
40 °C to +70  °C for the components of the packaging. Special attention shall be 
given to freezing temperatures for liquids and to the potential degradation of 
packaging material within the temperature ra nge from –40 °C to +70  °C. 
 
40. (640.)  The design and manufacturing techniques shall be in accordance with national, 
foreign, or international standards or legislation, if during the use of the packaging 
for transport they ensure the same or greater degree  of nuclear safety, radiation 
protection, physical protection, and handling of a radiation emergency as 
stipulated by the Act and its implementing legislation.  
 
41. (641.)  The design of the package shall include a containment system securely closed by a 
positive fastening device that cannot be opened unintentionally or due to pressure 
that may arise within the package.  
 
42. (642.)  Special form radioactive material may be considered part of the containment 
system.  
 
43. (643.)  If the containment system forms a separate unit of the package, it shall be capable 
of being securely closed by a positive fastening device that is independent of any 
other part of the package.   - 16 - 
 
44. (644.)  Any component of the containment system must be designed to withstand any 
radiolyt ic decomposition of liquids and other volatile materials and the generation 
of gas by chemical reaction and radiolysis.  
 
45. (645.)  The containment system shall retain its radioactive contents during reduction of 
ambient pressure to 60  kPa. 
 
46. (646.)  All valves, other than pressure relief valves, shall be provided with an enclosure to 
retain any leakage.  
 
47. (647.)  A radiation shield that encloses a component of the package that is part of the 
containment system shall be so designed as to prevent the uni ntentional release of 
that component from the shielded area. Where the radiation shield pursuant to the 
first sentence forms a separate unit, it must be capable of being securely closed by 
a positive fastening device that is independent of any other part o f the packaging.  
 
48. (648.)  A package shall be so designed that if it were subjected to the tests specified in 
Points  19 to 24 of Part  II, it would prevent:  
a) loss or dispersal of the radioactive contents; and  
b) more than a 20  % increase in the maximum radiat ion level on an arbitrary 
location on the external surface of the package.  
 
49. (649.)  The design of a package intended for liquid radioactive or fissile material shall 
expand with space to accommodate thermal changes in the volume of the liquid 
radioactiv e contents, dynamic effects, and filling dynamics.  
 
50. (650.)  A Type A package designed to contain liquid radioactive or fissile material shall:  
a) meet the conditions specified in Point  48(a) if subjected to tests specified in 
Point  25 of Part  II; and  
b) eithe r contain sufficient absorbent material that  
1. will absorb at least twice its volume of liquid contents; and   
2. is suitably positioned so as to contact the liquid in the event of leakage; 
or 
c) be provided with a containment system composed of primary inner and 
secondary outer containment components designed to enclose the liquid 
contents completely and to ensure their retention within the secondary outer 
containment components, even if the primary inner components leak.  
 
51. (651.)  A package designed for gases sh all prevent loss or dispersal of the radioactive 
contents during tests specified in Point  25 of Part  II, except for a Type A package 
designed for tritium gas or for noble gases.  
 
 
REQUIREMENTS FOR TYP E B(U) PACKAGES  
 
52. (652.)  A Type B(U) package shall be  designed to meet the requirements of Points  7 to 
18, 36 to 47, 48(b), 49, 53 to 66, and of Points  19 to 21, if carried by air.  
 
53. (653.)  1. A package shall be so designed that heat generated within the package by its  - 17 - 
contents shall not negatively affect  compliance with containment system and 
shielding requirements, as follows:  
a) under ambient conditions specified in Points  56 and 57;  
b) under normal conditions of transport specified in Points  19 to 24 of Part  II; and  
c) if left unattended for seven days.  
 
2. Particular attention shall be paid to the effects of heat that may  
a) alter the arrangement, the geometrical form, or the physical state of the 
radioactive contents;  
b) cause deformation or melting of the radioactive content, receptacle, or 
packaging enclosing the radioactive content;  
c) reduce the efficiency of the packaging through differential thermal expansion, 
cracking, or melting of the shielding material;  
d) accelerate corrosion when combined with moisture.  
 
54. (654.)  Except for a package transported under exclusi ve use, a package shall be so 
designed that the temperature of an arbitrary part of an easily accessible surface 
shall not exceed 50  °C 
a) under ambient conditions specified in Point  56; and   
b) if it is not exposed to sunlight.  
 
55. (655.)  1. Except for a packa ge transported by air pursuant to Point  19, the maximum 
temperature of an arbitrary part of an easily accessible surface of a package shall 
not exceed 85  °C 
a) under conditions of exclusive use under ambient conditions pursuant to 
Point  56; 
b) if it is not expos ed to sunlight; and  
c) if left unattended for seven days.  
 
2. Barriers or screens intended for protection of transport workers may be taken 
into account without the need for these to be tested as packages.  
 
56. (656.)  Ambient temperature is defined as 38  °C. 
 
57. (657.)  Sunlight exposure conditions and their values are specified in Table  1. 
 
58. (658.)  A package that includes thermal protection for the purpose of satisfying the 
requirements of the thermal test specified in Point  28 of Part  II shall be so 
desig ned that such protection will remain effective if the package is subjected to 
the tests specified in Points  19 to 24, and also either in Points  27(a) and 27(b), or 
in Points  27(b) and 27(c) of Part  II, according to rules specified in Point  59(b) 
depending on the mass, average specific mass, and activity of the package. 
Thermal protection on the exterior of the package shall not be rendered ineffective 
by ripping, cutting, skidding, abrading or rough handling.  
 
Table  1(12.) Insolation data  
Case  Form and loca tion of surface  Insolation for 12  h per day 
(W/m2) 
1 Flat surfaces transported horizontally — downward facing  0 
2 Flat surfaces transported horizontally — upward facing  800  - 18 - 
3 Surfaces transported vertically  200a) 
4 Other downward facing (not horizontal ) surfaces  200a) 
5 All other surfaces  400a) 
Legend:  
a) Alternatively, a sine function may be used, with an absorption coefficient adopted and the effects of possible 
reflection from neighbouring objects neglected.  
 
59. (659.)  1. A package shall be design ed so that  
a) it restricts the loss of radioactive contents to not more than 10-6 A2 per hour 
after performance of tests specified in Part  19 to 24 of Part  II;  
b) it retains sufficient shielding to ensure that the radiation level 1 m from the 
surface of the pac kage does not exceed 10 mSv/hwith the maximum 
radioactive contents that the package is designed to contain, according to  
1. Point  27(c) of Part  II, if the package has a mass not greater than 500  kg, 
a mean density not greater than 1  000 kg/m3 based on its ext ernal 
dimensions, and radioactive contents greater than 1  000 A2 not as 
special form radioactive material; or  
2. Point  27(a) of Part  II for other packages; and   
c) the accumulated loss of radioactive contents in a period of seven days does not 
exceed 10 A 2 for k rypton -85 and A 2 for all other radionuclides after the 
performance of tests specified in (a) or (b).  
 
2. Where mixtures of different radionuclides are present, the provisions of 
Points  5 to 7 of Annex  3 to this decree shall apply to the calculation of A 2, except 
that for krypton -85 an effective A 2(i) value equal to 10 A 2 may be used. When 
determining loss of radioactive contents pursuant to (1)(a), the assessment shall 
take into account the external contamination limits specified in Point  8 of Annex  4 
to this decree.  
 
60. (660.)  A package for the transport of radioactive contents with activity greater than 105 
A2 shall be so designed that if it were subjected to the enhanced water immersion 
test specified in Point  30 of Part  II, there would be no rupture of the containment 
system.  
 
61. (661.)  Compliance with the permitted activity release limits shall depend neither upon 
filters nor upon a mechanical cooling system.  
 
62. (662.)  A package shall not include a pressure relief system from the containment system 
that would allow the release of radioactive material to the environment under the 
conditions of the tests specified in Points  19 to 24 and 26 to 29 of Part  II. 
 
63. (663.)  A package shall be so designed that if it were at the maximum normal operating 
pressu re and it were subjected to the tests specified in 19 to 24 and 26 to 29 of 
Part II, the levels of strains in the containment system would not attain values that 
would adversely affect the fulfilment of other requirements of this decree.  
 
64. (664.)  A pack age shall not have a maximum normal operating pressure in excess of 
700 kPa. 
 
65. (665.)  A package containing low dispersible radioactive material shall be so designed 
that any features added to the low dispersible radioactive material that are not part  - 19 - 
of it, or any internal components of the packaging, shall not adversely affect the 
characteristics of the low dispersible radioactive material.  
 
66. (666.)  A package shall be designed for an ambient temperature range of –40 °C to 
+38 °C. 
 
 
REQUIREMENTS FOR T YPE B(M) PACKAGES  
 
67. (667.)  1. Type B(M) packages shall meet the requirements for Type B(U) packages 
specified in Point  52. 
 
2. The requirements of (1) need not be met during carriage within the Czech 
Republic or during solely between the Czech Republic and some states, if the 
Office or the relevant authorities of these states approve the packaging type 
pursuant requirements other than those specified in Points  37, 55 to 57, and 60 to 
66. Notwithstanding, the requirements for Type B(U) packages specified in 
Points  55 and 60 to 66 shall be met as far as practicable.  
 
68. (668.)  Intermittent venting of Type B(M) packages is possible, provided the the Office 
so stipulates in a type approval decision or in the case of international carriage, the 
Office and rel evant authorities of states that the carriage concerns.  
 
 
REQUIREMENTS FOR TYP E C PACKAGES  
 
69. (669.)  A Type C package shall be designed to meet the requirements of Points  7 to 21, 
36 to 47, 48(b), 49, 53 to 57, 61 to 66, and 70 to 72.  
 
70. (670.)  A packa ge shall be capable of meeting the assessment criteria prescribed for tests 
in Points  59(b) and 63 after being placed in an environment defined by a thermal 
conductivity of 0.33  W/(m·K) and a temperature of 38  °C in the steady state. 
Initial conditions for  assessment of the package are that any thermal insulation of 
the package remains intact, the package is at the maximum normal operating 
pressure, and the ambient temperature is 38  °C. 
 
71. (671.)  1. A package shall be designed so that  
a) at maximum normal op erating pressure and after the performance of tests 
specified in Points  19 to 24, it would restrict the loss of radioactive contents to 
not more than 10-6 A2 per hour; and   
b) after performance of the series of tests specified in Point  34 of Part  II 
1. it retain s sufficient shielding to ensure that the radiation level 1  m from 
the surface of the package does not exceed 10  mSv/h with the 
maximum radioactive contents that the package is designed to contain; 
and 
2. the accumulated loss of radioactive contents in a peri od of seven days 
does not exceed 10 A 2 for krypton -85 and A 2 for other radionuclides.  
 
2. Where mixtures of different radionuclides are present, the provisions of 
Points  5 to 7 of Annex  3 to this decree shall apply to the calculation of A 2, except  - 20 - 
that for  krypton -85 an effective A 2(i) value equal to 10 A 2 may be used. When 
determining loss of radioactive contents pursuant to (1), external non -fixed 
contamination limits specified in Point  8 of Annex  4 to this decree shall be taken 
into account.  
 
72. (672.)  A package shall be so designed that if it were subjected to the enhanced water 
immersion test specified in Point  30 of Part  II, there would be no rupture of the 
containment system.  
 
 
REQUIREMENTS FOR PAC KAGES CONTAINING FIS SILE MATERIAL  
 
73. (673.)  Fissile  material shall be transported so as to:  
a) Maintain subcriticality during routine, normal and accident conditions of 
transport; in particular, the following contingencies shall be considered:  
1. leakage of water into or out of the package;  
2. loss of efficiency of  built-in neutron absorbers or moderators;  
3. rearrangement of the contents either within the package or as a result of 
loss from the package;  
4. reduction of spaces within or between packages;  
5. packages becoming immersed in water or buried in snow;  
6. temperature c hanges; and  
b) meet the requirements:  
1. of Point  36 except for unpackaged material when specifically allowed 
by Point  17(e) of Annex  3 to this decree;  
2. of radioactive properties of fissile material stipulated by this decree;  
3. of Point  37 unless the material is ex cepted by Point  17 of Annex  3 to 
this decree;  
4. of Points  76 to 86 unless the material is excepted by Point  17 of 
Annex  3 to this decree, and Point  74 or 75.  
 
74. (674.)  A package containing fissile material that meets the requirements of (d) and one 
of the provisions of (a) to (c) is excepted from the requirements of Points  76 to 86 
of Part  I. 
a) A package containing fissile material in any form provided that:  
1. the smallest external dimension of the package is not less than 10  cm; and  
2. the criticality safety inde x of the package does not exceed 10, where it is 
calculated using the following formula:  
CSI = 50 × 5 × {[mass of uranium -235 in package (g)]/Z
fissile radionuclides* in the package (g)]/280}, where the values of Z are 
taken from Table  2. 
b) A package containing fissile material in any form provided that:  
1. the smallest external dimension of the package is not less than 30  cm; 
2. the pac kage, after being subjected to the tests specified in Points  19 to 
24 of Part  II, retains its fissile material contents, preserves the minimum 
overall outside dimensions of at least 30  cm, and prevents the entry of a 
10 cm cube; and  
                                                 
*  Plutonium can have any isotopic composition provided that the amount of radioactive Plutonium -241 is less than 
the amount of Plutonium -240.  - 21 - 
3. the criticality safety index of the package does not exceed 10, where it 
is calculated using the following formula:  
CSI = 50 × 2 × {[mass of uranium -235 in package (g)]/Z
other fissile radionuclides in the package (g)]/280}, where the values of 
Z are taken from Table 2.  
c) A package containing fissile material in any form provided that:  
1. the smallest external dimension of the package is not less than 10  cm; 
2. the pack age, after being subjected to the tests specified in Points  19 to 
24 of Part  II, retains its fissile material contents, preserves the minimum 
overall outside dimensions of at least 10  cm, and prevents the entry of a 
10 cm cube;  
3. the criticality safety index  is calculated using the following formula:  
CSI = 50 × 5 × {[mass of uranium -235 in package (g)]/Z
other fissile radionuclides* in the package (g)]/280}, where the values 
of Z are taken from Table  2; and  
4. the maximum mass of fissile radionuclides in any package does not 
exceed 15  g. 
d) The total mass of beryllium, hydrogenous material enriched i n deuterium, 
graphite and other allotropic forms of carbon in an individual package shall not 
be greater than the mass of fissile radionuclides in the package except where 
their total concentration does not exceed 1  g in any 1  000 g of material. 
Beryllium incorporated in copper alloys up to 4  % by weight of the alloy does 
not need to be considered.  
 
Table  2(13.) Values of Z for calculation of the criticality safety index pursuant to Point  74 
 
Enrichmenta) Z 
Uranium enriched up to 
1.5 % 2200  
Uranium enrich ed up to 
5 % 850 
Uranium enriched up to 
10 % 660 
Uranium enriched up to 
20 % 580 
Uranium enriched up to 
100 % 45 
 
Legend:  
a) If a package contains uranium with varying enrichments of uranium -235, then the value corresponding to the 
highest enrichment s hall be used for Z.  
 
75. (675.)  A package containing not more than 1  000 g of plutonium are excepted from the 
requirements of Points  76 to 86 provided that:  
a) not more than 20  % of the plutonium by mass is fissile radionuclides;  
b) the criticality safety index is calculated using the following formula: CSI = 50 
× 2 × [mass of plutonium (g)/1000]; and  
c) the amount of uranium contained along with plutonium in the package does not 
exceed 1  % of the mass of the plutonium.  
  - 22 - 
Contents specification for assessments of pac kage designs containing fissile material  
76. (676.)  Where the chemical or physical form, isotopic composition, mass or 
concentration, moderation ratio or density, or geometric configuration is not 
known, the assessments of Points  80 to 85 shall be performe d assuming that each 
unknown parameter has a value that gives the maximum neutron multiplication 
consistent with known conditions and parameters in these assessments.  
 
77. (677.)  The assessment of irradiated nuclear fuel according to Points  80 to 85 shall be 
based on:  
a) either an isotopic composition demonstrated to provide maximum neutron 
multiplication during irradiation history;  
b) or a conservative estimate of the neutron multiplication for assessment of the 
package. After irradiation but prior to shipment, a measurement shall be 
performed to confirm the conservatism of the isotopic composition.  
 
Geometry and temperature requirements  
78. (678.)  A package, after being subjected to the tests specified in Points  19 to 24:  
a) shall preserve minimum overall outside d imensions of at least 10  cm; 
b) shall prevent the entry of a 10  cm cube.  
 
79. (679.)  A package shall be designed for an ambient temperature range of –40 °C to 
+38 °C unless the Office specifies otherwise in a type approval decision.  
 
Assessment of an individu al package in isolation  
80. (680.)  For a package in isolation, it shall be assumed that water can leak into or out of all 
void spaces of the package, including those within the containment system. If the 
design incorporates special features to prevent leak age of water into or out of void 
spaces, even as a result of operator error, it may be assumed that water leaks 
neither into or out of these spaces. Special features are  
a) either multiple high standard water barriers, not less than two of which would 
remain watertight if the package were subject to the tests prescribed in 
Point  85(b), a high degree of quality control in the manufacture, maintenance 
and repair of packaging, and tests to demonstrate the closure of each package 
before each shipment; or  
b) for packa ges containing uranium hexafluoride with a maximum uranium 
enrichment of 5  % by mass uranium -235: 
1. no physical contact between the valve and any other component of the 
packaging other than at its original point of attachment for the test 
specified in Point  85(b), and perfectly leak -proof valves after the 
performance of tests specified in Point  28 of Part  II; and   
2. a high degree of quality control in the manufacture, maintenance and 
repair of packaging, and tests to demonstrate closure of each package 
before e ach shipment.  
 
81. (681.)  When assessing an isolated package, it shall be assumed that the confinement 
system causes reflection of neutrons as would be caused by a layer of water at 
least 20  cm thick or additional reflection of neutrons as may be provided by the 
surrounding material of the packaging. When it can be demonstrated that the 
confinement system remains within the packaging following the tests prescribed 
in Point  85(b), the reflection of neutrons by a layer of water at least 20  cm thick  - 23 - 
may be ass umed in Point  82(c).  
 
82. (682.)  A package shall remain subcritical under the assumptions of Points  80 and 81 and 
under conditions that result in the maximum neutron multiplication consistent 
with:  
a) routine conditions of transport;  
b) the tests specified in Po int 84(b);  
c) the tests specified in Point  85(b).  
 
83. (683.)  For a package transported by air:  
a) the package shall be subcritical under conditions consistent with the Type C 
package tests specified in Point  34 of Part  II, assuming reflection by at least 
20 cm of water but no leakage of water into the package; and  
b) in the assessment pursuant to Point  82, special features pursuant to Point  80 are 
not allowed, unless following Type C package tests specified in Point  34 of 
Part II and water ingress tests for a packa ge pursuant to Point  33 of Part  II, 
leakage of water into and out of void spaces is prevented.  
 
Assessment of package arrays under normal transport conditions  
84. (684.)  A number N shall be derived, such that a set of five times N packages shall be 
subcrit ical for the arrangement and package conditions that provide the maximum 
neutron multiplication, where:  
a) there shall not be any substance between the packages, and the package 
arrangement is exposed on all sides to neutron reflection as would be caused by 
a layer of water at least 20  cm thick; and   
b) the state of each package corresponds to a condition after the performance of 
tests specified in Points  19 to 24 of Part  II. 
 
Assessment of package arrays under accident conditions of transport  
85. (685.)  A number  N shall be derived, such that a set of two times N packages shall be 
subcritical for the arrangement and package conditions that provide the maximum 
neutron multiplication, where:  
a) there is a hydrogen moderator between the packages, and the package 
arrange ment is exposed on all sides to neutron reflection as would be caused by 
a layer of water at least 20  cm thick;  
b) the state of each package corresponds to a condition after the performance of 
tests specified in Points  19 to 24 of Part  II and after the perfor mance of the 
more limiting of the following tests:  
1. for packages having a mass not greater than 500  kg and an overall 
density not greater than 1  000 kg/m3 based on external dimensions, 
according to Point  27(b), Point  27(c), Point  28, and either according to  
Point  29 or according to Points  31 to 33 of Part  II; 
2. for other packages according to Point  27(a), Point  27(b), Point  28, and 
either according to Point  29 or according to Points  31 to 33 of Part  II; 
c) when part of the fissile material escapes from the contai nment system 
following the tests specified in Point  85(b), it shall be assumed that fissile 
material escaped from each package in the array. All of the fissile material 
shall be arranged and moderated to achieve maximum neutron multiplication 
and neutron r eflection as would be caused by a layer of water at least 20  cm 
thick.   - 24 - 
 
Stipulation of the criticality safety index  
86. (686.)  The criticality safety index for packages containing fissile material is calculated 
according to the formula: CSI = 50/N, where N  is the smaller of two values of N 
according to Points  84 and 85.  
The value of the CSI may be zero, provided that an unlimited number of packages 
are subcritical (i.e. N is effectively equal to infinity in both cases).  
 
 
PART  II 
 
TEST PROCEDURES  
 
DEMONSTRA TION OF COMPLIANCE  
 
1. (701.)  Demonstration of compliance with the performance standards required in Part  I 
shall be accomplished by one or more of the methods listed in (a) to (d). The 
methods are as follows:  
a) a test with specimens representing LSA -III mat erial, special form radioactive 
material, or low dispersible radioactive material, or with prototypes or samples 
of the packaging. The contents of the specimen or the packaging for the tests 
shall simulate as closely as practicable the expected range of ra dioactive 
contents. The specimens or packaging to be tested shall be prepared as 
presented for transport;  
b) presentation of documentation from prior successful demonstration of 
conformance pursuant to (a), (c), and (d) of sufficiently similar nature;  
c) tests w ith models of appropriate scale with features that are significant with 
respect to the tested properties, if engineering experience has shown the results 
of such tests to be suitable for design purposes; when a scale model is used, the 
need to adjust certa in test parameters shall be taken into account;  
d) calculation, or reasoned argument, when the calculation procedures and 
parameters are generally considered to be reliable or conservative.  
 
2. (702.)  Appropriate assessment methods shall be used to assess tes ts performed on the 
specimen, prototype, or sample. Test assessment must prove compliance with 
requirements stipulated in Part I and compliance of test procedures with 
requirements in Part  II. 
 
LEACHING TESTS FOR A  GROUP LSA -III MATERIAL WITH LO W SPECIFIC 
ACTIVITY AND FOR A L OW DISPERSIBLE RADIO ACTIVE MATERIAL  
 
3. (703.)  A solid material sample representing the entire contents of the package shall be 
immersed for seven days in water at room temperature. The volume of water to be 
used in the test shall be su fficient to ensure that at the end of the seven -day test 
period, the free volume of the unabsorbed and unreacted water remaining shall be 
at least 10  % of the volume of the solid test sample. The water shall have an initial 
pH of 6 to 8 and a maximum condu ctivity of 1  mS/m at 20  °C. The total activity 
of the free volume of water shall be measured following the seven -day immersion 
of the test sample.  
  - 25 - 
TESTS FOR SPECIAL FO RM RADIOACTIVE MATER IAL 
 
General requirements  
4. (704.)  Specimens that contain or simula te special form radioactive material shall be 
subjected to an impact test, the percussion test, the bending test and the heat test 
specified in Points  5 to 9. A different specimen may be used for each of the tests. 
Following each test, a leaching assessmen t or volumetric leakage test shall be 
performed on the specimen by a method no less sensitive than the methods given 
in Point  10 for non -dispersible solid material or in Point  11 for encapsulated 
material.  
 
Test methods  
5. (705.)  Impact test: The specimen shall drop onto the target from a height of 9  m. The 
target shall be as defined in Point  17. 
 
6. (706.)  Percussion test: The specimen shall be placed on a sheet of lead that is supported 
by a smooth solid surface and struck by the flat face of a mild steel  bar so as to 
cause an impact equivalent to that resulting from a free drop of 1.4  kg through 
1 m. The lower part of the bar shall be 25  mm in diameter with the edges rounded 
off to a radius of 3.0 ± 0.3  mm. The lead sheet, of hardness number 3.5 –4.5 on th e 
Vickers scale and not more than 25  mm thick, shall cover an area greater than that 
covered by the specimen. A fresh surface of lead shall be used for each impact. 
The bar shall strike the specimen so as to cause maximum damage.  
 
7. (707.)  Bending test: T he test shall apply only to long, slender sources with both a 
minimum length of 10  cm and a length to minimum width ratio of not less than 
10. The specimen shall be rigidly clamped in a horizontal position so that one half 
of its length protrudes from the face of the clamp. The orientation of the specimen 
shall be such that the specimen will suffer maximum damage when its free end is 
struck by the flat face of a steel bar. The steel bar shall strike the specimen so as to 
cause an impact equivalent to that r esulting from a free vertical drop of 1.4  kg 
through 1  m. The lower part of the bar shall be 25  mm in diameter with the edges 
rounded off to a radius of 3.0 ± 0.3  mm. 
 
8. (708.)  Heat test: The specimen shall be heated in air to a temperature of 800  °C and held 
at that temperature for a period of 10  min. and shall then be allowed to cool.  
 
9. (709.)  Specimens that comprise or simulate radioactive material enclosed in a sealed 
capsule may be excepted from:  
a) the tests prescribed in Points  5 and 6, provided that  the specimens are 
alternatively subjected to the impact test for the appropriate class pursuant to 
ISO 2919:2012(E) : 
1. the Class 4 impact test if the mass of the special form radioactive 
material is less than or equal to 200  g; 
2. the Class 5 impact test if th e mass of the special form radioactive 
material is greater than 200  g but less than 500  g; 
b) the tests prescribed in Point  8, provided that the specimens are alternatively 
subjected to the Class 6 heat test pursuant to ISO 2919:2012(E) . 
 
Leaching and volumet ric leakage test methods   - 26 - 
 
10. (710.)  For specimens that comprise or simulate non -dispersible solid material, a leaching 
assessment shall be performed as follows:  
a) The specimen shall be immersed for seven days in water at room temperature. 
The volume of wate r to be used in the test shall be sufficient to ensure that at 
the end of the seven -day test period, the free volume of the unabsorbed and 
unreacted water remaining shall be at least 10  % of the volume of the solid test 
sample itself. The water shall have an initial pH of 6 to 8 and a maximum 
conductivity of 1  mS/m at 20  °C; 
b) the water with the specimen shall then be heated to a temperature of 50 ± 5  °C 
and maintained at this temperature for 4  h; 
c) the activity of the water shall then be determined;  
d) The specim en shall then be kept for at least seven days in still air at not less 
than 30  °C and with a relative humidity of not less than 90  %; 
e) the specimen shall then be immersed in water of the same specification as that 
in (a) and the water with the specimen heat ed to 50 ± 5  °C and maintained at 
this temperature for 4  h; 
f) the activity of the water shall then be determined.  
 
11. (711.)  For specimens that comprise or simulate radioactive material enclosed in a sealed 
capsule, either a leaching assessment or a volumet ric leakage assessment shall be 
performed as follows:  
a) a leaching test:  
1. the specimen shall be immersed in water at room temperature. The 
water shall have an initial pH of 6 to 8 and a maximum conductivity of 
1 mS/m at 20  °C; 
2. the water with the specimen shal l then be heated to a temperature of 50 
± 5 °C and maintained at this temperature for 4  h; 
3. the activity of the water shall then be determined;  
4. The specimen shall then be kept for at least seven days in still air at not 
less than 30 °C and with a relative h umidity of not less than 90  %; 
5. the process according to Points  1, 2, and 3 shall be repeated once;  
b) the alternative volumetric leakage assessment shall include any of the tests 
prescribed in ISO 9978:1992(E).  
 
 
TESTS FOR LOW DISPER SIBLE RADIOACTIVE MA TERIAL  
 
12. (712.)  A specimen that comprises or simulates low dispersible radioactive material shall 
be subjected to the enhanced thermal test specified in Point  36 and the impact test 
specified in Point  37. A different specimen may be used for each of the tests . 
Following the test in the first sentence, the specimen shall be subjected to the 
leach test specified in Point 3. After each test it shall be determined if the 
applicable requirements of Point  5 of Part  I have been met.  
 
TESTS FOR PACKAGES  
 
Test specimen  preparation  
13. (713.)  All specimens shall be inspected before testing in order to identify and record 
faults or damage, including the following:   - 27 - 
a) divergence from design;  
b) manufacturing defects;  
c) corrosion or other damage;  
d) deformation.  
 
14. (714.)  The contai nment system of the package shall be clearly specified.  
 
15. (715.)  The external features of the specimen shall be clearly identified so that reference 
may be made simply and clearly to any part of such a specimen.  
 
Testing the integrity of the containment  system and shielding and assessing criticality 
safety  
16. (716.)  After performance of tests specified in Points  18 to 37:  
a) faults and damage shall be identified and recorded;  
b) it shall be determined whether the integrity of the containment system and 
shield ing has been retained to the extent required in Part  I for the package 
under test; and  
c) for a package containing fissile material, it shall be determined whether the 
assumptions and conditions used in the assessments required by Points  73 to 86 
of Part  I also apply to the tested package.  
 
Target for drop tests  
17. (717.)  The target for the drop test specified in Points  5, 22, 25(a), 27, and 35 shall be a 
flat, horizontal surface of such a character that any increase in its resistance to 
displacement or defor mation upon impact by the specimen would not significantly 
increase damage to the specimen.  
 
Test for packages designed to contain uranium hexafluoride  
18. (718.)  Specimens that comprise or simulate packagings designed to contain 0.1  kg or 
more of uranium hexafluoride shall be tested hydraulically at an internal pressure 
of at least 1.38  MPa. For stipulated periodic review of packaging, an equivalent 
non-destructive test may be applied that is stipulated in documentation used as the 
basis for a packaging ty pe approval decision issued by the Office, and in the case 
of international carriage, also by relevant authorities of states that the carriage 
concerns.  
 
Tests demonstrating the ability to withstand normal conditions of transport  
19. (719.)  Tests demonstra ting the ability to withstand normal conditions of transport are the 
water spray test, the free drop test, the stacking test and the penetration test. A 
specimen of the package shall be subjected to the free drop test, the stacking test 
and the penetration  test, preceded in each case by the water spray test. One 
specimen may be used for all the tests pursuant to the first sentence, provided that 
the requirements of Point  20 are fulfilled.  
 
20. (720.)  The time interval between the conclusion of the water spr ay test and the 
subsequent test shall be such that the water has soaked in to the maximum extent, 
without appreciable drying of the exterior of the specimen. In the absence of any 
evidence to the contrary, this interval shall be taken to be 2  h if the wate r spray is 
applied from four directions simultaneously. However, if the water spray is 
applied from each of the four directions consecutively, the subsequent test shall be  - 28 - 
performed immediately after the end of the water spray test.  
 
21. (721.)  Water spray  test: The specimen shall be subjected to a water spray test that 
simulates exposure to rainfall of approximately 5  cm per hour for at least 1  h. 
 
22. (722.)  Free drop test: The specimen shall drop onto the target so as to suffer maximum 
damage in respect of the safety features to be tested:  
a) The height of drop measured from the lowest point of the specimen to the 
upper surface of the target shall be not less than the distance specified in 
Table  3 for the applicable package mass. The target shall meet the 
requirements of Point  17; 
b) for rectangular fibreboard or wood packages not exceeding a mass of 50  kg, a 
separate specimen shall be subjected to a free drop onto each corner from a 
height of 0.3  m; 
c) for cylindrical fibreboard not exceeding a mass of 100  kg, a s eparate specimen 
shall be subjected to a free drop onto each of the quarters of each rim from a 
height of 0.3  m. 
 
23. (723.)  Stacking test: Unless the shape of the packaging effectively prevents stacking, the 
specimen shall be subjected, for a period of 24  h, to a compressive load equal to 
the greater of the following:  
a) five times the maximum weight of the package; or  
b) the product of the vertically projected area of the package and a pressure of 
13 kPa. 
 
Table  3(14.) Free drop distance for tests proving the a bility of a package to withstand normal 
conditions of transport  
Mass of packaging with rated content (kg)  Free drop distance (m)  
less than 5  000 1.2 
greater than or equal to 5  000 and less than 10  000 0.9 
greater than or equal to 10  000 and less than 15  000 0.6 
greater than or equal to 15  000 0.3 
 
 
24. (724.)  Penetration test: The specimen shall be placed on a rigid, flat, horizontal surface 
that will not move significantly while the test is being carried out:  
a) a bar 3.2  cm in diameter with a hemispheri cal end and a mass of 6  kg shall be 
dropped and directed to fall, with its longitudinal axis vertical, onto the centre 
of the weakest part of the specimen, so that, if it penetrates sufficiently far, it 
will hit the containment system. The bar shall not be  significantly deformed by 
the test performance;  
b) the height of drop of the bar measured from its lower end to the intended point 
of impact on the upper surface of the specimen shall be 1  m. 
 
Additional tests for Type A packages designed for liquids and gas es 
25. (725.)  A specimen, or separate specimens, shall be subjected to tests specified in (a) and 
(b). If it can be demonstrated that one test is more severe for the specimen, the 
specimen shall be subjected to the more severe test:  
a) Free drop test: the spe cimen shall drop onto the target so as to cause the most 
damage to the containment system. The height of the drop measured from the  - 29 - 
lowest part of the specimen to the upper surface of the target shall be 9  m. The 
target shall be as defined in Part  17; 
b) Pene tration test: the specimen shall be subjected to the test specified in 
Point  24 with a drop height of 1.7  m. 
 
Tests demonstrating the ability to withstand accident conditions during transport  
26. (726.)  The specimen shall be subjected to the cumulative eff ects of the tests specified in 
Points  27 and 28, in that order. Following these tests, either this specimen or 
another separate specimen shall be subjected to the water immersion test as 
specified in Point  29, and in the case of a Type B(U) or Type B(M) pa ckage 
containing more than 105 A2 and a Type C package, also the test as specified in 
Point  30. 
 
27. (727.)  Mechanical test: the mechanical test consists of three different drop tests:  
a) drop test I: the specimen shall drop onto the target so as to suffer ma ximum 
damage, and the height of the drop measured from the lowest point of the 
specimen to the upper surface of the target shall be 9  m. The target shall be as 
defined Point  17. 
b) drop test II: the specimen shall drop onto a bar rigidly mounted perpendicular ly 
on the target so as to suffer maximum damage. The height of the drop 
measured from the intended point of impact of the specimen to the upper 
surface of the bar shall be 1  m. The bar shall be of solid mild steel of circular 
section, 15.0 ± 0.5  cm in diam eter and 20  cm long, unless a longer bar would 
cause greater damage. Otherwise a bar of sufficient length to cause maximum 
damage shall be used. The upper end of the bar shall be flat and horizontal with 
its edge rounded off to a radius of not more than 6  mm. The target shall meet 
the requirements of Point  17; 
c) drop test III: the specimen shall be subjected to a dynamic crush test by 
positioning the specimen on the target so as to suffer maximum damage by the 
drop of a 500  kg mass from 9  m onto the specimen.  The mass shall consist of a 
1 m × 1  m solid mild steel plate and shall fall in a horizontal attitude. The 
lower face of the steel plate shall have its edges and corners rounded off to a 
radius of not more than 6  mm. The height of the drop shall be measure d from 
the underside of the plate to the highest point of the specimen. The target shall 
meet the requirements of Point  17. 
 
Each specimen shall be subjected to the applicable drops, as specified in Point  59 
or 85 of Part  I. The order of the drop tests sha ll be such that, on completion of the 
mechanical test, the specimen shall have suffer maximum damage in the thermal 
test that follows.  
 
28. (728.)  Thermal test: the specimen shall be in thermal equilibrium under conditions of an 
ambient temperature of 38  °C, subject to insolation conditions specified in Table  1 
and subject to the design maximum rate of internal heat generation within the 
package from the radioactive contents. Any of these parameters are allowed to 
have different values prior to, and during,  the test, provided due account is taken 
of them in the subsequent assessment of package response. The specimen must be 
exposed to the following in the specified order:  
a) for a period of 30 min . to a thermal environment that provides a heat flux at 
least equ ivalent to that of a hydrocarbon fuel –air fire in sufficiently quiescent  - 30 - 
ambient conditions to give a minimum average flame emissivity coefficient of 
0.9 and an average temperature of at least 800  °C, fully engulfing the 
specimen, with a surface absorptivi ty coefficient of 0.8 or that value that the 
package may be demonstrated to possess if exposed to the fire specified;  
b) an ambient temperature of 38  °C, subject to insolation conditions specified in 
Table  1 and subject to the design maximum rate of internal heat generation 
within the package by the radioactive contents for a sufficient period to ensure 
that temperatures in the specimen are everywhere decreasing and/or are 
approaching initial steady state conditions. Any of these parameters are 
allowed to have  different values prior to, and during, the test, provided due 
account is taken of them in the subsequent assessment of package response. 
During and following the test, the specimen shall not be artificially cooled and 
any combustion of materials of the sp ecimen shall be permitted to proceed 
naturally.  
 
29. (729.)  Water immersion test: the specimen shall be immersed under at least 15  m of 
water for a period of not less than 8  h in the attitude that will lead to maximum 
damage. For demonstration purposes, an  external gauge pressure of at least 
150 kPa shall be considered to meet these conditions.  
 
Enhanced water immersion test for Type B(U) and Type B(M) packages containing 
more than 105 A2 and for Type C packages  
30. (730.)  Water immersion test: the specimen  shall be immersed under at least 200  m of 
water for a period of not less than 1  h. For demonstration purposes, an external 
gauge pressure of at least 2  MPa shall be considered to meet these conditions.  
 
Water immersion test for radioactive packages contai ning fissile material  
31. (731.)  A package for which it has been assumed for purposes of assessment under 
Points  80 to 85 of Part  I that water leaks in and out to the extent that results in 
greatest reactivity shall be excepted from the test specified in P oint 33. 
 
32. (732.)  Before the specimen is subjected to the water leakage test specified in Point  33, it 
shall be subjected to the tests in Point  27(b) and Point  27(a), or 727(c) and 28.  
 
33. (733.)  The specimen shall be immersed under at least 0.9  m of w ater for a period of not 
less than 8  h in the attitude for which maximum leakage is expected.  
 
Tests for type C packages  
34. (734.)  Specimens shall be subjected to the following series of tests:  
a) as specified Points  27(a), 27(c), 35, and 36, in that order; and 
b) as specified in (37).  
Separate specimens may be used for the series of tests in (a) and for the test in (b).  
 
35. (735.)  Puncture –tearing test: the specimen shall be subjected to the damaging effects of a 
vertical solid probe made of mild steel. The or ientation of the package specimen 
and the impact point on the package surface shall be such as to cause maximum 
damage at the conclusion of the test sequence specified in Point  34(a).  
a) A specimen representing a package having a mass of less than 250  kg, sha ll be 
placed on a target and subjected to a probe having a mass of 250  kg falling 
from a height of 3  m above the intended impact point. For this test the probe  - 31 - 
shall be a 20  cm diameter cylindrical bar with the striking end forming the 
frustum of a right c ircular cone with the following dimensions: 30  cm height 
and 2.5  cm diameter at the top with its edge rounded off to a radius of not more 
than 6 mm. The target on which the specimen is placed shall be as specified in 
Point  17. 
b) For a package having a mass o f 250  kg or more, the base of the probe shall be 
placed on a target and the specimen dropped onto the probe. The height of the 
drop, measured from the point of impact with the specimen to the upper surface 
of the probe, shall be 3  m. The probe for this tes t shall have the same properties 
and dimensions as specified in (a), except that the length and mass of the probe 
shall be such as to cause maximum damage to the specimen. The target on 
which the specimen is placed shall be as specified in Point  17. 
 
36. (736.)  Enhanced thermal test: the conditions for this test shall be as specified in Point  28, 
except that the exposure to the thermal environment shall be for a period of 60 
min. 
 
37. (737.)  Impact test: The specimen shall be subject to an impact on a targe t at a velocity of 
not less than 90  m/s, at such an orientation as to suffer maximum damage. The 
target shall be as defined in Point  17, except that the target surface may be at any 
orientation as long as the surface is normal to the specimen path.   - 32 - 
 
Annex  2 to Decree  No …………  
 
REQUIREMENTS FOR TYP E D AND S PACKAGES  
 
1. Type D and S packaging:  
a) shall have mechanical ruggedness demonstrably enough with regard to 
designed manner of manipulation; and  
b) shall be manufactured from materials whose service life demons trably 
corresponds to the designed service life of the packaging. Materials with a 
shorter service life may be used for packaging components if are readily 
replaceable during storage or repository operation.  
 
2. The contents of Type D or Type S packaging s hall be sufficiently dried out and 
surrounded by a defined medium. The Office shall decide on the dryness criteria 
and parameters of this medium in the type approval decision when requested by 
the applicant.  
 
3. A Type D or S packaging shall be designed to  comply with limits and conditions 
for the handling of radioactive waste, including relevant acceptability criteria, 
approved by the Office.  
 
4. Type S packaging shall be manufactured:  
a) to meet the requirements specified in Points  6 to 11 and 13 to 16 of Pa rt I of 
Annex  1 to this decree, and other requirements stipulated by the Office in the 
type approval decision, taking into account manner of use;  
b) to ensure feasibility of checking package leak -tightness during storage;  
c) to preserve adequate shielding during  normal operation, abnormal operation, 
design basis accidents, and beyond design basis accidents that are not serious 
accidents. The shielding of the package shall ensure that the radiation level on 
the exterior does not exceed 10  mSv/h, even at the maximu m design contents 
of radioactive content;  
d) so that the heat generated inside the packaging by its radioactive contents does 
not under the normal conditions and at the ambient temperature of 38  °C have a 
negative effect on compliance with leak -tightness and shielding criteria if the 
packaging and its contents are left unattended for seven days;  
e) to eliminate the influence of generated heat, the heat shall not:  
1. change the spacing, geometrical form or physical state of the 
radioactive contents, or if radionuclid es are sealed within special 
capsule – cause deformation or melting of this capsule or its radioactive 
contents;  
2. reduce the efficiency of the packaging through differential thermal 
expansion, cracking, or melting of the shielding material;  
3. accelerate corro sion when combined with moisture; and  
4. cause the interruption of the residual heat removal; elimination of 
residual heat shall also be ensured also under beyond design basis 
accident conditions that are not serious accidents.   - 33 - 
 
Annex  3 to Decree  No …………  
 
ACTIVITY LIMITS AND CL ASSIFICATION  
 
GENERAL REQUIREMENTS  
 
1. (401.)  A radioactive or fissile material is assigned one of the UN numbers listed in 
Table  1, in accordance with the requirements of Points  8 to 34.  
 
Table  1(1.) Selected UN numbers, names, and des criptions  
UN 
number  NAME a) and description  
Excepted packages  
UN 2908  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGINGS  
UN 2909  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - PRODUCTS OF NATURAL 
URANIUM or DEPLETED URANIUM or THORIUM  
UN 2910  RADIOACT IVE MATERIAL, EXCEPTED PACKAGE - A LIMITED AMOUNT OF 
MATERIAL  
UN 2911  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - DEVICES or PRODUCTS   
UN 3507  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE – URANIUM HEXAFLUORIDE , 
less than 0.1  kg in a package, excepted fissile mat erial or non -fissile material  
Materials with low specific activity  
UN 2912  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -I) 
excepted fissile material or non -fissile material  
UN 3321  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIV ITY (LSA -II) 
excepted fissile material or non -fissile material  
UN 3322  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -III) 
excepted fissile material or non -fissile material  
UN 3324  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY  (LSA -II), 
FISSILE MATERIAL  
UN 3325  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -
III), FISSILE MATERIAL  
Surface contaminated objects  
UN 2913  RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO -I or SCO -
II), excepted fissile substan ce, or non -fissile substance  
UN 3326  RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO -I or SCO -
II), FISSILE SUBSTANCE  
Type A packages  
UN 2915  RADIOACTIVE MATERIAL, TYPE A PACKAGE other than special form radioactive 
material, exceptions of fissile  material, or non -fissile material  
UN 3327  RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE MATERIAL other than 
special form radioactive material  
UN 3332  RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM RADIOACTIVE 
MATERIAL, exceptions of fissile material , or non -fissile material  
UN 3333  RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM RADIOACTIVE 
MATERIAL, FISSILE MATERIAL  
Type B(U) packages  
UN 2916  RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE  
exceptions of fissile material or non -fissile material  
UN 332 8 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE MATERIAL   - 34 - 
Type B(M) packages  
UN 2917  RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE  
exceptions of fissile material or non -fissile material  
UN 3329  RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, FISSILE MATERIAL  
Type  C packages  
UN 3323  RADIOACTIVE MATERIAL, TYPE C PACKAGE  
exceptions of fissile material or non -fissile material  
UN 3330  RADIOACTIVE MATERIAL, TYPE C PACKAGE, FISSILE MATERIAL  
Transport under special arrangement  
UN 2919  RADIOACTIVE MATERIAL, TRANSPORT U NDER SPECIAL ARRANGEMENT  
exceptions of fissile material or non -fissile material  
UN 3331  RADIOACTIVE MATERIAL, TRANSPORT UNDER SPECIAL ARRANGEMENT, 
FISSILE MATERIAL  
Uranium hexafluoride  
UN 2977  RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, FISSILE MATERIAL  
UN 2978  RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE  
exceptions of fissile material or non -fissile material  
Legend:  
a) NAME can be found in the 'NAME and description' field and is limited to the part written in CAPITAL 
LETTERS. In Items  UN 2909, UN 2911, UN 2913, and UN 3326, only the appropriate NAME from alternative 
NAMES  separated by the conjunction 'or'.  
 
BASIC RADIONUCLIDE V ALUES  
 
2. (402.)  Table  2 lists basic radionuclide values:  
a) A1 and A 2 in TBq;  
b) activity concentration limits for exceptions of mater ial in Bq/g; and  
c) activity limits for exceptions of material in Bq.  
 
Table  2(2.) Basic radionuclide values  
Radionuclide (atomic number)  A1 
[TBq]  A2 
[TBq]  Activity 
concentrati
on limits 
for 
exceptions 
of material  
[Bq/g]  Activity 
limits for 
an 
exceptions 
of 
consignme
nt 
[Bq] 
Actinium (89)      
Ac-225a)  8x10-1 6x10-3 1x101 1x104 
Ac-227 (a)  9x10-1 9x10-5 1x10-1 1x103 
Ac-228 6x10-1 5x10-1 1x101 1x106 
Silver (47)      
Ag-105 2x100 2x100 1x102 1x106 
Ag-108m (a)  7x10-1 7x10-1 1x101(b) 1x106(b) 
Ag-110m (a)  4x10-1 4x10-1 1x101 1x106 
Ag-111 2x100 6x10-1 1x103 1x106 
Aluminium (13)      
Al-26 1x10-1 1x10-1 1x101 1x105 
Americium (95)       - 35 - 
Am-241 1x101 1x10-3 1x100 1x104 
Am-242m (a)  1x101 1x10-3 1x100(b) 1x104(b) 
Am-243 (a)  5x100 1x10-3 1x100(b) 1x103(b) 
Argon (18 )     
Ar-37 4x101 4x101 1x106 1x108 
Ar-39 4x101 2x101 1x107 1x104 
Ar-41 3x10-1 3x10-1 1x102 1x109 
Arsenic (33)      
As-72 3x10-1 3x10-1 1x101 1x105 
As-73 4x101 4x101 1x103 1x107 
As-74 1x100 9x10-1 1x101 1x106 
As-76 3x10-1 3x10-1 1x102 1x105 
As-77 2x101 7x10-1 1x103 1x106 
Astatine (85)      
At-211 (a)  2x101 5x10-1 1x103 1x107 
Gold (79)      
Au-193 7x100 2x100 1x102 1x107 
Au-194 1x100 1x100 1x101 1x106 
Au-195 1x101 6x100 1x102 1x107 
Au-198 1x100 6x10-1 1x102 1x106 
Au-199 1x101 6x10-1 1x102 1x106 
Barium (56)      
Ba-131 (a)  2x100 2x100 1x102 1x106 
Ba-133 3x100 3x100 1x102 1x106 
Ba-133m  2x101 6x10-1 1x102 1x106 
Ba-140 (a)  5x10-1 3x10-1 1x101(b) 1x105(b) 
Beryllium (4)      
Be-7 2x101 2x101 1x103 1x107 
Be-10 4x101 6x10-1 1x104 1x106 
Bismuth (8 3)     
Bi-205 7x10-1 7x10-1 1x101 1x106 
Bi-206 3x10-1 3x10-1 1x101 1x105 
Bi-207 7x10-1 7x10-1 1x101 1x106 
Bi-210 1x100 6x10-1 1x103 1x106 
Bi-210m (a)  6x10-1 2x10-2 1x101 1x105 
Bi-212 (a)  7x10-1 6x10-1 1x101(b) 1x105(b) 
Berkelium (97)      
Bk-247 8x100 8x10-4 1x100 1x104 
Bk-249 (a)  4x101 3x10-1 1x103 1x106 
Bromine (35)      
Br-76 4x10-1 4x10-1 1x101 1x105 
Br-77 3x100 3x100 1x102 1x106 
Br-82 4x10-1 4x10-1 1x101 1x106 
Carbon (6)      
C-11 1x100 6x10-1 1x101 1x106 
C-14 4x101 3x100 1x104 1x107 
Calcium (20)       - 36 - 
Ca-41 Unlimited  Unlimited  1x105 1x107 
Ca-45 4x101 1x100 1x104 1x107 
Ca-47 (a)  3x100 3x10-1 1x101 1x106 
Cadmium (48)      
Cd-109 3x101 2x100 1x104 1x106 
Cd-113m  4x101 5x10-1 1x103 1x106 
Cd-115 (a)  3x100 4x10-1 1x102 1x106 
Cd-115m  5x10-1 5x10-1 1x103 1x106 
Cerium (58)      
Ce-139 7x100 2x100 1x102 1x106 
Ce-141 2x101 6x10-1 1x102 1x107 
Ce-143 9x10-1 6x10-1 1x102 1x106 
Ce-144 (a)  2x10-1 2x10-1 1x102(b) 1x105(b) 
Californium (98)      
Cf-248 4x101 6x10-3 1x101 1x104 
Cf-249 3x100 8x10-4 1x100 1x103 
Cf-250 2x101 2x10-3 1x101 1x104 
Cf-251 7x100 7x10-4 1x100 1x103 
Cf-252 1x10-1 3x10-3 1x101 1x104 
Cf-253 (a)  4x101 4x10-2 1x102 1x105 
Cf-254 1x10-3 1x10-3 1x100 1x103 
Chlorine (17)      
Cl-36 1x101 6x10-1 1x104 1x106 
Cl-38 2x10-1 2x10-1 1x101 1x105 
Curium (96)      
Cm-240 4x101 2x10-2 1x102 1x105 
Cm-241 2x100 1x100 1x102 1x106 
Cm-242 4x101 1x10-2 1x102 1x105 
Cm-243 9x100 1x10-3 1x100 1x104 
Cm-244 2x101 2x10-3 1x101 1x104 
Cm-245 9x100 9x10-4 1x100 1x103 
Cm-246 9x100 9x10-4 1x100 1x103 
Cm-247 (a)  3x100 1x10-3 1x100 1x104 
Cm-248 2x10-2 3x10-4 1x100 1x103 
Cobalt (27)      
Co-55 5x10-1 5x10-1 1x101 1x106 
Co-56 3x10-1 3x10-1 1x101 1x105 
Co-57 1x101 1x101 1x102 1x106 
Co-58 1x100 1x100 1x101 1x106 
Co-58m 4x101 4x101 1x104 1x107 
Co-60 4x10-1 4x10-1 1x101 1x105 
Chromium (24)      
Cr-51 3x101 3x101 1x103 1x107 
Caesium (55)      
Cs-129 4x100 4x100 1x102 1x105 
Cs-131 3x101 3x101 1x103 1x106 
Cs-132 1x100 1x100 1x101 1x105  - 37 - 
Cs-134 7x10-1 7x10-1 1x101 1x104 
Cs-134m  4x101 6x10-1 1x103 1x105 
Cs-135 4x101 1x100 1x104 1x107 
Cs-136 5x10-1 5x10-1 1x101 1x105 
Cs-137 (a)  2x100 6x10-1 1x101(b) 1x104(b) 
Copper (29)      
Cu-64 6x100 1x100 1x102 1x106 
Cu-67 1x101 7x10-1 1x102 1x106 
Dysprosium (66)      
Dy-159 2x101 2x101 1x103 1x107 
Dy-165 9x10-1 6x10-1 1x103 1x106 
Dy-166 (a)  9x10-1 3x10-1 1x103 1x106 
Erbium (68)      
Er-169 4x101 1x100 1x104 1x107 
Er-171 8x10-1 5x10-1 1x102 1x106 
Europium (63)      
Eu-147 2x100 2x100 1x102 1x106 
Eu-148 5x10-1 5x10-1 1x101 1x106 
Eu-149 2x101 2x101 1x102 1x107 
Eu-150 (with short half -life) 2x100 7x10-1 1x103 1x106 
Eu-150 (with long half -life) 7x10-1 7x10-1 1x101 1x106 
Eu-152 1x100 1x100 1x101 1x106 
Eu-152m  8x10-1 8x10-1 1x102 1x106 
Eu-154 9x10-1 6x10-1 1x101 1x106 
Eu-155 2x101 3x100 1x102 1x107 
Eu-156 7x10-1 7x10-1 1x101 1x106 
Fluorine (9)      
F-18 1x100 6x10-1 1x101 1x106 
Iron (26)      
Fe-52 (a)  3x10-1 3x10-1 1x101 1x106 
Fe-55 4x101 4x101 1x104 1x106 
Fe-59 9x10-1 9x10-1 1x101 1x106 
Fe-60 (a)  4x101 2x10-1 1x102 1x105 
Gallium (31)      
Ga-67 7x100 3x100 1x102 1x106 
Ga-68 5x10-1 5x10-1 1x101 1x105 
Ga-72 4x10-1 4x10-1 1x101 1x105 
Gadolinium (64)      
Gd-146 (a)  5x10-1 5x10-1 1x101 1x106 
Gd-148 2x101 2x10-3 1x101 1x104 
Gd-153 1x101 9x100 1x102 1x107 
Gd-159 3x100 6x10-1 1x103 1x106 
Germanium ( 32)     
Ge-68 (a)  5x10-1 5x10-1 1x101 1x105 
Ge-71 4x101 4x101 1x104 1x108 
Ge-77 3x10-1 3x10-1 1x101 1x105 
Hafnium (72)       - 38 - 
Hf-172 (a)  6x10-1 6x10-1 1x101 1x106 
Hf-175 3x100 3x100 1x102 1x106 
Hf-181 2x100 5x10-1 1x101 1x106 
Hf-182 Unlimited  Unlimite d 1x102 1x106 
Mercury (80)      
Hg-194 (a)  1x100 1x100 1x101 1x106 
Hg-195m (a)  3x100 7x10-1 1x102 1x106 
Hg-197 2x101 1x101 1x102 1x107 
Hg-197m  1x101 4x10-1 1x102 1x106 
Hg-203 5x100 1x100 1x102 1x105 
Holmium (67)      
Ho-166 4x10-1 4x10-1 1x103 1x105 
Ho-l66m  6x10-1 5x10-1 1x101 1x106 
Iodine (53)      
I-123 6x100 3x100 1x102 1x107 
I-124 1x100 1x100 1x101 1x106 
I-125 2x101 3x100 1x103 1x106 
I-126 2x100 1x100 1x102 1x106 
I-129 Unlimited  Unlimited  1x102 1x105 
I-131  3x100 7x10-1 1x102 1x106 
I-132 4x10-1 4x10-1 1x101 1x105 
I-133 7x10-1 6x10-1 1x101 1x106 
I-134 3x10-1 3x10-1 1x101 1x105 
I-135 (a)  6x10-1 6x10-1 1x101 1x106 
Indium (49)      
In-111 3x100 3x100 1x102 1x106 
In-113m  4x100 2x100 1x102 1x106 
In-114m (a)  1x101 5x10-1 1x102 1x106 
In-115m  7x100 1x100 1x102 1x106 
Iridium (77)      
Ir-189 (a)  1x101 1x101 1x102 1x107 
Ir-190 7x10-1 7x10-1 1x101 1x106 
Ir-192 1x100(c) 6x10-1 1x101 1x104 
Ir-194 3x10-1 3x10-1 1x102 1x105 
Potassium (19)      
K-40 9x10-1 9x10-1 1x102 1x106 
K-42 2x10-1 2x10-1 1x102 1x106 
K-43 7x10-1 6x10-1 1x101 1x106 
Krypton (36)      
Kr-79 4x101 2x100 1x103 1x105 
Kr-81 4x101 4x101 1x104 1x107 
Kr-85 1x101 1x101 1x105 1x104 
Kr-85m 8x100 3x100 1x103 1x1010 
Kr-87 2x10-1 2x10-1 1x102 1x109 
Lanthanum (57)      
La-137 3x101 6x100 1x103 1x107 
La-140 4x10-1 4x10-1 1x101 1x105  - 39 - 
Lutetium (71)      
Lu-172 6x10-1 6x10-1 1x101 1x106 
Lu-173 8x100 8x100 1x102 1x107 
Lu-174 9x100 9x100 1x102 1x107 
Lu-174m  2x101 1x101 1x102 1x107 
Lu-177 3x101 7x10-1 1x103 1x107 
Magnesium (12)      
Mg-28 (a)  3x10-1 3x10-1 1x101 1x105 
Manganese (25)      
Mn-52 3x10-1 3x10-1 1x101 1x105 
Mn-53 Unlimited  Unlimited  1x104 1x109 
Mn-54 1x100 1x100 1x101 1x106 
Mn-56 3x10-1 3x10-1 1x101 1x105 
Molybdenum (42)      
Mo-93 4x101 2x101 1x103 1x108 
Mo-99 (a)  1x100 6x10-1 1x102 1x106 
Nitrogen (7)      
N-13 9x10-1 6x10-1 1x102 1x109 
Sodium (11)      
Na-22 5x10-1 5x10-1 1x101 1x106 
Na-24 2x10-1 2x10-1 1x101 1x105 
Niobium (41)      
Nb-93m 4x101 3x101 1x104 1x107 
Nb-94 7x10-1 7x10-1 1x101 1x106 
Nb-95 1x100 1x100 1x101 1x106 
Nb-97 9x10-1 6x10-1 1x101 1x106 
Neodymium (60)      
Nd-147 6x100 6x10-1 1x102 1x106 
Nd-149 6x10-1 5x10-1 1x102 1x106 
Nickel (28)      
Ni-59 Unlimited  Unlimited  1x104 1x108 
Ni-63 4x101 3x101 1x105 1x108 
Ni-65 4x10-1 4x10-1 1x101 1x106 
Neptunium (93)      
Np-235 4x101 4x101 1x103 1x107 
Np-236 (with short half -life) 2x101 2x100 1x103 1x107 
Np-236 (with long half -life) 9x100 2x10-2 1x102 1x105 
Np-237 2x101 2x10-3 1x100(b) 1x103(b) 
Np-239 7x100 4x10-1 1x102 1x107 
Osmium (76)      
Os-185 1x100 1x100 1x101 1x106 
Os-191 1x101 2x100 1x102 1x107 
Os-191m  4x101 3x101 1x103 1x107 
Os-193 2x100 6x10-1 1x102 1x106 
Os-194 (a)  3x10-1 3x10-1 1x102 1x105 
Phosphorus (15)      
P-32 5x10-1 5x10-1 1x103 1x105  - 40 - 
P-33 4x101 1x100 1x105 1x108 
Protactiniu m (91)      
Pa-230 (a)  2x100 7x10-2 1x101 1x106 
Pa-231 4x100 4x10-4 1x100 1x103 
Pa-233 5x100 7x10-1 1x102 1x107 
Lead (82)      
Pb-201 1x100 1x100 1x101 1x106 
Pb-202 4x101 2x101 1x103 1x106 
Pb-203 4x100 3x100 1x102 1x106 
Pb-205 Unlimited  Unlimited  1x104 1x107 
Pb-210 (a)  1x100 5x10-2 1x101(b) 1x104(b) 
Pb-212 (a)  7x10-1 2x10-1 1x101(b) 1x105(b) 
Palladium (46)      
Pd-103 (a)  4x101 4x101 1x103 1x108 
Pd-107 Unlimited  Unlimited  1x105 1x108 
Pd-109 2x100 5x10-1 1x103 1x106 
Promethium (61)      
Pm-143 3x100 3x100 1x102 1x106 
Pm-144 7x10-1 7x10-1 1x101 1x106 
Pm-145 3x101 1x101 1x103 1x107 
Pm-147 4x101 2x100 1x104 1x107 
Pm-148m (a)  8x10-1 7x10-1 1x101 1x106 
Pm-149 2x100 6x10-1 1x103 1x106 
Pm-151 2x100 6x10-1 1x102 1x106 
Polonium (84)      
Po-210 4x101 2x10-2 1x101 1x104 
Praseodymium (59)      
Pr-142 4x10-1 4x10-1 1x102 1x105 
Pr-143 3x100 6x10-1 1x104 1x106 
Platinum (78)      
Pt-188 (a)  1x100 8x10-1 1x101 1x106 
Pt-191 4x100 3x100 1x102 1x106 
Pt-193 4x101 4x101 1x104 1x107 
Pt-193m  4x101 5x10-1 1x103 1x107 
Pt-195m  1x101 5x10-1 1x102 1x106 
Pt-197 2x101 6x10-1 1x103 1x106 
Pt-197m  1x101 6x10-1 1x102 1x106 
Plutonium (94)      
Pu-236 3x101 3x10-3 1x101 1x104 
Pu-237 2x101 2x101 1x103 1x107 
Pu-238 1x101 1x10-3 1x100 1x104 
Pu-239 1x101 1x10-3 1x100 1x104 
Pu-240 1x101 1x10-3 1x100 1x103 
Pu-241 (a)  4x101 6x10-2 1x102 1x105 
Pu-242 1x101 1x10-3 1x100 1x104 
Pu-244 (a)  4x10-1 1x10-3 1x100 1x104 
Radium (88)       - 41 - 
Ra-223 (a)  4x10-1 7x10-3 1x102(b) 1x105(b) 
Ra-224 (a)  4x10-1 2x10-2 1x101(b) 1x105(b) 
Ra-225 (a)  2x10-1 4x10-3 1x102 1x105 
Ra-226 (a)  2x10-1 3x10-3 1x101(b) 1x104(b) 
Ra-228 (a)  6x10-1 2x10-2 1x101(b) 1x105(b) 
Rubidium (37)      
Rb-81 2x100 8x10-1 1x101 1x106 
Rb-83 (a)  2x100 2x100 1x102 1x106 
Rb-84 1x100 1x100 1x101 1x106 
Rb-86 5x10-1 5x10-1 1x102 1x105 
Rb-87 Unlimited  Unlimited  1x104 1x107 
Rb (natural)  Unlimited  Unlimited  1x104 1x107 
Rhenium (75)      
Re-184 1x100 1x100 1x101 1x106 
Re-184m  3x100 1x100 1x102 1x106 
Re-186 2x100 6x10-1 1x103 1x106 
Re-187 Unlimited  Unlimited  1x106 1x109 
Re-188 4x10-1 4x10-1 1x102 1x105 
Re-189(a)  3x100 6x10-1 1x102 1x106 
Re (natural)  Unlimited  Unlimited  1x106 1x109 
Rhodium (45)      
Rh-99 2x100 2x100 1x101 1x106 
Rh-101 4x100 3x100 1x102 1x107 
Rh-102 5x10-1 5x10-1 1x101 1x106 
Rh-102m  2x100 2x100 1x102 1x106 
Rh-103m  4x101 4x101 1x104 1x108 
Rh-105 1x101 8x10-1 1x102 1x107 
Radon (86)      
Rn-222 (a)  3x10-1 4x10-3 1x101(b) 1x108(b) 
Ruthenium (44)      
Ru-97 5x100 5x100 1x102 1x107 
Ru-103 (a)  2x100 2x100 1x102 1x106 
Ru-105 1x100 6x10-1 1x101 1x106 
Ru-106 (a)  2x10-1 2x10-1 1x102(b) 1x105(b) 
Sulfur (16)     
S-35 4x101 3x100 1x105 1x108 
Antimony (51)      
Sb-122 4x10-1 4x10-1 1x102 1x104 
Sb-124 6x10-1 6x10-1 1x101 1x106 
Sb-125 2x100 1x100 1x102 1x106 
Sb-126 4x10-1 4x10-1 1x101 1x105 
Scandium (21)      
Sc-44 5x10-1 5x10-1 1x101 1x105 
Sc-46 5x10-1 5x10-1 1x101 1x106 
Sc-47 1x101 7x10-1 1x102 1x106 
Sc-48 3x10-1 3x10-1 1x101 1x105 
Selenium (34)       - 42 - 
Se-75 3x100 3x100 1x102 1x106 
Se-79 4x101 2x100 1x104 1x107 
Silicon (14)      
Si-31 6x10-1 6x10-1 1x103 1x106 
Si-32 4x101 5x10-1 1x103 1x106 
Samarium (62)      
Sm-145 1x101 1x101 1x102 1x107 
Sm-147 Unlimited  Unlimited  1x101 1x104 
Sm-151 4x101 1x101 1x104 1x108 
Sm-153 9x100 6x10-1 1x102 1x106 
Tin (50)      
Sn-113 (a)  4x100 2x100 1x103 1x107 
Sn-117m 7x100 4x10-1 1x102 1x106 
Sn-119m  4x101 3x101 1x103 1x107 
Sn-121m (a)  4x101 9x10-1 1x103 1x107 
Sn-123 8x10-1 6x10-1 1x103 1x106 
Sn-125 4x10-1 4x10-1 1x102 1x105 
Sn-126 (a)  6x10-1 4x10-1 1x101 1x105 
Strontium (38)      
Sr-82 (a)  2x10-1 2x10-1 1x101 1x105 
Sr-85 2x100 2x100 1x102 1x106 
Sr-85m 5x100 5x100 1x102 1x107 
Sr-87m 3x100 3x100 1x102 1x106 
Sr-89 6x10-1 6x10-1 1x103 1x106 
Sr-90 (a)  3x10-1 3x10-1 1x102(b) 1x104(b) 
Sr-91 (a)  3x10-1 3x10-1 1x101 1x105 
Sr-92 (a)  1x100 3x10-1 1x101 1x106 
Tritium (1)      
T(H-3) 4x101 4x101 1x106 1x109 
Tantalum (73)      
Ta-178 (with long half -life) 1x100 8x10-1 1x101 1x106 
Ta-179 3x101 3x101 1x103 1x107 
Ta-182 9x10-1 5x10-1 1x101 1x104 
Terbium (65)      
Tb-157 4x101 4x101 1x104 1x107 
Tb-158 1x100 1x100 1x101 1x106 
Tb-160 1x100 6x10-1 1x101 1x106 
Technetium (43)      
Tc-95m (a)  2x100 2x100 1x101 1x106 
Tc-96 4x10-1 4x10-1 1x101 1x106 
Tc-96m (a)  4x10-1 4x10-1 1x103 1x107 
Tc-97 Unlimited  Unlimited  1x103 1x108 
Tc-97m 4x101 1x100 1x103 1x107 
Tc-98 8x10-1 7x10-1 1x101 1x106 
Tc-99 4x101 9x10-1 1x104 1x107 
Tc-99m 1x101 4x100 1x102 1x107 
Tellurium (52)       - 43 - 
Te-121 2x100 2x100 1x101 1x106 
Te-121m  5x100 3x100 1x102 1x106 
Te-123m  8x100 1x100 1x102 1x107 
Te-125m  2x101 9x10-1 1x103 1x107 
Te-127 2x101 7x10-1 1x103 1x106 
Te-127m (a)  2x101 5x10-1 1x103 1x107 
Te-129 7x10-1 6x10-1 1x102 1x106 
Te-129m (a)  8x10-1 4x10-1 1x103 1x106 
Te-131m (a)  7x10-1 5x10-1 1x101 1x106 
Te-132 (a)  5x10-1 4x10-1 1x102 1x107 
Thorium (90)      
Th-227 1x101 5x10-3 1x101 1x104 
Th-228 (a) 5x10-1 1x10-3 1x100(b) 1x104(b) 
Th-229 5x100 5x10-4 1x100(b) 1x103(b) 
Th-230 1x101 1x10-3 1x100 1x104 
Th-231 4x101 2x10-2 1x103 1x107 
Th-232 Unlimited  Unlimited  1x101 1x104 
Th-234 (a)  3x10-1 3x10-1 1x103(b) 1x105(b) 
Th (natural)  Unlimited  Unlim ited 1x100(b) 1x103(b) 
Titanium (22)      
Ti-44 (a)  5x10-1 4x10-1 1x101 1x105 
Thallium (81)      
Tl-200 9x10-1 9x10-1 1x101 1x106 
Tl-201 1x101 4x100 1x102 1x106 
Tl-202 2x100 2x100 1x102 1x106 
Tl-204 1x101 7x10-1 1x104 1x104 
Thulium (69)      
Tm-167 7x100 8x10-1 1x102 1x106 
Tm-170 3x100 6x10-1 1x103 1x106 
Tm-171 4x101 4x101 1x104 1x108 
Uranium (92)      
U-230 (rapid lung retention) (a)(d)  4x101 1x10-1 1x101(b) 1x105(b) 
U-230 (medium lung retention) (a)(e)  4x101 4x10-3 1x101 1x104 
U-230 (slow lung  retention) (a)(f)  3x101 3x10-3 1x101 1x104 
U-232 (rapid lung retention) (d)  4x101 1x10-2 1x100(b) 1x103(b) 
U-232 (medium lung retention) (e)  4x101 7x10-3 1x101 1x104 
U-232 (slow lung retention) (f)  1x101 1x10-3 1x101 1x104 
U-233 (rapid lung retention)  (d) 4x101 9x10-2 1x101 1x104 
U-233 (medium lung retention) (e)  4x101 2x10-2 1x102 1x105 
U-233 (slow lung retention) (f)  4x101 6x10-3 1x101 1x105 
U-234 (rapid lung retention) (d)  4x101 9x10-2 1x101 1x104 
U-234 (medium lung retention) (e)  4x101 2x10-2 1x102 1x105 
U-234 (slow lung retention) (f)  4x101 6x10-3 1x101 1x105 
U-235 (all types of lung retention) (a)(d)(e)(f)  Unlimited  Unlimited  1x101(b) 1x104(b) 
U-236 (quick retention) (d)  Unlimited  Unlimited  1x101 1x104 
U-236 (medium retention rate) (e)  4x101 2x10-2 1x102 1x105 
U-236 (slow retention) (f)  4x101 6x10-3 1x101 1x104  - 44 - 
U-238 (all types of lung retention) (d)(e)(f)  Unlimited  Unlimited  1x101(b) 1x104(b) 
U (natural)  Unlimited  Unlimited  1x100(b) 1x103(b) 
U (enriched up to 20 % or less) (g)  Unlimite d Unlimited  1x100 1x103 
U (depleted)  Unlimited  Unlimited  1x100 1x103 
Vanadium (23)      
V-48 4x10-1 4x10-1 1x101 1x105 
V-49 4x101 4x101 1x104 1x107 
Wolfram (74)      
W-178 (a)  9x100 5x100 1x101 1x106 
W-181 3x101 3x101 1x103 1x107 
W-185 4x101 8x10-1 1x104 1x107 
W-187 2x100 6x10-1 1x102 1x106 
W-188 (a)  4x10-1 3x10-1 1x102 1x105 
Xenon (54)      
Xe-122 (a)  4x10-1 4x10-1 1x102 1x109 
Xe-123 2x100 7x10-1 1x102 1x109 
Xe-127 4x100 2x100 1x103 1x105 
Xe-131m  4x101 4x101 1x104 1x104 
Xe-133 2x101 1x101 1x103 1x104 
Xe-135 3x100 2x100 1x103 1x1010 
Yttrium (39)      
Y-87 (a)  1x100 1x100 1x101 1x106 
Y-88 4x10-1 4x10-1 1x101 1x106 
Y-90 3x10-1 3x10-1 1x103 1x105 
Y-91 6x10-1 6x10-1 1x103 1x106 
Y-91m 2x100 2x100 1x102 1x106 
Y-92 2x10-1 2x10-1 1x102 1x105 
Y-93 3x10-1 3x10-1 1x102 1x105 
Ytterbium (70)      
Yb-169 4x100 1x100 1x102 1x107 
Yb-175 3x101 9x10-1 1x103 1x107 
Zinc (30)      
Zn-65 2x100 2x100 1x101 1x106 
Zn-69 3x100 6x10-1 1x104 1x106 
Zn-69m (a)  3x100 6x10-1 1x102 1x106 
Zirconium (40)      
Zr-88 3x100 3x100 1x102 1x106 
Zr-93 Unlimited  Unlimited  1x103(b) 1x107(b) 
Zr-95 (a)  2x100 8x10-1 1x101 1x106 
Zr-97 (a)  4x10-1 4x10-1 1x101(b) 1x105(b) 
Legend:  
(a) For the listed parent radionuclides, the values A 1 and A 2 include contributions from radioactive  decay 
products with a decay half -life of less than 10 days:  
Mg-28 Al-28 
Ar-42 K-42 
Ca-47 Sc-47 
Ti-44 Sc-44 
Fe-52 Mn-52m 
Fe-60 Co-60m  - 45 - 
Zn-69m Zn-69 
Ge-68 Ga-68 
Rb-83 Kr-83m 
Sr-82 Rb-82 
Sr-90 Y-90 
Sr-91 Y-91m 
Sr-92 Y-92 
Y-87 Sr-87m 
Zr-95 Nb-95m 
Zr-97 Nb-97m,  Nb-97 
Mo-99 Tc-99m 
Tc-95m Tc-95 
Tc-96m Tc-96 
Ru-103 Rh-103m  
Ru-106 Rh-106 
Pd-103 Rh-103m  
Ag-108m  Ag-108 
Ag-110m  Ag-110 
Cd-115 In-115m  
In-114m  In-114 
Sn-113 In-113m  
Sn-121m  Sn-121 
Sn-126 Sb-126m  
Te-118 Sb-118 
Te-127m  Te-127 
Te-129m  Te-129 
Te-131m  Te-131 
Te-132 I-132 
I-135 Xe-135m  
Xe-122 I-122 
Cs-137 Ba-137m  
Ba-131 Cs-131 
Ba-140 La-140 
Ce-144 Pr-144m, Pr -144 
Pm-148m  Pm-148 
Gd-146 Eu-146 
Dy-166 Ho-166 
Hf-172 Lu-172 
W-178 Ta-178 
W-188 Re-188 
Re-189 Os-189m  
Os-194 Ir-194 
Ir-189 Os-189m  
Pt-188 Ir-188 
Hg-194 Au-194 
Hg-195m  Hg-195 
Pb-210 Bi-210 
Pb-212 Bi-212, Tl -208, Po -212 
Bi-210m  Tl-206 
Bi-212 Tl-208, Po -212 
At-211 Po-211 
Rn-222 Po-218, Pb -214, At -218, Bi -214, Po -214 
Ra-223 Rn-219, Po -215, Pb -211, Bi -211, Po -211, Tl -207 
Ra-224 Rn-220, Po -216, Pb -212, Bi -212, Tl -208, Po -212 
Ra-225 Ac-225, Fr -221, At -217, Bi -213, Tl -209, Po -213, Pb -209 
Ra-226 Rn-222, Po -218, Pb -214, At -218, Bi -214, Po -214 
Ra-228 Ac-228 
Ac-225 Fr-221, At -217, Bi -213, Tl -209, Po -213, Pb -209 
Ac-227 Fr-223 
Th-228 Ra-224, Rn -220, Po -216, Pb -212, Bi -212, Tl-208, Po -212  - 46 - 
Th-234 Pa-234m, Pa -234 
Pa-230 Ac-226, Th -226, Fr -222, Ra -222, Rn -218, Po -214 
U-230 Th-226, Ra -222, Rn -218, Po -214 
U-235 Th-231 
Pu-241 U-237 
Pu-244 U-240, Np -240m  
Am-242m  Am-242, Np -238 
Am-243 Np-239 
Cm-247 Pu-243 
Bk-249 Am-245 
Cf-253 Cm-249 
(b) Parent radionuclides and products of their radioactive decay corresponding to permanent equilibrium:  
Sr-90 Y-90 
Zr93  Nb-93m 
Zr-97 Nb-97 
Ru-106 Rh-106 
Ag-108m  Ag-108 
Cs-137 Ba-137m  
Ce-144 Pr-144 
Ba-140 La-140 
Bi-212 Tl-208 (0.36), Po -212 (0.64)  
Pb-210 Bi-201, Po -210 
Pb-212 Bi-212, Tl -208 (0.36), Po -212 (0.64)  
Rn-222 Po-218, Pb -214, Bi -214, Po -214 
Ra-223 Rn-219, Po -215, Pb -211, Bi -211, Tl -207 
Ra-224 Rn-220, Po -216, Pb -212, Bi -212, Tl -208 (0.36), Po -212 (0.64)  
Ra-226 Rn-222, Po -218, Pb -214, Bi -214, Po -214, Pb-210, Bi -210, Po -210 
Ra-228 Ac-228 
Th-228 Ra-224, Rn -220, Po -216, Pb212, Bi -212, Tl208 (0.36), Po -212 (0.64)  
Th-229 Ra-225, Ac -225, Fr -221, At -217, Bi -213, Po -213, Pb -209 
Th natural  Ra-228, Ac -228, Th -228, Ra -224, Rn -220, Po -216, Pb -212, Bi -212, Tl -208(0.36), Po -212(0.64)  
Th-234 Pa-234m  
U-230 Th-226, Ra -222, Rn -218, Po -214 
U-232 Th-228, Ra -224, Rn -220, Po -216, Pb -212, Bi -212, Tl -208 (0.36), Po -212 (0.64)  
U-235 Th-231 
U-238 Th-234, Pa -234m  
U natural  Th-234, Pa -234m, U -234, Th -230, Ra -226, Rn -222, Po -218, Pb-214, Bi -214, Po -214, Pb -210, Bi -
210, Po -210 
Np-237 Pa-233 
Am-242m  Am-242 
Am-243 Np-239 
(c) Activity may be determined from a measurement of the rate of decay or a measurement of the radiation level 
at a prescribed distance from the radionuclide source o f ionising radiation.  
(d) These values apply only to uranium compounds UF 6, U 2F2 and UO 2(NO 3)2 in both normal and accident 
conditions of transport.  
(d) These values apply only to uranium compounds UO 3, UF 4, UCl 4 and hexavalent uranium compounds in both 
normal and accident conditions of transport.  
(f) These values apply to all compounds of uranium other than those specified in (d) and (e).  
(g) These values apply to unirradiated uranium only.  
 
 
DETERMINATION OF BAS IC RADIONUCLIDE VALU ES 
 
3. (403.)  1. For a ra dionuclide not listed in Table  2, specific activity limits for material 
exception and activity limits for package exception shall be calculated in 
accordance with principles and methods stipulated in Annex  7 to this decree, or 
values in Table  3 shall be us ed. The value of A 2 may also be calculated using the 
dose coefficient for the relevant lung absorption type, according to International  - 47 - 
Atomic Energy Agency recommendations, where the calculation shall take into 
account the chemical form of each radionucli de under normal conditions of 
transport and under accident conditions of transport.  
 
2. For a radionuclide enclosed or contained in an instrument or product that meets 
the requirements of Point  23(c), an alternative basic value may be used to the 
basic val ue for the specific activity limit for material exception listed in Table  2. 
This alternative value shall be calculated in accordance with procedures and 
methods described in Annex  7 to this decree.  
 
4. (404.)  In the calculations of A 1 a A 2 for a radionucl ide not in Table  2: 
a) a single radioactive decay chain in which the radionuclides are present in their 
naturally occurring proportions, and in which no daughter nuclide has a half -
life either longer than 10 days or longer than of the parent nuclide, shall be  
considered as a single radionuclide; and the activity to be taken into account 
and the A 1 a A 2 value to be applied shall be those corresponding to the parent 
nuclide of that chain;  
b) a radioactive decay chain in which any daughter nuclide has a half -life ei ther 
longer than 10 days or greater than that of the parent nuclide, the parent and 
such daughter nuclides shall be considered as mixtures of different nuclides.  
 
5. (405.)  For mixtures of radionuclides for which basic radionuclide values are provided in 
Table 2, basic values shall be determined using the formula:  
Xm = 1 / Σ[f(i)/X(i)],  
 I 
where:  
f(i) is the fraction of activity or activity concentration of radionuclide  i in the 
mixture;  
 X(i) is the appropriate value of A 1 or A 2 or the activity concentration for exempt 
material or the activity limit for an exempt consignmen t for the relevant 
radionuclide i; 
 Xm is the basic value derived for a mixture from A 1 or A 2, or the activity 
concentration for exempt material or the activity limit for an exempt consignment.  
 
6. (406.)  When the identity of each radionuclide is known but  the individual activities of 
some of the radionuclides are not known, the radionuclides may be grouped 
according to the type of emitted radiation (alpha, beta, or gamma) with known 
overall activities for the given group, and calculations may be performed 
according to the formula s in Points  5 and 30 using appropriate lowest radionuclide 
values from A 1, A 2,, specific activity limits for exempt material, or activity limits 
for the exempt consignment in each group. For groups based on total alpha 
activity, the  lowest radionuclide values for radionuclide sources emitting alpha 
radiation (hereinafter an “alpha emitter ”) in the given group shall be used. For 
groups based on the total beta or gamma activity, the lowest radionuclide values 
for radionuclide sources e mitting beta or gamma radiation (hereinafter an “beta or 
gamma emitter ”) in the given group shall be used.  
 
7. (407.)  For radionuclides or for mixtures of radionuclides for which relevant data for the 
use of Table  2 is not available, the values shown in Ta ble 3 shall be used. s  - 48 - 
Table  3(3.) Basic radionuclide values for unknown radionuclides or mixtures  
 
Radioactive contents  A1 A2 Activity 
concentratio
n limits for 
exempt 
material  Activity limits 
for an exempt 
consignment  
 [TBq]  [TBq]  [Bq/g]  [Bq] 
Only beta o r gamma emitters are known to be 
present  0.1 0.02 1x101 1x104 
Alpha emitters are known to be present, but 
radionuclide sources emitting neutrons 
(hereinafter “neutron emitter ”) are not known 
to be present  0.2 9x10-5 1x10-1 1x103 
Neutron emitters are know n to be present or 
no relevant data are available  0.001  9x10-5 1x10-1 1x103 
 
MATERIAL CLASSIFICAT ION 
 
Material with low specific activity  
8. (408.)  A radioactive or fissile material is classified as material with low specific activity 
if 
a) it conforms to t he definition in §  2(i); 
b) it meets the requirements of Points  9 to 11; and  
c) it meets relevant requirements of Points  17 to 22 of Annex  4 to this decree.  
 
9. (409.)  1. A material with low specific activity is classified in group LSA -I, LSA -II, or 
LSA -III. 
 
2. Group LSA -I includes:  
a) uranium and thorium ores, their concentrates, and other ores containing 
naturally occurring radionuclides;  
b) natural or depleted uranium, natural thorium, or their compounds or mixtures, 
which have not been irradiated and are in solid or liquid form;  
c) a radioactive material for which A 2 is unlimited; of fissile material, only an 
exempt fissile material may be included;  
d) other radioactive material in which activity is uniformly distributed throughout 
their volume, and the calculated mean s pecific activity does not exceed 30 
times the specific activity limit for material exemption stipulated pursuant to 
Points  2 and 7, where external shielding materials surrounding the LSA 
material are not taken into account in determining the mean specific activity; of 
fissile material, only an exempt fissile material may be included.  
 
3. Group LSA -II includes:  
a) water with tritium with concentration up to 0.8 TBq/l;  
b) other materials in which activity is uniformly distributed throughout their 
volume, and the ca lculated mean specific activity does not exceed 10-4 A2/g for 
solids and gases and 10-5 A2/g for liquids, where external shielding materials 
surrounding the LSA material are not taken into account in determining the 
mean specific activity.   - 49 - 
 
4. Group LSA -III includes solids, except for powdered materials, that meet the 
requirements of Point  1 of Part  I of Annex  1 to this decree, and in which:  
a) the radioactive or fissile material is uniformly distributed throughout the 
volume of the solid material or in an arr ay of several solid objects, or is 
relatively uniformly distributed in a compact bonding agent;  
b) the radioactive or fissile material is relatively insoluble or is contained in a 
relatively insoluble matrix in such a manner that even in the event of loss of 
packaging, the loss of radioactive or fissile material from one package through 
leaching in water for 7 days does not exceed 0.1 A 2; and  
c) the calculated mean specific activity of solid material without shielding does 
not exceed 2.10-3 A2/g, where external s hielding materials surrounding the LSA 
material are not taken into account in determining the mean specific activity.  
 
10. (410.)  A package with non -flammable solid material of group LSA -II or LSA -III must 
not contain activity greater than 3  000 A2 when be ing transported by air.  
 
11. (411.)  The radioactive contents in a single package of LSA material shall be so restricted 
that the radiation level specified in Point  17 of Annex  4 to this decree shall not be 
exceeded, and the activity in a single package sha ll be so restricted that the 
activity limits for a conveyance specified in Point  22 of Annex  4 to this decree 
shall not be exceeded.  
 
Surface contaminated object  
12. (412.)  A radioactive or fissile material is classified as a surface contaminated object 
(SCO) if:  
a) it conforms to the definition in §  2(l); 
b) it meets the requirements of Points  13 and 14; and  
c) it meets relevant requirements of Points  17 to 22 of Annex  4 to this decree.  
 
13. (413.)  1. A surface contaminated object is classified in group SCO -I or SC O-II. 
 
2. Group SCO -I includes a solid object for which:  
a) non-fixed contamination on the accessible surface averaged over 300  cm2 (or 
the entire surface if less than 300  cm2) does not exceed:  
1. 4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitt ers, 
2. or 0.4  Bq/cm2 for all other alpha emitters;  
b) fixed contamination on the accessible surface averaged over 300  cm2 (or the 
entire surface if less than 300 cm2) does not exceed:  
1. 4.104 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or  
2. 4.103 Bq/cm2 for all other alpha emitters; and  
c) the sum of fixed and non -fixed contamination on the accessible surface 
averaged over 300  cm2 (or the entire surface if less than 300  cm2) does not 
exceed:  
1. 4.104 Bq/cm2 for beta and gamma emitters and low toxic ity alpha 
emitters, or  
2. 4.103 Bq/cm2 for all other alpha emitters.  
 
3. Group SCO -II includes a solid object on which either the fixed or non -fixed  - 50 - 
contamination on the surface exceeds the applicable limits specified (2) and for 
which:  
a) non-fixed contaminatio n on the accessible surface averaged over 300  cm2 (or 
the entire surface if less than 300  cm2) does not exceed:  
1. 400 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters,  
2. 40 Bq/cm2 for all other alpha emitters;  
b) fixed contamination on the acces sible surface averaged over 300  cm2 (or the 
entire surface if less than 300  cm2) does not exceed:  
1. 8.105 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or  
2. 8.104 Bq/cm2 for all other alpha emitters; and  
c) the sum of fixed and non -fixed con tamination on the accessible surface 
averaged over 300  cm2 (or the entire surface if less than 300  cm2) does not 
exceed:  
1. 8.105 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or  
2. 8.104 Bq/cm2 for all other alpha emitters.  
 
14. (414.)  The radioactive contents in a package with an SCO shall be so restricted that the 
radiation level specified in Point  17 of Annex  4 to this decree shall not be 
exceeded, and the activity in a single package shall be so restricted that the 
activity limits for a  conveyance specified in Point  22 of Annex  4 to this decree 
shall not be exceeded.  
 
Special form radioactive material  
15. (415.)  A radioactive or fissile material is classified as a special form radioactive material 
if: 
a) it meets the requirements of Points  2 to 4 of Part  I of Annex  1 to this decree, 
and 
b) it is type approved as a special form radioactive material pursuant to 
§ 137(1)(b) of the Act.  
 
Low dispersible radioactive material  
16. (416.)  A radioactive or fissile material is classified as a slow disper sible radioactive 
material if:  
a) it meets the requirements of Point  5 of Part  I of Annex  1 to this decree;  
b) it is type approved as a low dispersible radioactive material pursuant to 
§ 137(1)(c) of the Act; and  
c) the package containing it meets the requirements of Point  65 of Part  I of 
Annex  1 to this decree.  
 
Fissile material  
17. (417.)  Fissile material and a package containing fissile material shall be classified as 
FISSILE MATERIAL  under the relevant entry in Table  1. Assuming that they are 
transported in pack ages that meet the requirements of Point  36 of Part  I of 
Annex  1 to this decree, and pursuant to the requirements of Point  70 of Annex  4 
to this decree, the following are exempt from the above requirement:  
a) uranium enriched with 235U to a maximum of 1  % by mass, and with a total 
plutonium and 233U content not exceeding 1  % of the mass of 235U provided  - 51 - 
that the fissile nuclides are distributed essentially homogeneously throughout 
the material. If 235U is present in metallic, oxide or carbide forms, it shall n ot 
form a lattice arrangement.  
b) liquid solutions of uranyl nitrate enriched in 235U to a maximum of 2  % by 
mass, with a total plutonium and 233U content not exceeding 0.002  % of the 
mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) 
of 2; 
c) uranium enriched with 235U to a maximum of 5  % by mass, assuming:  
1. the mass of 235U is no greater than 3.5  g per package;  
2. total plutonium and 233U content does not exceed 1  % of the mass of 
235U per package; and  
3. transport of the package is restricted by limits for a consignment 
specified in Point  70(c) of Annex  4 to this decree;  
d) fissile radionuclides with total mass not exceeding 2  g per package, assuming 
that transport of the package is restricted by limits for a consignment specified 
in Point  70(d) o f Annex  4 to this decree;  
e) fissile radionuclides with total mass not exceeding 45  g in packaging or 
unpackaged, assuming that transport of the package is restricted by limits for a 
consignment specified in Point  70(e) of Annex  4 to this decree;  
f) fissile mate rials that meet the requirements of Point  70(b) of Annex  4 to this 
decree and Point  6 of Part  I of Annex  1 to this decree;  
if they are transported, except for unpackaged fissile radionuclides pursuant to (e), 
in a package whose smallest external overall di mension is greater than or equal to 
10 cm. 
 
18. (418.)  The contents of a package containing fissile material must meet the requirements 
stipulated for package design by this decree or a type approval decision.  
 
Uranium hexafluoride  
19. (419.)  Uranium hexaf luoride is classified under one of the following UN numbers:   
a) UN 2977, RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, 
FISSILE MATERIAL;  
b) UN 2978, RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, 
exempt fissile material or non -fissile material;  
c) UN 3507  URANIUM HEXAF LUORIDE , RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTIONS – less than 0.1  kg in package, exempt fissile 
material or non -fissile material.  
 
20. (420.)  Packages containing uranium hexafluoride shall comply with the following:  
a) the mass of uranium hexafluoride shall c orrespond to this permitted mass for 
the given package type;  
b) the mass of uranium hexafluoride shall not be greater than a value that would 
lead to an ullage smaller than 5  % at the maximum temperature of the package 
as specified for facilities where the pa ckage shall be used; and  
c) the uranium hexafluoride shall be in solid form and the internal pressure shall 
not be greater than atmospheric pressure when handed over for carriage.  
 
CLASSIFICATION OF PA CKAGES  
 
21. (421.)  The quantity of radioactive or fissile material in a package shall not exceed the  - 52 - 
relevant limits for the given package type in Points  22 to 33.  
 
Classification as a package exception  
22. (422.)  A packages is classified as a package exception if:  
a) it is an empty package that had contained radioa ctive material;  
b) it contains an instrument or product whose activity does not exceed limits 
specified in Table  4; 
c) it contains a product manufactured from natural uranium, depleted uranium, or 
natural thorium;  
d) it contains a radioactive material whose activit y does not exceed limits 
specified in Table  4; 
e) it contains less than 0.1  kg of uranium hexafluoride, whose activity does not 
exceed the limits specified in the column ‘Materials - Package limits ’ in 
Table  4. 
 
Table  4(4.) Activity limits for package excepti on 
Physical state of contents (phase)  Device or product  Materials - 
Package 
limitsa)  Item 
limitsa) Package 
limitsa)  
Solids:     
special form radioactive material  10-2A1 A1 10-3A1 
radioactive material other than special form  10-2A2 A2 10-3A2 
Liquid  10-3A2 10-1A2 10-4A2 
Gases:     
Tritium (3H) 2x10-2A2 2x10-1A2 2x10-2A2 
special form radioactive material  10-3A1 10-2A1 10-3A1 
radioactive material other than special form  10-3A2 10-2A2 10-3A2 
 Legend:  
a) For mixtures of radionuclides, see Points  4 to 6. 
 
 
 
23. (423.)  1. Radioactive material that is enclosed in or contained in an instrument or 
product may be classified under UN 2911, RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTION - DEVICES or PRODUCTS, if: 
a) the radiation level at 10  cm from any point on the ext ernal surface of any 
unpackaged instrument or product is less than or equal to 0.1  mSv/h;  
b) each device or product is marked ' RADIOACTIVE '. Marking is not required 
for: 
1. the faces of timepieces or other devices marked with radioluminescent 
paint;  
2. consumer pro ducts that have either received type approval from the 
Office or do not individually exceed the activity limit for an exempt 
consignment in the column marked ‘Activity limit for an exempt 
consignment [Bq] ’ in Table  2, provided that they are transported in a 
package that is marked ‘RADIOACTIVE ’ on an internal surface in such 
a manner that is visible when the package is opened;  
3. other devices or products that are too small to be marked with 
‘RADIOACTIVE ’, if they are transported in packaging that is marked  - 53 - 
‘RADIOACTIVE ’ on an internal surface in such a manner that is visible 
when the package is opened;  
c) the radioactive material is completely enclosed by a non -active compound; a 
device performing the sole function of containing radioactive material shall not 
be considered to be an instrument or product pursuant to Point  23; 
d) the activity limits specified in the column ‘Item limits ’ in Table  4 are met for an 
instrument or product, and the activity limits specified in the column ‘Package 
limits ’ in Table  4 are met fo r a package.  
 
24. (424.)  1. Radioactive material in forms other than as specified in Point  23 and with an 
activity not exceeding the limits specified in the column ‘Materials - Package 
limits ’ of Table  4 is classified under UN 2910, RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTION - LIMITED QUANTITY OF MATERIAL , provided 
that: 
a) the package retains its radioactive contents under routine conditions of 
transport;  
b) the package is marked ‘RADIOACTIVE ’ 
1. on an internal surface in such a manner that is visible when the package  
is opened, or  
2. elsewhere than on the package if marking the internal surface is not 
feasible.  
 
25. (425.)  Uranium hexafluoride, if its activity does not exceed the limits specified in the 
column ‘Materials - Package limits ’ of Table  4 is classified under U N 3507  
URANIUM HEXAFLUORIDE , RADIOACTIVE MATERIAL, PACKAGE 
EXCEPTION – less than 0.1  kg in the package, exempt fissile material or non -
fissile material, if:  
a) the mass of uranium hexafluoride in the package is less than 0.1  kg, and  
b) the requirements of Points  20 and 24 are met.  
 
26. (426.)  Articles manufactured of natural uranium, depleted uranium or natural thorium 
and articles in which the sole radioactive material is unirradiated natural uranium, 
unirradiated depleted uranium, or unirradiated natural thoriu m may be classified 
under UN 2909, RADIOACTIVE MATERIAL, PACKAGE EXCEPTION - 
PRODUCTS MADE FROM N ATURAL URANIUM or DEPLETED URANIUM 
or THORIUM, if the outer surface of the uranium or thorium is enclosed in an 
inactive sheath made of metal or some other sub stantial material.  
 
Additional requirements and controls for transport of empty packagings  
27. (427.)  An empty packaging that had previously contained radioactive material may be 
classified under UN 2908, RADIOACTIVE MATERIAL, PACKAGE 
EXCEPTION - EMPTY PAC KAGING, if: 
a) it is defect -free condition and securely closed;  
b) the outer surface of any uranium or thorium in its structure is covered with an 
inactive sheath made of metal or some other substantial material;  
c) the level of internal non -fixed contamination doe s not exceed one hundred 
times the limits specified in Point  8 of Annex  4 to this decree; and  
d) any labels which may have been displayed on it in conformity with Point  38 of 
Annex  4 to this decree are no longer visible.  
  - 54 - 
Classification as a  Type A package  
28. (428.)  A package containing radioactive or fissile material is classified as a Type A 
package if it adheres to the requirements of Points  29 and 30.  
 
29. (429.)  Type A packages shall not contain activities greater than the following::  
a) A1 for special form  radioactive material; and  
b) A2 for radioactive material other than special form.  
 
30. (430.)  For mixtures of radionuclides whose identities and activities are known, the 
following condition shall apply to the radioactive contents of a Type A package:  
Σ [B(i)/A 1(i)] + Σ [C(j)/A 2(j)]  1, 
 i j 
where:  
B(i) is the activity of radionuclide i as special form radioactive material;  
A1(i) value of A 1 for radionuclide  i; 
C(j) is the activity of radionuclide j as other than special form radioactive material;  
A2(j) is t he value of A 2 for radionuclide  j. 
 
Classification as a  Type B(U), B(M), and C package  
31. (431.)  A Type B(U), Type B(M) and Type C package shall be classified in accordance 
with a type approval decision issued by the Office or in accordance with 
document issued by a competent authority of the country of origin of design.  
 
32. (432.)  A Type B(U), Type B(M) and Type C package shall meet specifications in a type 
approval decision issued by the Office or specifications in a document issued by a 
competent autho rity of the country of origin of design.  
 
33. (433.)  A Type B(U) and Type B(M) package, if transported by air, shall meet the 
requirements of Point  32 and shall not contain activities greater than the 
following:  
a) for low dispersible radioactive material, ac tivity values approved for the given 
design;  
b) for special form radioactive material, 3  000 A1 or 100  000 A2, whichever is 
lower;  
c) for other than special form radioactive material, 3  000 A2. 
 
 
TRANSPORT UNDER SPEC IAL ARRANGEMENTS  
 
34. (434.)  Radioactive or fi ssile material shall be classified as transported under special 
arrangements if it is carried pursuant to §  9(4)(c) of the Act.  
  - 55 - 
 
Annex  4 to Decree  No …………  
 
TECHNICAL AND ORGANI SATIONAL CONDITIONS OF CARRIAGE AND 
TRANSPORT OF RADIOAC TIVE OR FISSILE MATE RIAL 
 
REQUIREMENTS BEFORE THE FIRST SHIPMENT  
 
1. (501.)  Before a packaging is first used to transport radioactive or fissile material:  
a) it shall be confirmed that it has been manufactured in conformity with design 
specifications, and  
b) meets the following requi rements:  
1. if the design pressure of the containment system exceeds 35  kPa, the 
containment system of each packaging shall conform to approved 
design requirements relating to the capability of that system to maintain 
its integrity under that pressure;  
2. the ef fectiveness of shielding and containment and, where necessary, 
the heat transfer characteristics and the effectiveness of the confinement 
system of packaging intended for use as a Type B(U), Type B(M) or 
Type C package and packaging intended for the carria ge of fissile 
material shall be within the limits of the approved design;  
3. packaging intended for the carriage of fissile material it shall be capable 
of ensuring effectiveness of the criticality safety features within the 
limits applicable to or specified for the design. Where, in order to 
comply with the requirements of Point  73 of Part  I of Annex  1 to this 
decree, neutron poisons are included in the packaging, checks shall be 
performed to confirm the presence and distribution of those neutron 
poisons.  
 
REQUIREMENTS BEFORE EA CH SHIPMENT  
 
2. (502.)  Before shipment of a package, it shall be ensured that it contain:  
a) radionuclides different from those specified for the package design; and  
b) contents in a form, or physical or chemical state, different from those s pecified 
for the package design.  
 
3. (503.)  Before shipment of a package:  
a) lifting attachments that do not meet the requirements of Point  8 of Part  I of 
Annex  1 to this decree shall be removed or otherwise rendered incapable of 
being used for lifting the pa ckage, in accordance with Point  9 of Part  I of 
Annex  1 to this decree;  
b) a Type B(U), Type B(M) and Type C package shall achieve equilibrium 
conditions sufficient to demonstrate compliance with the requirements for 
temperature and pressure, pursuant to the p ackaging type approval decision 
issued by the Office or a relevant authority of the State of origin of the 
packaging;  
c) closures, valves, or other openings of the containment system through which 
the radioactive contents of a Type B(U), B(M), C package might  escape are 
closed and, where feasible, sealed in a manner where checks or suitable tests  - 56 - 
are capable of demonstrating compliance with the requirements of Points  59 
and 71 of Part  I of Annex  1 to this decree;  
d) for a package containing fissile material, the measurements specified in 
Point  77(b) of Part  I of Annex  1 to this decree and the tests to demonstrate 
closure of the package as specified in Point  80 of Part  I of Annex  1 to this 
decree shall be performed.  
 
 
TRANSPORT OF OTHER G OODS  
 
4. (504.)  A package m ay contain only instruments necessary for the handling of the 
radioactive content. The interaction between these instruments and the package, 
under the conditions of transport applicable to its design, shall not reduce the its 
safety.  
 
5. (505.)  Freight co ntainers, IBCs, packagings, and overpacks used for the transport of 
radioactive or fissile material may be used for the storage or transport of other 
goods if after their decontamination, the value of non -fixed surface contamination:  
a) is less than 0.4  Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters;  
b) is less than 0.04  Bq/cm2 for all other alpha emitters.  
 
6. (506.)  A consignment shall be segregated from other dangerous goods during transport 
in compliance with the relevant regulations for c arriage of dangerous goods of the 
country of origin, transit, and destination; regulations of a qualified carrier may 
also be used if they ensure the same or a greater level of protection.  
 
 
OTHER DANGEROUS PROP ERTIES OF CONTENTS  
 
7. (507.)  Any other dange rous properties of the contents of the package, such as 
explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness, 
shall be taken into account in the packing, labelling, marking, placarding, storage 
and transport.  
 
 
REQUIREMENTS FOR D ETECTING CONTAMINATI ON AND FOR SECURING 
LEAKING PACKAGES  
 
8. (508.)  The non -fixed contamination on the external surfaces of a package shall be kept as 
low as practicable and, under routine conditions of transport, shall not exceed the 
following limits:  
a) 4.0 Bq/cm2 for gamma and beta emitters and low toxicity alpha emitters;  
b) 0.4 Bq/cm2 for all other alpha emitters;  
these limits are applicable when averaged over any area of 300  cm² of any part of 
the surface.  
 
9. (509.)  The level of non -fixed contamination on the external and internal surfaces of a 
freight container, IBC, packaging, and overpack shall not exceed the limits 
specified in Point  8.  - 57 - 
 
10. (510.)  If there is suspicion or it is evident that a package is damaged or that radioactive 
contents are leaking,  access to the package shall be restricted and a qualified 
person shall assess the extent of contamination and the resultant radiation level of 
the package. The assessment shall include the package, the conveyance, the 
adjacent loading and unloading areas and, if necessary, all other material that has 
been carried on or in the conveyance.  
 
11. (511.)  A damaged package or a package leaking radioactive contents in excess of 
allowable limits for normal conditions of transport shall be repaired or otherwise 
restored to a functional state and decontaminated prior to being forwarded for 
further carriage. Until it is forwarded for further carriage, it may be temporarily 
placed in a monitored location.  
 
12. (512.)  A conveyance and equipment used regularly for the tr ansport of radioactive or 
fissile material shall be periodically checked to determine the level of 
contamination. The frequency of such checks shall be correspond to the likelihood 
of contamination and the extent to which radioactive or fissile material is  being 
transported.  
 
13. (513.)  A conveyance, part thereof, or equipment that has become contaminated above the 
limits specified in Point  8 during the transport of radioactive or fissile material, or 
that shows a radiation level in excess of 5  Sv/h, shall  be decontaminated by a 
qualified person. They may be reused if:  
a) non-fixed contamination does not exceed the limits specified in Point  8; 
b) the radiation level resulting from fixed contamination does not exceed 5  Sv/h 
on the external surface.  
 
14. (514.)  A freight container, tank, IBC or conveyance dedicated to the transport of 
unpackaged material under exclusive use shall be excepted from the requirements 
for non -fixed contamination on the internal surface of Points  9 and 13 for as long 
as it remains under exclusive use.  
 
 
REQUIREMENTS AND CON TROLS FOR TRANSPORT OF PACKAGE EXCEPTION S 
 
15. (515.)  1. A package exception need only meet requirements of Points  3 to 5, 7 to 13, 16, 
30 to 33, 45, 46 introductory sentence, 46(a), 46(k), 50, 53, 55, 56, 61, 64, 82, a nd 
83; all other relevant requirements of this decree shall be met.  
 
2. If the package exception contains fissile material, one of the conditions in 
Point  17(a) to (f) of Annex  3 to this decree for an exempt fissile material must be 
met. 
 
16. (516.)  The ra diation level at any point on the external surface of a package exception 
shall not exceed 5  Sv/h.  
 
REQUIREMENTS AND CON TROLS FOR TRANSPORT OF LSA MATERIAL AND SCO 
ITEMS IN INDUSTRIAL PACKAGES OR UNPACKAG ED 
  - 58 - 
17. (517.)  The quantity of LSA material or SCO in a single Type IP -1, IP -2, IP -3 package, or 
object or collection of objects, shall be so restricted that the external radiation 
level at 3  m from the unshielded material or object or collection of objects does 
not exceed 10  mSv/h.  
 
18. (518.)  LSA materia l and SCO that are or contain fissile material, that do not meet 
conditions for use in one of the exceptions pursuant to Point  17(a) to (f) of 
Annex  3 to this decree for an exempt fissile material, shall meet the applicable 
requirements of Points  68 and 69 . 
 
19. (519.)  LSA material and SCO that are or contain fissile material shall meet the 
applicable requirements of Point  73. 
 
20. (520.)  LSA material and SCO in groups LSA -I and SCO -I may be transported, 
unpackaged, under the following conditions:  
a) other tha n ores containing only naturally occurring radionuclides, they are 
transported in such a manner that under routine conditions of transport there 
will be no escape of the radioactive contents from the conveyance nor loss of 
shielding;  
b) they conveyance shall be under exclusive use, except when only transporting 
SCO -I on which the contamination on the accessible and the inaccessible 
surfaces is not greater than the limit specified in Point  8; 
c) for SCO -I where it is suspected that non -fixed contamination exists o n 
inaccessible surfaces in excess of the values specified in Point  13(2)(a) of 
Annex  3 to this decree, measures shall be taken to ensure that the radioactive or 
fissile material is not released into the conveyance;  
d) unpackaged fissile material meets the req uirements of Point  17(e) of Annex  3 
to this decree.  
 
21. (521.)  LSA material and SCO, except as otherwise specified in Point  20, shall be 
packaged in accordance with the requirements of Table  1. 
 
Table 1 (5.) Industrial package requirements for LSA and SCO  
Radioactive contents  Industrial package type  
 Transport under exclusive use  Transport not under exclusive 
use 
LSA -I Solid a) 
 Liquid  Type IP -1 
Type IP -1 Type IP -1 
Type IP -2 
LSA -II Solid  
 Liquid and gas  Type IP -2 
Type IP -2 Type IP -2 
Type IP -3 
LSA -III Type IP -2 Type IP -3 
SCO -I a) Type IP -1 Type IP -1 
SCO -II Type IP -2 Type IP -2 
Legend:  
a) Under the conditions specified in Point  20, LSA -I material and SCO -I may be transported unpackaged.  
 
22. (522.)  The total activity in a single hold or compartment of a n inland waterway craft, or 
in another conveyance, for carriage of LSA material or SCO in a Type IP -1, IP -2, 
or IP -3 package or unpackaged, shall not exceed the limits shown in Table  2. 
  - 59 - 
Table  2(6.) Activity limits for LSA and SCO in industrial packages or  transported as 
unpackaged  
Type of material or object  Activity limit for 
conveyances other than 
inland waterway craft  Activity limit for a hold or 
compartment of an inland 
waterway craft  
LSA -I Unlimited  Unlimited  
LSA -II and LSA -III 
non-combustible solids  Unlimited  100 A 2 
LSA -II and LSA -III 
combustible solids  
and all liquids and gases  100 A 2 10 A 2 
SCO  100 A 2 10 A 2 
 
 
DETERMINATION OF THE  TRANSPORT INDEX  
 
23. (523.)  The transport index for a package, freight container, overpack, unpackaged 
material in gro up LSA -I or unpackaged object in group SCO -I is a number 
derived in accordance with the following procedure:  
a) multiply the maximum radiation level in units of millisieverts per hour (mSv/h) 
at a distance of 1  m from the external surfaces of the package, fre ight 
container, overpack, or unpackaged LSA -I or SCO -I by 100. For uranium and 
thorium ores and their concentrates, the maximum radiation level at any point 
1 m from the external surface of the load may alternatively be taken as:  
1. 0.4 mSv/h for ores and phy sical concentrates of uranium and thorium,  
2. 0.3 mSv/h for chemical concentrates of thorium,  
3. 0.02 mSv/h for chemical concentrates of uranium, other than uranium 
hexafluoride;  
b) for tanks, freight containers and unpackaged LSA -I and SCO -I, the value 
determined in step (a) shall be multiplied by the appropriate factor from 
Table  3; 
c) the value obtained in steps (a) and (b) shall be rounded up to the first decimal 
place, except for value of 0.05 or less, which may be considered as zero.  
 
Table  3(7.) Multiplication f actors for large loads  
Load dimensions a) Multiplication factor  
load dimensions ≤ 1 m2 1 
1 m2 < load dimensions ≤ 5 m2 2 
5 m2 < load dimensions ≤ 20 m2 3 
load dimensions > 20  m2 10 
Legend:  
a) Largest cross -sectional area of the load being measured.  
 
24. (524.)  The transport index shall be determined, for:  
a) a non -rigid overpack, as the sum of TIs of packages it contains;  
b) a freight container, overpack, or conveyance, as either the sum of the TIs of all 
the packages it contains, or by direct measurement of  radiation level.   - 60 - 
 
 
DETERMINATION OF THE  CRITICALITY SAFETY I NDEX FOR FREIGHT 
CONTAINERS, OVERPACK S, AND CONSIGNMENTS  
 
25. (525.)  The CSI for a freight container, overpack, consignment, or conveyance shall be 
determined as the sum of the individual CSIs of  all the packages it contains.  
 
 
LIMITS FOR THE TRANS PORT INDEX, CRITICAL ITY SAFETY INDEX, AN D 
RADIATION LEVELS FOR  PACKAGES AND OVERPAC KS 
 
26. (526.)  1. Except for consignments under exclusive use, the TI of any package or 
overpack shall not exceed 10.  
 
2. The CSI of any package or overpack shall not exceed 50.  
 
27. (527.)  The radiation level at any point on the external surface of a package or overpack 
shall not exceed 2  Sv/h. The requirement of the introductory sentence does not 
apply to packages or over packs transported under exclusive use by rail or by road 
in accordance with the conditions specified in Point  73(a), or under exclusive use 
and special arrangement by vessel or by air in accordance with the conditions 
specified in Point  75 or 79.  
 
28. (528 .) The radiation level at any point on the external surface of a package or overpack 
transported under exclusive use shall not exceed 10  Sv/h.  
 
 
CATEGORY  
 
29. (529.)  Packages, freight containers, and overpacks shall be placed in either category I -
WHITE, II -YELLOW, or III -YELLOW pursuant to requirements specified in 
Table  4 and pursuant to the requirements of (a) to (d):  
a) if the TI satisfies the condition for one category but the surface radiation level 
satisfies the condition for a different category, the pa ckage, freight container, 
or overpack shall be assigned to the higher category; category I -WHITE is 
regarded as the lowest category;  
b) the TI shall be determined via the procedures specified in Points  23 and 24;  
c) except for Point  30, a package transported und er special arrangement is placed 
in category III -YELLOW;  
d) except for Point  30, an overpack containing packages transported under special 
arrangement is placed in category III -YELLOW.  
 
Table  4 (8.) Categories of packages and overpacks  
Conditions   
Transport index  Maximum radiation level at any point on the external 
surface  Category  
0 a) at most 0.0005 mSv/h  I-WHITE  
more than 0, but not 
more than 1 a) more than 0.005 mSv/h, but not more than 0.5  mSv/h  II-YELLOW   - 61 - 
more than 1, but not 
more than 10  more than 0 .5 mSv/h, but not more than 2  mSv/h  III-YELLOW  
more than 10  more than 2  mSv/h, but not more than 10  mSv/h  III-YELLOW 
b) 
Legend:  
a) If the measured TI is not greater than 0.05, the TI value may be considered to be zero in accordance with 
Point  23(c).  
b) Shall also be transported under exclusive use except for freight containers, see Table  6. 
 
 
MARKING, LABELLING, AND PLACARDING  
 
30. (530.)  1. A package or overpack shall be assigned a UN number and named pursuant to 
Table  1 of Annex  3 to this decree.  
 
2. In cases of international transport of packages requiring competent authority 
approval of design or shipment, for which packaging type approval or transport 
authorisation by relevant authorities of countries the shipment concerns, the UN 
number, proper shipp ing name, categori sation, labelling and marking shall be in 
accordance with the decision of the relevant authority of the country of origin of 
design.  
 
Labelling  
31. (531.)  1. A package shall be legibly and durably marked on the outside of the packaging 
with an identification of either the consignor or consignee, or both.  
 
2. If the markings of all the packages within the overpack are not clearly visible, 
the outside of the overpack shall be legibly and durably marked with an 
identification of either the co nsignor or consignee, or both.  
 
32. (532.)  1. A package shall be legibly and durably marked on the outside with the UN 
marking as specified in Table  5. 
 
2. If the markings of all the packages within the overpack are not clearly visible, 
the overpack shall be legibly and durably marked with the word ‘OVERPACK ’ 
and the UN marking as specified in Table  5. 
 
Table  5(9.) UN markings for packages and overpacks  
Item UN marking a) 
Package  
(other than a package exception)  UN number, preceded by the letters 'UN',  and 
its proper shipping name  
Package exception  UN number, preceded by the letters ‘UN’ 
Overpack (other than an overpack 
containing only package exceptions)  UN number, preceded by the letters ‘UN’ for 
each applicable UN number in the overpack, 
followed by t he proper shipping name in the 
case of a non -excepted package  
Overpack containing only package 
exceptions  UN number, preceded by the letters ‘UN’ for 
each applicable UN number in the overpack  
Legend:  
a)for a list of UN numbers and proper shipping names,  see Table  1 of Annex  3 to this decree   - 62 - 
 
33. (533.)  A package of gross mass exceeding 50  kg shall have its permissible gross mass 
legibly and durably marked on the external surface.  
 
34. (534.)  A package that conforms to:  
a) an IP -1, IP -2, or IP -3 design shall  be legibly and durably marked on the outside 
of the packaging with ‘TYPE IP -1’, ‘TYPE IP -2’ or ‘TYPE IP -3’, as 
appropriate;  
b) a Type A package design shall be legibly and durably marked on the outside of 
the packaging with ‘TYPE A ’; 
c) an IP -2, IP -3, or a Type  A package design shall be legibly and durably marked 
on the outside of the packaging with the international vehicle registration code 
(VRI code) of the country of origin of design and either the name of the 
manufacturer or identification of the packaging specified by the Office.  
 
35. (535.)  The packaging manufactured pursuant to a type approval decision shall be legibly 
and durably marked with the following on the outside surface:  
a) the type identification mark in accordance with a type approval decision iss ued 
by the Office;  
b) a serial number to uniquely identify each packaging of approved type;  
c) for Type B(U), B(M), or C packages, ‘TYPE B(U) ’, ‘TYPE B(M) ’, or ‘TYPE 
C’, as applicable.  
 
36. (536.)  A package that conforms to a Type B(U), Type B(M), or Type C desi gn shall have 
the outside of its packaging marked by embossing, stamping or other means 
resistant to the effects of fire and water with the trefoil symbol. Table  1 contains 
an example of the trefoil symbol.  
 
37. (537.)  LSA -I material or an SCO -I object tha t is contained in receptacles or wrapping 
materials and is transported under exclusive use pursuant to Point  20 shall be 
marked on the outer surface of these receptacles or wrapping materials with 
‘RADIOACTIVE LSA -I’ or ‘RADIOACTIVE SCO -I’, as appropriate.  
 
 
  - 63 - 
Figure  1 (1.) Basic trefoil symbol with proportions based on a central circle of radius X. The 
minimum permitted size of X is 4  mm. 
 
Labelling  
38. (538.)  1. Except for Point  43, a package, overpack, and freight container shall bear 
labels conforming t o the models in:  
a) Figure  2 for the category I -WHITE;  
b) Figure  3 for the category II -YELLOW;  
c) Figure  4 for the category III -YELLOW.  
 
2. Except for an exempt fissile material pursuant to Point  17 of Annex  3 to this 
decree, a package, overpack, and freight contai ner containing fissile material shall 
also bear labels conforming to the model in Figure  5. 
 
3. Other labels that do not relate to the contents shall be removed or covered.  
 
39. (539.)  1. Labels conforming to the models in Figures  2, 3 or 4 shall be affixe d to two 
opposite sides of the outside of a package or overpack or on the outside of all four 
sides of a freight container or tank.  
 
2. The label conforming to the model in Figure  5 shall be affixed adjacent to the 
labels specified in (1).  
 
3. The labels s hall not cover the markings specified in Points  31 to 36.  
 
  - 64 - 
 
 
Figure  2(2.) Category I -WHITE label. The background colour of the label shall be white, the 
colour of the trefoil and the printing shall be black, and the colour of the category bar shall be 
red. [TRANSLATION NOT REQ UIRED]  
 
 
Labelling for radioactive contents  
40. (540.)  Each label conforming to the models in Figures  2, 3 and 4 shall be completed with 
the following information on  
a) content:  
1. except for LSA -I material, the names of the radionuclides pursuant to 
Table  2 of Annex  3 to this decree, using the symbols prescribed therein. 
For mixtures of radionuclides, the most restrictive nuclides must be 
listed to the extent the space on the line permits. For materials in an 
LSA group or objects in an SCO  group, the names of the radionuclides 
shall be followed by ‘LSA -II’, ‘LSA -III’, ‘SCO -I’, or ‘SCO -II’ as 
applicable.  
2. For LSA -I material, the term ‘LSA -I’ shall be filled in.  
b) activity: the maximum activity of the radioactive contents during transport 
expres sed in units of becquerels (Bq) with the appropriate SI prefix symbol. 
For fissile material, the total mass of fissile nuclides in units of grams (g), or 
multiples thereof, may be used in place of activity. For an overpack or freight 
container, the ‘conten ts’ and ‘activity ’ entries on the label shall bear the  - 65 - 
information in accordance with Letter  (a) and (b). Labels for an overpack or 
freight container containing a mixed load of packages containing different 
radionuclides, entries in the content and activit y rows may read: ‘See Transport 
Documents ’; 
c) transport index: the number determined in accordance with Points  23 and 24; 
no TI entry is required for category I -WHITE.  
 
Labelling for criticality safety  
41. (541.)  Each label conforming to the model in Figure  5 shall be completed with the  CSI 
as stated in the transport authorisation or packaging type approval decision issued 
by the Office, in a decision issued by relevant authorities of the country of origin 
of the packaging or the country of origin of carriage  in the case of international 
carriage, or in accordance with the requirements of Point  74 or 75 of Part  I to 
Annex  1 to this decree.  
 
42. (542.)  For an overpack or freight container, the label conforming to the model in 
Figure  5 shall bear the sum of the CSIs of all the packages contained therein.  
 
Placarding  
43. (543.)  A large freight container carrying packages other than package exceptions, and a 
tank shall bear placards that conform to the model given in Figure  6. The placards 
shall be affixed in a ver tical orientation to the front, each side wall, and to the rear 
wall of the large freight container or tank. Other labels that do not relate to the 
contents shall be removed. Instead of using both labels and placards, it is possible 
to use only enlarged la bels as shown in Figures  2, 3, 4, or 5, enlarged so they have 
the minimum dimensions as specified in the model in Figure  6.  - 66 - 
 
 
Figure  3(3.) Category II -YELLOW label. The background colour of the upper half of the 
label shall be yellow and the lower half wh ite, the colour of the trefoil and the printing shall 
be black, and the colour of the category bars shall be red. [TRANSLATION  NOT 
REQUIRED]  
 
 
44. (544.)  1. Where a consignment of unpackaged LSA -I or SCO -I being shipped in a 
freight container or tank is or  a consignment of packaged radioactive material 
being shipped under exclusive use can be marked with a single UN number, the 
UN number for the consignment shall be displayed in black digits not less than 
65 mm high:  
a) in the lower half of the placard shown i n Figure  6 on a white background; or  
b) on a placard pursuant to the model shown in Figure  7. 
 
2. When marking pursuant to (1)(b), the subsidiary placard pursuant to the model 
in Figure  7 shall be affixed immediately adjacent to the main placard pursuant to 
the model in Figure  6 on all four sides of the freight container or tank.  
 
  - 67 - 
 
 
Figure  4(4.) Category II -YELLOW label. The background colour of the upper half of the 
label shall be yellow and the lower half white, the colour of the trefoil and the printing s hall 
be black, and the colour of the category bars shall be red.  
 
 
THE CARRIER'S RESPON SIBILITIES  
 
45. (545.)  Unless otherwise specified in this decree, no radioactive or fissile material shall be 
provided for transport unless it is properly marked, labell ed, placarded, described 
in transport documents, includes a declaration of the carrier or confirmation of 
freight container or conveyance loading, as applicable, and is in every aspect 
suitable for transport.  
  - 68 - 
 
 
Figure  5(5.) Criticality safety index label . The background colour of the label shall be white, 
the colour of the printing shall be black.  
 
 
Particulars of consignment description in the carriage document  
46. (546.)  1. In the transport documents accompanying a consignment, the carrier shall 
include  identification of the consignor and consignee, in the case of a natural 
person their name(s), surname, and addresses, and in the case of a corporate entity 
its name and registered address, and the relevant information in the following 
order:  
a) the UN number  assigned to the radioactive or fissile material, preceded by the 
letters ‘UN’; 
b) the proper shipping name assigned to the radioactive or fissile material;  
c) UN class number ‘7’; 
d) subsidiary hazard class numbers corresponding to the label numbers required if 
the radioactive or fissile material is also classified in other classes or subclasses 
of dangerous goods; the subsidiary hazard class numbers shall follow the 
primary hazard class number in brackets;  
e) the name or symbol of each radionuclide or, for mixtures o f radionuclides, an 
appropriate general description or a list of the most restrictive nuclides;  
f) a description of the physical and chemical form of the radioactive or fissile 
material, or information that the material is special form radioactive material or   - 69 - 
low dispersible radioactive material; the chemical form may be stated as a 
chemical formula;  
g) the maximum activity of the radioactive contents during transport expressed in 
units of becquerels (Bq) with the appropriate SI prefix symbol. In place of 
activit y, the following may be provided:  
1. for fissile material, total mass in grams (g) or multiples thereof;  
2. for a mixture of fissile radionuclides, the mass of each fissile nuclide 
present in grams (g) or multiples thereof;  
h) the category of the package, i.e. I -whiteE, II-yellow , or III-yellow;  
i) the transport index for categories II-YELLOW and III-YELLOW ; 
j) for fissile material:  
1. shipped under one of the exceptions in Point  17(a) to (f) of Annex  3 to 
this decree, a reference to this provision;  
2. shipped under one of the exceptions in Point  17(c) to (e) of Annex  3 to 
this decree, the total mass of fissile radionuclides;  
3. shipped in a package with the use of one of the provisions of 
Point  74(a) to (c) of Annex  1 to this decree, a reference to this 
provision;  
4. the criticality safety index;  
k) the identification mark of a type approval or transport authorisation decision 
issued by the Office, and in the case of international transport, also the 
identification mark of authorisation of relevant authorities of countries the 
transport concerns, required for the consignment;  
l) for a consignment shipped under exclusive use, the statement '‘EXCLUSIVE 
USE SHIPMENT ’; 
m) for a consignment of LSA -II, LSA -III, SCO -I and SCO -II, the total activity of 
the consignment as a multiple of A 2; for a consign ment of radioactive or fissile 
material for which the A 2 value is unlimited, the multiple of A 2 is equal to zero.  
 
2. For a consignment of more than one package, the information pursuant to 
(1)(a) to (k) shall be given for each package. For packages in an overpack, freight 
container, or conveyance, a detailed statement of the contents of each package 
within the overpack, freight container, or conveyance and, where appropriate, of 
each overpack, freight container, or conveyance shall be included. If individu al 
packages are to be removed from the overpack, freight container, or conveyance 
at a point of intermediate unloading, appropriate transport documents for these 
packages shall be made available.  
  - 70 - 
 
Figure  6(6.) Placard. Except for Point  71, minimum dimens ions shall be as shown; when 
different dimensions are used, the relative proportions shall be maintained. The numeral ‘7’ 
shall not be less than 25  mm high. The background colour of the upper half of the label shall 
be yellow and the lower half white, the colour of the trefoil and the printing shall be black. 
The use of the word ‘RADIOACTIVE ’ in the bottom half is optional, to allow the alternative 
use of this placard to display the appropriate UN number for the consignment.  
 
 
  - 71 - 
Figure  7(7.) Placard for sep arate display of UN number. The background colour of the placard 
shall be orange and the border and UN number shall be black. The symbol ‘’ denotes 
the space in which the appropriate UN number for radioactive material be displayed, as 
specified in Tabl e 1 of Annex  3 to this decree.  
 
 
Consignor ’s declaration  
47. (547.)  The consignor shall include in the transport documents a certification or 
declaration in the following terms: ‘I hereby declare that the contents of this 
consignment are fully and accurate ly described above by the proper shipping 
name and are classified, packaged, marked and labelled/placarded, and are in all 
respects in proper condition for transport in accordance with the applicable 
international and national governmental regulations. ’ 
 
48. (548.)  The consignor need not provide a declaration pursuant to Point  47 for that part of 
the transport covered by the obligation to provide a declaration with similar 
content stipulated by an international convention by which the Czech Republic is 
boun d. 
 
49. (549.)  The declaration pursuant to Point  47 shall be signed and dated by the consignor.  
 
50. (550.)  Documentation for the transport of dangerous goods may be provided to the 
carrier in writing, or with his/her approval, electronically.  
 
51. (551.)  During marine transport of radioactive or fissile material placed or loaded into a 
freight container or on a vehicle, those responsible for loading the container or 
vehicle shall provide a container/vehicle packing certificate specifying the 
container/vehi cle identification number and certifying that the operation has been 
carried out in accordance with international requirements.  
 
52. (552.)  The information required in the transport documents and the container/vehicle 
packing certificate may be incorporate d into a single document or attached one to 
each other. If the information is incorporated into a single document, the 
document shall include a signed declaration stating:  
‘I hereby declare that the packing and loading of radioactive or fissile material 
into the container/vehicle has been carried out in accordance with the applicable 
provisions. ’ 
 
53. (553.)  The declaration pursuant to Point  52 shall be dated and the person signing it shall 
be identified in the document. The declaration shall be made on the  transport 
document that contains the information specified in Point  46. 
 
Information for carriers  
54. (554.)  The consignor shall provide in the transport documents instructions regarding 
actions that must be taken by the carrier. The instructions shall be  in the languages 
required by the carrier, the Office, and in the case of international transport, also 
the appropriate authorities of the countries the transport concerns. The instructions 
include at least the following:  
a) supplementary requirements for loa ding, stowage, carriage, handling, and 
unloading of the package, overpack, or freight container, including any special  - 72 - 
stowage provisions for the safe dissipation of heat, or instructions that no such 
requirements are necessary;  
b) information regarding restr ictions on the mode of transport or conveyance and 
any necessary routing instructions;  
c) instructions regarding emergency arrangements for the given consignment.  
 
55. (555.)  The consignor shall retain a copy of each of the transport documents containing 
the information specified in Points  46, 47, 51, 52 and 54 for at least three months. 
When the documents are kept electronically, the consignor shall be able to 
reproduce them in printed form.  
 
56. (556.)  The type approval decision and transport authorisation n eed not accompany the 
consignment. However, the consignor shall make them available to the carrier(s) 
before loading and unloading.  
 
Notification of administrative authorities  
57. (557.)  Before the first shipment of any package requiring type approval or a uthorisation 
for transport, the consignor shall ensure that copies of type approval or 
authorisation for transport documents have been submitted to the competent 
authorities of countries that the transport concerns.  
 
58. (558.)  1. The consignor shall notif y the Office, and in the case of international transport, 
also competent authorities of countries that the transport concerns, regarding 
transport:  
a) of Type C packages containing radioactive or fissile material with activity 
greater than 3.103 A1 or 3.103 A2 or 1 000 TBq, whichever is less;  
b) of Type B(U) packages containing radioactive or fissile material with activity 
greater than 3.103 A1 or 3.103 A2 or 1 000 TBq, whichever is less;  
c) of type B(M) packages;  
d) under special arrangement.  
 
2. The Office and other competent authorities must receive notification pursuant 
to (1) at least 7 days prior to the start of transport.  
 
59. (559.)  The consignment notification shall include:  
a) information enabling the identification of the package or packages, including 
all ident ification marks in accordance with a type approval decision issued by 
the Office, and in the case of international transport, also identification marks 
of authorisation of competent authorities of countries that the transport 
concerns;  
b) information on the d ate of shipment, the expected date of arrival, and the 
proposed route;  
c) the names of the radioactive or fissile material or radionuclides;  
d) a description of the physical and chemical form of the radioactive or fissile 
material, or information that the materi al is special form radioactive material or 
low dispersible radioactive material;  
e) information regarding the maximum activity of the radioactive contents during 
transport expressed in units of becquerels (Bq) with the appropriate SI prefix 
symbol. In place o f activity, the following may be provided:  
1. for fissile material, total mass in grams (g) or multiples thereof;   - 73 - 
2. for a mixture of fissile radionuclides, the mass of each fissile nuclide 
present in grams (g) or multiples thereof;  
 
60. (560.)  The consignor is not required to send a separate notification pursuant to Points  58 
and 59 if the required information has been included in the transport approval 
application.  
 
Documents and operating rules the consignor must have available  
61. (561.)  The consignor shall h ave available a copy of a decision of the decision of the 
Office regarding transport, and in the case of international transport, also a copy 
of decisions of competent authorities of countries that the transport concerns, a 
copy of the instructions with re gard to the proper closing of the package, and 
preparations for shipment, before making any shipment.  
 
 
TRANSPORT AND STORAG E IN TRANSIT  
 
Segregation during transport and storage in transit  
62. (562.)  A package, overpack, or freight containers containing r adioactive or fissile 
material and unpackaged material shall be segregated during transport and during 
storage in transit from:  
a) workers in regularly occupied working areas by distances calculated using a 
maximum permissible effective dose criterion of 5  mSv in a year and 
conservative model parameters;  
b) members of the public in areas where the public has regular access by distances 
calculated using a maximum permissible effective dose criterion of 1  mSv in a 
year and conservative model parameters;  
c) undeveloped  photographic film by distances calculated using a maximum dose 
criterion of 0.1  mGy due to the transport of one consignment of radioactive or 
fissile material on this film;  
d) other dangerous goods in accordance with Point  6. 
 
63. (563.)  Category II -YELLOW o r III -YELLOW packages or overpacks shall not be 
carried in compartments occupied by passengers, except those exclusively 
reserved for couriers specially authorised to accompany such packages or 
overpacks.  
 
Stowage on or in the conveyance during transport a nd storage in transit  
64. (564.)  During transport and storage, the consignment shall be securely stowed so that it 
cannot move, turn over, or fall.  
 
65. (565.)  1. A package or overpack may be carried or stored among other packaged cargo 
without any special  stowage provisions, if:  
a) its average surface heat flux does not exceed 15  W/m2, and  
b) the immediate surrounding cargo is packaged in a manner other than sacks or 
bags.  
 
2. The provisions of (1) shall not be applied if the Office, and in the case of 
internati onal transport, also competent authorities of states that the transport 
concerns, specifies or specify otherwise in a type approval decision.   - 74 - 
 
66. (566.)  For the loading of freight containers and accumulation of packages, overpacks, 
and freight containers,  the following applies:  
a) except under the condition of exclusive use, and for consignments of LSA -I 
material, the total number of packages, overpacks, and freight containers on or 
in a single conveyance shall not exceed the values shown in Table  6; 
b) the radi ation level under routine conditions of transport shall not exceed 
2 mSv/h at any point on, and 0.1  mSv/h at 2  m from, the external surface of the 
conveyance; for consignments transported under exclusive use by road or rail 
radiation limits around the vehi cle are stipulated in Points  73(b) and (c);  
c) the sum of the CSIs in a freight container and on or in a conveyance shall not 
exceed the values shown in Table  7. 
 
Table  6 (10.) TI limits for freight containers and conveyances not under exclusive use  
 
Type of freight container or conveyance  Limit on total sum of 
transport ind ices in a 
freight container or 
aboard a conveyance  
Freight container  small  
 Large  50 
50 
Vehicle  50 
Aircraft  passenger  
 Cargo  50 
200 
Inland waterway vessel  50 
Seagoing vessel a) 
(1) Hold, compartment, or defined deck area:  
 packages, overpacks, or small freight containers  
 large freight containers  
(2) Total vessel:  
 packages, overpacks, or small freight containers  
 large freight containers   
 
 
50 
200 
 
200 
unlimited  
Legend:  
a) Packages or  overpacks on vehicles that meet the requirements of Point  73 of Annex  4 to this decree may be 
transported by vessels provided that they are not removed from the vehicle at any time while it is on board the 
vessel.  
 
67. (567.)  Packages or overpacks with a transport index greater than 10 and consignments 
with a criticality safety index greater than 50 shall be transported only under 
exclusive use.  
 
Additional transport and storage requirements during transport of fissile material  
 
68. (568.)  The number total  sum of the criticality safety ind ices in a group of packages, 
overpacks, or freight containers containing fissile material stored in transit shall 
not exceed 50 in a storage area. The distance between individual groups pursuant 
to the first sentence shall  be at least 6  m. 
 
Table  7(11.) CSI limits for freight containers and conveyances containing fissile material   - 75 - 
 
 
 
Type of freight container or conveyance  Limit on total sum of 
criticality safety ind ices in a 
freight container or aboard a 
conveyance  
 Other 
transport  Transport 
under 
exclusive use  
Freight container  small  
 Large  50 
50 – 
100 
Vehicle  50 100 
Aircraft  passenger  
 Cargo  50 
50 – 
100 
Inland waterway vessel  50 100 
Seagoing vessel a): 
(1) Hold, compartment, or defined deck area  
 packages, overpacks,  or small freight containers  
 large freight containers  
(2) Total seagoing vessel  
 packages, overpacks, or small freight containers  
 large freight containers   
 
50 
50 
 
200 b) 
unlimited b)  
 
100 
100 
 
200 c) 
unlimited c) 
Legend:  
a) Packages or overpacks on a vehicle that meets the requirements of Point  73, may be transported by vessel 
provided that they are not removed from the vehicle at any time while on board the vessel. In this case the entries 
under the heading ‘Under exclusive use ’ apply.  
b) The consignm ent shall be so handled and stowed that the total sum of CSIs in any group does not exceed 50, 
and that each group is handled and stowed so that the groups are separated from each other by at least 6  m. 
c) The consignment shall be so handled and stowed tha t the total sum of CSIs in any group does not exceed 100, 
and that each group is handled and stowed so that the groups are separated from each other by at least 6  m. The 
intervening space between groups may be occupied by other cargo in accordance with Poi nt 6. 
 
69. (569.)  Where the total sum of the criticality safety ind ices on board a conveyance or in a 
freight container exceeds 50, storage shall be such as to maintain a spacing of at 
least 6  m from other groups of packages, overpacks, or freight containe rs 
containing fissile material or other conveyances carrying radioactive material.  
 
70. (570.)  Additional requirements relating to transport of fissile material classified pursuant 
to one of Point  17(a) to (f) of Annex  3 to this decree are as follows:  
a) for a consignment, one in Point  17(a) to (f) of Annex  3 to this decree may be 
used;  
b) a consignment may carry only one exempted fissile material in packages 
pursuant to Point  17(f) of Annex  3 to this decree, unless specified otherwise by 
the Office, and in the c ase of international transport, also competent authorities 
of countries that the transport concerns, in the authorisation for transport;  
c) exempted fissile material in packages pursuant to Point  17(c) of Annex  3 to this 
decree shall be transported in a consi gnment containing at most 45  g of fissile 
radionuclides;  
d) exempted fissile material in packages pursuant to Point  17(d) of Annex  3 to 
this decree shall be transported in a consignment containing at most 15  g of 
fissile radionuclides;   - 76 - 
e) unpackaged and packaged  exempted fissile material in packages pursuant to 
Point  17(e) of Annex  3 to this decree shall be transported in a consignment 
containing at most 45  g of fissile radionuclides, and must be transported under 
exclusive use.  
 
Additional requirements relating to transport by rail and road  
71. (571.)  1. Rail and road vehicles carrying packages, overpacks, or freight containers 
labelled with any of the labels shown in Figure  2, 3, 4 or 5 or carrying 
consignments under exclusive use, shall display the placards sho wn in Figure  6: 
a) on the two external lateral walls in the case of a rail vehicle;  
b) on the two external lateral walls and the rear wall in the case of a road vehicle.  
 
2. In the case of a vehicle without sides, the placards may be affixed directly on 
the chas sis carrying the cargo provided that they are readily visible; in the case of 
large -volume tanks or freight containers, the placards shall be placed only on 
them. In the case of vehicles which have insufficient area to allow the fixing of 
larger placards w ith dimensions as described in Figure  6, the dimensions the sides 
of the placard may by reduced to 100  mm. Other labels that do not relate to the 
radioactive contents of the vehicle shall be removed.  
 
72. (572)  1. Where a consignment of unpackaged LSA -I or SCO -I being on or in a vehicle 
or a consignment of packaged radioactive or fissile material being shipped under 
exclusive use on or in a vehicle can be marked with a single UN number, the UN 
number for the consignment shall be displayed in black digits no t less than 65  mm 
high:  
a) on a white background in the lower half of the placard shown in Figure  6; or 
b) on a placard pursuant to the model shown in Figure  7. 
 
2. When marking pursuant to (1)(b), the placard pursuant to the model in Figure  7 
shall be affixed i mmediately adjacent to the main placard pursuant to the model in 
Figure  6 on the two external lateral walls in the case of a rail vehicle, or on the 
two external lateral walls and the rear wall in the case of a road vehicle.  
 
73. (573.)  For consignments un der exclusive use, the radiation level shall not exceed:  
a) 10 mSv/h at any point on the external surface of any package or overpack; the 
radiation level shall however not exceed 2  mSv/h in the following situations:  
1. the vehicle is not equipped with an enclosu re that during routine 
conditions of transport prevents unauthori sed persons from accessing 
the interior of the enclosure;  
2. provisions are not made to secure the package or overpack so that its 
position within the vehicle remains fixed during routine condit ions of 
transport;  
3. there is loading or unloading during the shipment;  
b) 2 mSv/h at any point:  
1. on the outer surfaces of an enclosed vehicle, including roof and floor 
areas;  
2. on a vertical plane projected from the outer edge of an enclosed vehicle, 
the surface of the load, and the lower external surface of the vehicle;  
c) 0.1 mSv/h at any point 2  m from:  
1. the external surface of a vertical plane of an enclosed vehicle;   - 77 - 
2. the vertical plane that intersects the external edge of an open vehicle.  
 
74. (574.)  In the case o f road vehicles, no persons other than the driver and assistants shall 
be permitted in vehicles carrying packages, overpacks, or freight containers 
bearing category II -YELLOW or III -YELLOW labels.  
 
Additional requirements relating to transport by vessels  
75. (575.)  Packages or overpacks having a surface radiation level greater than 2  mSv/h shall 
not be transported by vessel. The provision of the first sentence does not apply to 
packages or overpacks:  
a) transported under exclusive use in accordance with Table  6, column ‘Transport 
under exclusive use ’ or on a vehicle that meets the requirements of Point  73, 
provided that they are not unloaded from the vehicle during its presence on 
board the vessel;  
b) transported under special arrangement.  
 
76. (576.)  The transpor t of consignments by means of a special use vessel is exempt from 
the requirements specified in Point  66 if:  
a) a radiation protection programme for the shipment has been drawn up and has 
been approved by the Office or a competent authority of the flag state of the 
vessel, if the operator of the special use vessel is a foreign entity, and also, if 
requested, by the competent authority at each port of call;  
b) stowage arrangements shall be predetermined for the entire route including any 
consignments to be loaded at ports of call en route;  
c) the loading, carriage and unloading of the consignments shall be supervised by 
persons qualified in the transport of radioactive and fissile material.  
 
Additional requirements relating to air transport  
77. (577.)  Type B(M) packag es and consignments under exclusive use shall not be 
transported on passenger aircraft.  
 
78. (578.)  Vented Type B(M) packages, packages that require external cooling by an 
auxiliary cooling system, packages subject to operational controls during 
transport,  and packages containing liquid pyrophoric material shall not be 
transported by air.  
 
79. (579.)  Packages or overpacks having a surface radiation level greater than 2  mSv/h shall 
not be transported by aircraft. The provision of the first sentence does not apply to 
packages or overpacks transported under special arrangements.  
 
Transport by post  
80. (580.)  The transport of radioactive or fissile material via post is prohibited in the Czech 
Republic.  
 
 
OTHER REQUIREMENTS  
 
81. (582.)  Customs inspection of the r adioactive contents of a package shall be performed in 
a location with facilities required to limit and monitor radiation exposure, and in 
the presence of qualified individuals.   - 78 - 
 
82. (582.)  A package opened upon the instructions of the Customs Office must be returned 
to its original condition prior to being handed over for further transport.  
 
83. (583.)  A package that cannot be delivered must be placed in a safe location. The Office 
must be informed of this fact immediately.  
 
 
CARRIAGE DOCUMENTS K EPT BY AND  AVAILABLE FROM THE C ARRIER  
 
84. (584.)  A carrier shall not accept a consignment for transport unless copies of the 
transport documents, other documents, or information have been handed over, or 
provided electronically.  
 
85. (585.)  The information applicab le to the consignment shall accompany the consignment 
to final destination and must be given to the consignee upon delivery.  
 
86. (586.)  Information applicable to the consignment given to the carrier in electronic form 
shall be available to the carrier at all times during transport to the final destination, 
and it must be possible to print out a paper version at any time.  
 
87. (587.)  The carrier shall retain a copy of the transport document and additional 
information and documentation pursuant to this decre e for at least three months.  
 
88. (588.)  When the documents pursuant to this decree are kept electronically, the consignor 
shall be able to reproduce them in printed form.   - 79 - 
 
Annex  5 to Decree  No …………  
 
Standardní dokument (Rozhodnutí Komise 2008/312/Euratom ) 
 
 
Obecné poznámky  
 
Části A -1 až A -6 se vyplňují u přepravy radioaktivního odpadu.  
Části B -1 až B -6 se vyplňují u přepravy vyhořelého paliva (včetně vyhořelého paliva 
určeného ke konečnému uložení, které je proto klasifikováno jako odpad).  
 
Část A -1 nebo B -1 (žádost o povolen í k přepravě): vyplňuje žadatel, kterým je podle typu 
přepravy  
— držitel v případě přepravy mezi členskými státy (typ MM) nebo vývozu ze Společenství 
do třetí země (typ ME),  
— příjemce v případě dovozu do Společenství ze třetí země (typ IM),  
— osoba odpově dná za přepravu v členském státě, kterým radioaktivní odpad nebo vyhořelé 
palivo vstupuje do Společenství v případě tranzitu Společenstvím (typ TT).  
 
Část A -2 nebo B -2 (potvrzení o přijetí žádosti): vyplní dotčené příslušné orgány, kterými 
podle typu přepr avy jsou příslušné orgány  
— země původu v případě přepravy typu MM nebo ME,  
— země určení v případě přepravy typu IM,  
— země, kde zásilka poprvé vstupuje do Společenství, v případě přepravy typu TT a všechny 
příslušné orgány případných členských států tran zitu. 
 
Část A -3 nebo B -3 (zamítnutí nebo souhlas): vyplní všechny dotčené příslušné orgány.  
 
Část A -4a/A -4b nebo B -4a/B -4b (povolení nebo zamítnutí přepravy): vyplní příslušný orgán 
odpovědný za vydání povolení, kterým je podle typu přepravy příslušný orgá n 
— země původu v případě přepravy typu MM a ME,  
— členského státu určení v případě přepravy typu IM nebo  
— prvního členského státu, kde zásilka vstupuje do Společenství, v případě přepravy typu 
TT. 
 
Část A -5 nebo B -5 (popis zásilky/seznam obalů): vyplňuje  žadatel uvedený v části A -1 nebo 
B-1. 
 
Část A -6 nebo B -6 (potvrzení příjmu zásilky): vyplní příjemce (u přepravy typu MM a IM) 
nebo držitel (u přepravy typu ME) nebo osoba odpovědná za přepravu (u přepravy typu TT).  
32008D0312  
  - 80 - 
 
Registrační číslo:   
(vyplní příslušný orgán odpovědný za vydáni 
povolení k přepravě)  
ČÁST A -1 
Žádost o povoleni k přepravě radioaktivního odpadu  
1. Typ přepravy (zaškrtněte příslušné okénko):  
 Typ MM: přeprava mezi členskými státy (přes jeden nebo více členských států nebo třetích  zemí)  
 Typ IM: dovoz do Společenství  
 Typ ME: vývoz ze Společenství  
 Typ TT: tranzit přes území Společenství  
2. Žádost o povolení pro (zaškrtněte příslušné okénko):  
 jednorázovou přepravu ___________________ Plánované období provedení: ______________________ _ 
 opakovanou přepravu: počet (plánovaný): ____________ Plánované období provedení: _______________  
3.  Nepoužije se.  
 Přeprava typu MM pres jednu nebo více třetích zemí:  
Výstupní hraniční přechod Společenství (*):  ________________________________ ____________________   
Vstupní hraniční přechod třetí země (*) ( první tranzitní země):  ________________________________ ______   
Výstupní hraniční přechod třeli země (*) (poslední tranzitní země):  ________________________________ __  
Hraniční přechod při zpětném dovozu do Společenství (*):  ________________________________ ________   
(*) Uvedené přechody musí být stejné pro veškerou přepravu uvedenou v žádosti, pokud to příslušné orgá ny nepovolí jinak.  
4. Žadatel (obchodní název):  ________________________________ ________________________________ _  
 Držitel (pro typy MM, ME)  
 Příjemce (pro typ IM)  
 Jiný (pro typ TT), upřesněte:  ________________________________ ____________________________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: __________________ Země: _____________________  
Tel.: ____________ ____________ Fax: _____________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
5. Uložení radioaktivního odpadu před přepravou (obchodní název):  ________________________________ ___  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: __________________ Země : _____________________  
Tel.: _______________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
6. Příjemce (obchodní název):  ________________________________ ________________________________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ _ Země: _____________________  
Tel.: _______________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
7. Uložení radioaktivního odpadu po přepravě (obchodní název):  ________________________________ _____   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: __ ______________ Město: __________________ Země: _____________________  
Tel.: _______________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
  - 81 - 
8. Charakteristika radioaktivního odpadu:  ________________________________ ________________________   
Fyzikálně -chemické vlastnosti (zaškrtněte příslušné okénko):  
 pevný,  kapalný,  plynný,  jiný (např. štěpný, s malou rozptýlitelností ...), upřesněte:  ______________   
Hlavní radionuklidy:  ________________________________ ________________________________ _______   
Maximální aktivita záření alfa na zásilku (GBq): ___________________ na obal (GBq): ___________ ________  
Maximální aktivita záření beta/aama na zásilku (GBq): _________________ na obal (GBq): _______________  
Celková aktivita záření alfa (GBq):  ________________________________ ___________________________   
Celková aktivita záření beta/gama (GBq):  ________________________________ ______________________   
(Tyto hodnoty představuji odhady, pokud se žádost týká opakovan é přepravy.)  
9. Celkový počet obalů:  ________________________________ ________________________________ ______   
Celková čistá hmotnost zásilky (kg):  ________________________________ __________________________   
Celková hrubá hmotnost zásilky (kg):  ________________________________ _________________________   
(Tyto hodnoty představují odhady, pokud se žádost týká opakované přepravy.)  
Popis zásilky:  
 igelitové pytle.  kovové sudy (m3): ________ _______,  přepravní kontejner ISO (m3): _______________,  
 jiné, upřesněte  ______________   
Druh obalů (1) (je-li znám):  ________________________________ ________________________________ __  
Způsob označeni jednotlivých obalů (při označování štítky uveďte příklad)  ____________________________   
(1) Podle Pravidel pro bezpečnou přepravu radioaktivních materiálů ve v ydání z roku 2005. bezpečnostní požadavky TS -R-1, 
IAEA. Vídeň, 2005.  
10. Druh činnosti, při níž vznikl radioaktivní odpad (zaškrtněte příslušné okénko):  
 lékařství,  výzkum,  (nejaderný) průmysl,  jaderný průmysl,  
 jiná činnost (upřesněte):  ________________________________ ________________________________ _  
11 Účel přepravy:  
 vráceni radioaktivního odpadu po zpracování nebo přepracování vyhořelého paliva  
 vrácení radioaktivního odpadu po zpracování radioaktivního odpadu  
 zpracování, např. obal, přebalení, úprava, snížení objemu  
 dočasné skladování  
 vrácení po dočasném s kladováni  
 konečné uloženi  
 jiný účel (upřesněte):  
12 Navržený druh dopravy  
(silniční, železniční, 
námořní, letecká, 
vnitrozemská vodní)  Místo odeslání  Místo příjezdu  Navrhovaný přepravce  
(je-li znám)  
 1.    
 2.    
 3.    
 4.    
 5.    
 6.    
 7.    
 8.    
  - 82 - 
13. Posloupný výčet zemí dotčených přepravou (první je země, ve které se radioaktivní odpad nachází, a poslední je 
země určení)  
 1. 3. 5. 7. 
 2. 4. 6. 8. 
14. Podle ustanovení směrnice 2006/117/Euratom já jako žadatel:  
1. žádám o povoleni uskut ečnit (opakovanou) přepravu výše uvedeného radioaktivního odpadu  
a 
2. potvrzuji, že uvedené údaje jsou pravdivé podle mého nejlepšího vědomí a svědomí a Že (opakovaná) 
přeprava se uskuteční v souladu se všemi platnými právními předpisy,  
a 
3. (*) (v případě  přepravy typu MM nebo ME) zavazuji se, že převezmu odpad nazpět, pokud nebude možné 
(opakovanou) přepravu uskutečnit nebo pokud nebude možné splnit podmínky přepravy,  
nebo  
(*) (v případě přepravy typu IM nebo TT) připojuji doklad o ujednáni mezi příjemcem  a držitelem 
radioaktivního odpadu usazeným ve třetí zemi, které akceptoval příslušný orgán třetí země a které uvádí, že 
držitel ve třetí zemi převezme radioaktivní odpad zpit, pokud nebude možné (opakovanou) přepravu 
uskutečnit nebo pokud nebude možné spl nit podmínky přepravy, pokud nelze přijmout jiné alternativní 
bezpečnostní opatření.  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možností označených hvězdičkou: nehodící se škrtněte.   - 83 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpov ědný za vydání 
povolení k přepravě)  
ČÁST A -2 
Potvrzení o přijetí žádosti o přepravu radioaktivního odpadu - Vyžádání chybějících údajů  
15
. Název příslušného orgánu odpovědného za vydáni povolení:  ________________________________ ______   
Členský stát:  ________________________________ ________________________________ ____________   
 původu (1);  určení (2),  kde zásilka poprvé vstupuje do Společenství (3) 
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: __________________ Město: __________________ Země: ___________________  
Tel.: _______________________ Fax: ________________________ E mail: __________________________  
Kontaktní osoba: pa n/paní  ________________________________ ________________________________ __  
Datum přijetí/registrace: ___________________________________________________________ (dd/mm/rrrr)  
(1) V případě zásilky typu MM nebo ME.  
(2) V případě zásilky typu IM.  
(3) V případě zásilky typu TT.  
16
. Název dotčeného příslušného orgánu:  ________________________________ ________________________   
Členský stát nebo země (zaškrtněte příslušně okénko)  určení,  tranzitu,  kde zásilka poprvé vstupuje do 
Společenství, nebo  původu (1):  ________________________________ ____________________________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: __________________ Město: __________________ Země: ___________________  
Tel.: __ _____________________ Fax: ________________________ E mail: __________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
(1) V připadá zásilky typu TT a IM může byt dobrovolně konzultována země původu, směrnice to však závazně nevyžaduje.  
17
. Podle ustanoveni sm ěrnice 2006/117/Euratom považuji žádost ze dne _____________________ (dd/mm/rrrr), 
která byla přijata dne _________________________ (dd/mm/rrrr)  
a) (*) za neúplnou a žádám o doplnění téohto chybějících údajů  
(V případě nedostatku místa uveďte úplný výčet c hybějících informací (položek) ve zvláštní příloze.)  
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
(datum a místo)  (razítko)  (podpis)  
b) (*) za řádně vyplněnou a potvrzuji její přijetí.  
 ________________________________ ________________________________ ___________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možností označených hvězdičkou: ne hodící se škrtněte.   - 84 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydání 
povolení k přepravě)  
ČÁST A -3 
Zamítnutí nebo schválení zásilky radioaktivního odpadu dotčenými příslušnými orgány  
18. Název dotčeného příslušného orgánu:  ________________________________ _________________________   
Členský stát n ebo země (zaškrtněte příslušné okénko a vyplňte):  ________________________________ ____   
 původu (1),  určení (2),  tranzitu (3) 
Adresa:  ________________________________ ________________________________ _________________   
Poštovní směrovací číslo: __________________ Město: ________________ Země: _____________________  
Tel.: ________________________ Fax: __________________ _____ E mail: __________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
(1) V případě zásilky typu TT a IM může být dobrovolně konzultována země původu, směrnice to však závazně nevyžaduje.  
(2) V případě zásilky typu MM nebo ME.  
(3) v případě zásilky typu MM, IM, ME nebo TT, pokud je dotčen alespoň jeden člensky stát tranzitu.  
19. (*) Obecná lhůta pro automatické schválení  ________________________________ _________   (dd/mm/rrrr)  
 (*) Žádost o další období nejvýše jednoho měsíce, prodloužení lhůty pro automatické schválení:  
 ________________________________ ________________________________ _________   (dd/mm/rrrr)  
 
 ________________________________ ________________________________ _______________________   
(datum a  místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možností označených hvězdičkou: nehodící se škrtněte.  
20. Podle ustanovení směrnice 2006/117/Euratom  
(*) zamítám z těchto důvodů (v případě nedostatku místa připojte úplný výčet důvodů ve zvláštní př íloze):  
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
 (*) schvaluji za těchto podmínek (v případě nedostatku místa připojte úplný výčet podmínek ve zvláštní příloze):  
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možností označenýc h hvězdičkou: nehodící se škrtněte.   - 85 - 
Registrační číslo:  ________________________________ _________   
(výplni příslušný orgán odpovědný za vydání 
povolení k přepravě)  
ČÁST A -4a 
Povolení k přepravě radioaktivního odpadu  
21. Název příslušného orgánu odpovědného za vydání povolení k přepravě:  _____________________________   
Členský  stát (zaškrtněte příslušné okénko a vyplňte):  ________________________________ _____________   
 původu,  určení nebo  kde odpad vstupuje do Společenství  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ___ ___________________ E mail: ___________________________  
Kontaktní osoba: pan/paní ________________________________ ________________________________ __  
22. Posloupný výčet případů schválení a/nebo zamítnutí zemí dotčených přepravou  
 Členský stát nebo země  Schváleno?  Výčet případných podmínek 
schváleni  Odkaz na přílohy  
 1. ANO/NE (*)    
 2. ANO/NE (*)    
 3. ANO/NE (*)    
 4. ANO/NE (*)    
 5. ANO/NE (*)    
 6. ANO/NE (*)    
 7 ANO/NE (*)    
 8. ANO/NE (*)    
 (*) Použije se pouze jedno prohlášení označené hvězdičkou, nehodící se škrtněte.  
23. Přijatého rozhodnutí uvedené ho v této části bylo dosaženo v souladu s ustanoveními směrnice 
2006/117/Euratom(1). 
Příslušné orgány dotčených zemí jsou informovány o tom, že  
jednorázová přeprava (*)  
opakovaná přeprava (*)  
radioaktivního odpadu popsaného v části A -1 byla  
POVOLENA  
Datum konce platnosti povolení:  ________________________________ ___________________   (dd/mm/rrrr)  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedno prohlášení označené hvězdičkou, nehodící se škrtněte.  
(1) Toto povolení nijak nesnižuje odpovědnost držitele, přepravce, vlastníka, příjemce nebo jakék oli jiné fyzické nebo právnické 
osoby dotčené zásilkou.   - 86 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydáni 
povolení k přepravě)  
ČÁST A -4b 
Zamítnuti' přepravy radioaktivního odpadu  
24. Název příslušného orgánu odpovědného za zamítnutí přeprav y:  ________________________________ ____   
členský stát (zaškrtněte příslušné okénko a vyplňte):  ________________________________ _____________   
 původu,  určeni,  tranzitu nebo  kde odpad vstupuje do Společenství  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: _________ _______________ Fax: ______________________ E mail: ___________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
25. Posloupný výčet případů schválení a/nebo zamítnutí dotčených zemí  
 Členský stát nebo země  Schváleno?  Výčet případných podmínek 
souhlasu nebo dů vodů zamítnutí  Odkaz na přílohy  
 1. ANO/NE (*)    
 2. ANO/NE (*)    
 3. ANO/NE (*)    
 4. ANO/NE (*)    
 5. ANO/NE (*)    
 6. ANO/NE (*)    
 7. ANO/NE (*)    
 8. ANO/NE (*)    
 Přijatého rozhodnuti uvedeného v této části bylo dosaženo v souladu s ustanove ními směrnice 
2006/117/Euratom.  
Příslušné orgány dotčených zemí jsou informovány o tom, že  
jednorázová přeprava (*)  
opakovaná přeprava (*)  
radioaktivního odpadu popsaného v části A -1 byla  
ZAMÍTNUTA  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedno prohlášení označené hvězdičkou, nehodící se škrtněte.   - 87 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydání 
povolení k přepravě)  
ČÁST A -5 
Popis zásilky radioaktivního odpadu a seznam obalů  
26. Žadatel (obchodní název):  ________________________________ ________________________________ __  
 držitel,  příjemce,  jiný, upřesněte:  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ___________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
27. Datum konce platnosti povolení  ________________________________ _________________   (dd/mm/rrrr) pro  
 jednorázovou přepravu nebo  
 opakovanou přepravu, sériová číslo zásilky:  ________________________________ _________________   
28. Charakteristika radioaktivního odpadu  
Fyzikálně -chemické vlastnosti (zaškrtněte příslušné okénko):  
 pevný  
 kapalný  
 plynný  
 jiný (např. štěpný, s malou rozptýlitelností...), upřesněte:  ________________________________ _______   
Hlavní radionuklidy:  ________________________________ ________________________________ _______   
Maximální aktivita záření alfa na obal (GBq):  ________________________________ ___________________   
Maximální aktivita záření beta/gama na obal (GBq):  ________________________________ ______________   
Celková aktivita záření alfa (GBq):  ________________________________ ___________________________   
Celková aktivita zářeni beta/gama (G Bq):  ________________________________ ______________________   
29. (*) Identifikační číslo  (*) Typ (1) (*) Hrubá hmotnost (kg)  (*) čistá hmotnost (kg)  (*) Aktivita (GBq)  
     
     
     
     
     
     
     
     
     
     
     
     
Celkový počet1 Celkem/typ:  Celkem:  Celkem:  Celkem:  
(*) Vyplní se pro každý obal. v případě nedostatku místa přiložte samostatný seznam!  
(1) Podle Pravidel pro bezpečnou přepravu radioaktivních materiálů ve vydání z rohu 2005, bezpečnostní požadavky TS -R-1, 
IAEA, Vídeň, 2005.  
30. Datum odeslání zásilky:  ________________________________ __________________________   (dd/mm/rrrr)  
Potvrzují, že údaje uvedené v této části (a v přiloženém seznamu nebo dokumentech) jsou podle mého 
nejlepšího vědomí a svědomí pravdivé - 
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)   - 88 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydání 
povol ení k přepravě)  
ČÁST A -6 
Potvrzení o přijetí radioaktivního odpadu  
31. Příjemce (obchodní název):  ________________________________ ________________________________ _  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: _____________ _________ E mail: ___________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
32. Uložení radioaktivního odpadu po přepravě (obchodní název):  ________________________________ ______   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ___ _____________________ Fax: ______________________ E mail: ___________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
33. Povolení udělené (zaškrtněte příslušně okénko):  
 pro jednorázovou přepravu typu MM nebo IM  
 pro jednorázovou přepravu typu ME nebo TT  
 pro op akovanou přepravu typu MM nebo IM, sériové číslo zásilky:  _______________________________   
Poslední přeprava, na niž se povolení vztahuje:  ano  ne 
 pro opakovanou přepravu typu ME nebo TT, sériové číslo zásilky:  _______________________________   
Poslední přeprava, na niž se povolení vztahuje:  ano  ne 
34.  Nepouži je se.  
 Přeprava typu ME nebo TT (tuto položku lze nahradit samostatným prohlášením, uveďte v odkazu na 
přílohy):  
Vstupní hraniční přechod třetí země určení nebo tranzitu:  
Třetí země: _________________________________ Hraniční přechod: _____________________ ___________  
35. Podle typu přepravy musí příjemce zaslat potvrzení o přijeti spolu s části A -5: 
— typ MM nebo IM: příslušnému orgánu členského státu určeni.  
— typ ME nebo TT: žadateli (typ ME: držiteli, typ TT: osobě odpovědné za přepravu v členském státu , kde 
odpad vstupuje do Společenství), podle položky 4 (část A -1). 
Datum přijetí radioaktivního odpadu:  ________________________________ _________________   (dd/mm/rrrr)  
Datum odeslání potvrzení o příjmu:  ________________________________ __________________   (dd/mm/rrrr)  
Já jako příjemce potvrzuji, že údaje v této části (a přiloženém seznamu) jsou podle méh o nejlepšího vědomí a 
svědomí pravdivé.  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
  - 89 - 
36.  Nepoužije se.  
 Přeprava typu ME nebo TT: žadatel zasílá potvrzení o přijeti a případné prohlášeni příjemce orgánu, který 
vydal povoleni.  
1. Příjemce se sídlem mimo Evropskou unii může přijeti radioaktivního odpadu potvrdit prohlášením nebo 
osvědčením uvádějícím alespoň údaje uvedené v položkách 31 až 36.  
2. Příslušný orgán, který obdrží originál potvrzení o přijeti, musí zaslat jeho kopie ostatním příslušným 
orgánům.  
3. Origin ály části A -5 a A -6 musí být nakonec zaslány příslušnému orgánu, který vydal povolení.  
4. U přepravy mezi členskými státy musí příslušný orgán členského státu původu nebo státu, kde zásilka 
poprvé vstoupí do Společenství, zaslat kopií potvrzeni o přijetí držiteli.  
 Datum odeslání potvrzeni o přijeti (spolu s části A -5): 
(dd/mm/rrrr)  Hraniční přechod výstupu ze Společenství:  
 Země:  hraniční přechod  
 
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)   - 90 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslu šný orgán odpovědný za vydání 
povolení k přepravě)  
ČÁST B -1 
Žádost o povolení k přepravě vyhořelého paliva  
1 Typ přepravy (zaškrtněte příslušné okénko):  
 Typ MM: přeprava mezi členskými státy (přes jeden nebo více členských států nebo třetích zemí)  
 Typ IM: dovoz do Společenství  
 Typ ME: vývoz ze Společenství  
 Typ TT: tranzit přes území Společenství  
2 Žádost o povoleni pro (zaškrtněte příslušné okénko):  
 jednorázovou přepravu ____________________ Pánované období provedení: _______________________  
 opakovanou pře pravu: počet (plánovaný): _____________ Plánované období provedeni: _______________  
3.  Nepoužije se.  
  (Opakovaná) přeprava typu MM přes jednu nebo více třetích zemí:  
Výstupní hraniční přechod Společenství (*):  ________________________________ _____________________   
Vstupní hraniční přechod třetí země (*) (pr vní tranzitní země):  ________________________________ _______   
Výstupní hraniční přechod třetí země (*) (poslední tranzitní země):  ________________________________ ____   
Hraniční přechod při zpětném dovozu do Společenství (*):  ________________________________ __________   
(*) Uvedeni přechody musí být stejné pro veškerou přepravu uvedenou v žádosti, pokud to příslušné orgány  nepovolí prak.  
4 Žadatel (obchodní název):  ________________________________ ________________________________ __  
 Držitel (pro typy MM, ME)  
 Příjemce (pro typ IM)  
 Jiný (pro typ TT), upřesněte:  ________________________________ _____________________________   
Adresa:  ________________________________ ________________________________ _________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________ ________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
5 Uložení vyhořelého paliva před přepravou (obchodní název):  ________________________________ _______   
Adresa:  ________________________________ ________________________________ _________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: _______ _______________  
Tel.: ________________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
6. Příjemce (obchodní název):  ________________________________ ________________________________ _  
Adresa:  ________________________________ ________________________________ _________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
7. Uložení vyhořelého paliva po přepravě (obchodní název):  ________________________________ _________   
Adresa:  ________________________________ ________________________________ _________________   
Poštovní směrovací číslo: ____________ ____ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
  - 91 - 
8. Typ vyhořelého paliva:  
 kovový uran  
 oxid uraničitý  
 směsné palivo (MOX)  
 jiné, upřesněte:  ________________________________ ________________________________ _______   
 Původní štěpná látka;  
 uran-235   (maximální obohaceni   %) 
 MOX   (nominální obohaceni uranu   %) 
  (maximální obsah plutonia   %) 
 Jiná, upřesněte:  ________________________________ ________________________________ ______   
Vyhoření paliva (průměr nebo obvyklé rozmezí):  ________________________________ ______   MWdny/teHM  
9. Celkový počet obalů  (např. kontejnerů, ...):  ________________________________ _____________________   
Celkový počet souborů/svazku/prvků/tyčí (upřesněte):  ________________________________ ____________   
Celková čistá hmotnost (kg):  ________________________________ ________________________________   
Celková hrubá hmotnost (kg):  ________________________________ _______________________________   
(Tyto hodnoty představují odhady, pokud se žádost týká opakované přepravy.)  
Popis zásilky (např. obaly):  
Druh o balů (') (je -li znán):  ________________________________ ________________________________ __  
Maximální obsah vyhořelého paliva na jeden obal (kg):  ________________________________ ___________   
Způsob označení jednotlivých obalů (při označeni štítky uveďte přiklad):  ______________________________   
(1) Podle Pravidel pro bezpečnou přepravu radioaktivních materiálů ve vydáni z roku 2005, bezpečnost ní požadavky TS -R-1, 
IAEA, Vídeň, 2005.  
10. Druh činnosti, při níž vzniklo vyhořelé palivo (zaškrtněte příslušné okénko):  
 výzkum,  komerční výroba jaderné energie,  jiná činnost (upřesněte):  ___________________________   
11. Účel přepravy vyhořelého paliva:  
 zpracování nebo přep racováni  
 dočasné skladováni  
 vrácení po dočasném skladováni  
 konečné uloženi  
 jiný účel (upřesněte):  
12. Navržený druh dopravy  
(silniční, železniční, 
námořní, letecká, 
vnitrozemská vodní)  Místo odesláni  Místo příjezdu  Navrhovaný přepravce  
(je-li znám)  
 1.    
 2.    
 3.    
 4.    
 5.    
 6.    
 7.    
 8.    
  - 92 - 
13. Posloupný výčet zemí dotčených přepravou vyhořelého paliva (první je země, ve které se vyhořelé palivo 
nachází, a poslední je země určení)  
 1. 3. 5. 7 
 2. 4. 6. 8. 
14. Podle ustanovení směr nice 2006/117/Euratom já jako žadatel:  
1. žádám o povolení uskutečnit (opakovanou) přepravu výše uvedeného vyhořelého paliva  
a 
2. potvrzuji, že uvedené údaje jsou pravdivé podle mého nejlepšího vědomi a svědomí a že (opakovaná) 
přeprava se uskuteční v soul adu se všemi platnými právními předpisy,  
a 
3. (*) (v případě přepravy typu MM nebo ME) zavazuji se. že převezmu vyhořelé palivo nazpět, pokud nebude 
možné (opakovanou) přepravu uskutečnit nebo pokud nebude možné splnit podmínky přepravy,  
nebo  
(*) (v případ ě přepravy typu IM nebo TT) připojuji doklad o ujednáni mezi příjemcem a držitelem vyhořelého 
paliva usazeným ve třetí zemi, které akceptoval příslušný orgán třetí země a které uvádí, že držitel ve třetí 
zemi převezme vyhořel ě palivo zpět, pokud nebude mo žné (opakovanou) přepravu uskutečnit nebo nebude 
možné splnit podmínky přepravy.  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna 2 možnosti označených hvězdičkou: nehodící se škrtnete.   - 93 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný  za vydání 
povoleni k přepravě)  
ČÁST B -2 
Potvrzení o přijetí žádosti o přepravu vyhořelého paliva - Vyžádání chybějících údajů  
15
. Název příslušného orgánu odpovědného za vydání povolení:  ________________________________ ______   
Členský stát:  ________________________________ ________________________________ ____________   
 původu (1),  určeni (2), nebo  kde vyhořelé pa livo poprvé vstupuje do Společenství (3) 
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ___________________________  
Kontaktní osob a: pan/paní  ________________________________ ________________________________ _  
 Datum přijetí/registrace:  ________________________________ _________________________   (dd/mm/rrrr)  
(1) V případ* zásilky typu MM nebo ME.  
(2) V případě zásilky typu IM.  
(3) V připadá zásilky typu IM nebo TT.  
16
. Název dotčeného příslušného orgánu:  ________________________________ ________________________   
Členský stát nebo země (vyznačte příslušné okén ko)  určení,  tranzitu,  kde zásilka poprvé vstupuje do 
Společenství, nebo  původu (1):  ________________________________ ____________________________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ___________________ ___ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ _  
(1) V případě zásilky typu TT a IM může být dobrovolná konzultována země původu, směrnice to však závazně nevyžaduje.  
17
. Podle ustanovení směrnice 2006/117/Euratom považuji žádost ze dne  _____________ (dd/mm/rrrr), která byla 
přijata dne ____________________ (dd/mm/rrrr),  
a) (*) za neúplnou a žádám o doplnění těchto chybějících údajů:  
(V případě nedostatku místa uveďte úplný výčet chybějících informací (položek) ve zvláštní příloze.)  
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
 ________________________________ ________________________________ ___________________   
(datum a místo)  (razítko)  (podpis)  
b) (*) za řádné vyplněnou a potvrzuji její přijet.  
 ________________________________ ________________________________ ___________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možnost) označených hvězdičkou: nehodící se škrtnete.   - 94 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušn ý orgán odpovědný za vydáni 
povolení k přepravě)  
ČÁST B -3 
Zamítnuti nebo schválení přepravy vyhořelého paliva dotčenými příslušnými orgány  
18. Název dotčeného příslušného orgánu:  ________________________________ ________________________   
Členský stát nebo země (zaškrtněte příslušně okénko a vyplňte):  ________________________________ ___  
 původu (1),  určení (2),  tranzitu (3): 
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pa n/pani  ________________________________ ________________________________ _  
(1) V případě zásilky typu TT a IM lze dobrovolné konzultovat zemi původu, směrnice to však závazné nevyžaduje.  
(2) V případě zásilky typu MM nebo ME.  
(3) V případě zásilky typu MM, IM, ME nebo TT, pokud je dotčen alespoň jeden členský stát tranzi tu. 
19. (*) Obecná lhůta pro automatické uděleni souhlasu:  ________________________________ _  (den/měsíc/rok)  
(*) Žádost o další období nejvýše Jednoho měsíce. prodloužení lhůty pro automatické schválení:  
 ________________________________ ________________________________ ______________  (dd/mm/rrrr)  
 
 ________________________________ ________________________________ ______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možnosti označených hvězdičkou: nehodící se škrtněte.  
20. Podle ustanovení směrnice 2006/117/Euratom  
(*) zamítám z těchto důvodů (v případě nedostatku místa připojte úplný výčet důvodů ve zvláštní příloze):  
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
(datum a místo)  (razítko)  (podpis)  
 (*) schvaluji za těchto podmínek (v případě nedostatku mista připojte úplný výčet podmínek ve zvláštní příloze):  
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
 ________________________________ ________________________________ ______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedna z možností označených hvězdičkou: nehodící se škrtněte.   - 95 - 
Registrační číslo :  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydání 
povoleni k přepravě)  
ČÁST B -4a 
Povolení k přepravě vyhořelého paliva  
21. Název příslušného orgánu odpovědného za vydání povolení k přepravě:  _____________________________   
Členský stát (zaškrtněte příslušné okénko a vyplňte):  ________________________________ _____________   
 původu,   určení,  tranzitu nebo  kde vyhořelé palivo vstupuje do Společenství  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: _________ ___________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
22. Posloupný výčet případů schválení a'nebo zamítnutí zemí dotčených přepravou  
 Členský stát nebo země  Schváleno?  Výčet případných podmínek 
souhlasu  Odkaz na přílohy  
 1. ANO/NE (*)    
 2. ANO/NE (*)    
 3. ANONE  (*)   
 4. ANO/NE (*)    
 5. ANO/NE (*)    
 6. ANO/NE (*)    
 7. ANO/NE (*)    
 8. ANO/NE (*)    
 (*) Použije se pouze jedno prohlášeni označené hvězdičkou, nehodící se škrtněte.  
23. Přijatého rozhodnutí uvedeného v této části bylo dosaženo v soul adu s ustanoveními směrnice 
2006W117/Euratom (1), 
Příslušné orgány dotčených zemi jsou informovány o tom, že  
jednorázová přeprava (*)  
opakovaná přeprava (*)  
vyhořelého paliva popsaného v částí B -1 byla  
POVOLENA  
Datum konce platnosti povolení:   (dd/mm/rrrr ) 
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedno prohlášení označené hvě2dičkou, nehodíc! se škrtněte.  
(1) Toto povolen' nijak nesnižme odpovědnost držitele, přepravce, vlastníka, příjemce nebo jakékoli jiné fyzická nebo právnické 
osoby do tčené zásilkou.   - 96 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydáni 
povolení k přepravě)  
ČÁST B -4b 
Zamítnuti přepravy vyhořelého paliva  
24. Název příslušného orgánu odpovědného za zamítnuli' přepravy:  ________________________________ ____   
Členský stát (zaškrtněte příslušné okén ko a vyplňte):  ________________________________ _____________   
 původu,  určení,  tranzitu nebo  kde vyhořelé palivo vstupuje do Společenství  
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: _____________ _________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
25. Posloupný výčet případů schválení a/nebo zamítnutí dotčených zemí  
 Členský stát nebo země  Schváleno?  Výčet případných podmínek 
souhlasu nebo důvodů zamítnutí  Odkaz na přílohy  
 1. ANO/NE (*)    
 2. ANO/NE (*)    
 3. ANO/NE (*)    
 4. ANO/NE (*)    
 5. ANO/NE (*)    
 6. ANO/NE (*)    
 7. ANO/NE (*)    
 8. ANO/NE (*)    
 Přijatého rozhodnutí uvedeného v této části bylo dosaženo v souladu s ustanoveními směrnice 
2006/117/Euratom.  
Příslušné orgány dotčených zemí jsou informovány o tom, že  
jednorázová přeprava (*)  
opakovaná přeprava (*)  
vyhořelého paliva popsaného v části B -1 byla  
ZAMÍTNUTA  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
(*) Použije se pouze jedno prohlášení označené hvězdičkou,  nehodící se škrtněte.   - 97 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydání 
povoleni k přepravě)  
ČÁST B -5 
Popis zásilky vyhořelého paliva a seznam obalů  
26. Žadatel (obchodní název):  ________________________________ ________________________________ __  
 držitel,  příjemce,  jiný, upřesněte:  ________________________________ _______________________   
Adresa:  ________________________________ ________________________________ _________________   
Pošto vní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní:  ________________________________ ________________________________ _  
27. Datum konce platnosti Dovolení   (dd/mm/rrrr) pro  
 jednorázovou přepravu  
 opakovanou přepravu, sériové číslo zásilky:  ________________________________ __________________   
28. Typ vyhořelého paliva:  
 kovový uran  
 oxid uraničitý  
 směsné palivo (MOX)  
 jiné. upřesněte:  ________________________________ ________________________________ ________   
 Původní štěpná látka:  
 uran 235   (maximální obohacení   %) 
 MOX   (nominální obohaceni uranem   %) 
  (max. obsah plutonia   %) 
 jiná. upřesněte:  ________________________________ ________________________________ _________   
 Vyhořeni paliva (průměr nebo obvyklé rozmezil:  ________________________________ _______   MWdny/teHM  
Celkový počet souborů/svazků/prvků/tyčí (upřesněte):  ________________________________ ____________   
Maximální obsah vyhořelého paliva na jeden obal (kg):   ________________________________ ___________   
29. (*) Identifikační číslo  (*) Typ (1) (*) hrubá hmotnost (kg)  (*) čistá hmotnost (kg)  (*) aktivita (GBq)  
     
     
     
     
     
     
     
     
     
     
     
     
Celkový počet:  Celkem/typ:  Celkem:  Celkem:  Celkem:  
(*) Vyplňte pro každý obal, v případě nedostatku místa přiložte samostatný seznam!  
(1) Podle Pravidel pro bezpečnou přepravu radioaktivních materiálů ve vydáni z roku 2005, bezpečnostní požadavky TS -R-1, 
IAEA, Vídeň, 2005.  
30. Datum odesláni zásilky:  ________________________________ ___________________________   (dd/mm/r rrr) 
Potvrzuji, že údaje uvedené v této část (a v přiloženém seznamu nebo dokumentech) jsou podle mého 
nejlepšího vědomí a svědomí pravdivé.  
 ________________________________ ________________________________ ________________________   
(datum a místo)  (razítko)  (podpis)   - 98 - 
Registrační číslo:  ________________________________ _________   
(vyplní příslušný orgán odpovědný za vydáni 
povolení k p řepravě)  
ČÁST B -6 
Potvrzení o přijeti vyhořelého paliva  
31. Při Brnče (obchodní název):  ________________________________ ________________________________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________________ Fax: ______________________ Email: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
32. Uložení vyhořelého paliva po přepravě (obchodní název):  ________________________________ _________   
Adresa:  ________________________________ ________________________________ ________________   
Poštovní směrovací číslo: ________________ Město: _________________ Země: ______________________  
Tel.: ________________ ________ Fax: ______________________ E mail: ____________________________  
Kontaktní osoba: pan/paní  ________________________________ ________________________________ __  
33. Povoleni udělené (zaškrtněte příslušné okénko):  
 pro jednorázovou přepravu typu MM nebo IM  
 pro jednorázovou přepravu typu ME nebo TT  
 pro opakovanou pře pravu typu MM nebo IM, sériové číslo zásilky:  _______________________________   
Poslední přeprava, na niž se povolení vztahuje:  ano  ne 
 pro opakovanou přepravu typu ME nebo TT, sériové číslo zásilky:  _______________________________   
Poslední přeprava, na niž se povolení vztahuje:  ano  ne 
34.  Nepoužije se  
 Pro př epravu typu ME nebo TT (tuto položku lze nahradit samostatným prohlášením, uveďte odkaz na 
přílohy):  ________________________________ ________________________________ _____________   
Vstupní hraniční přechod třetí země určeni nebo tranzitu:  ________________________________ _________   
Třetí země:  _______________________________   Hraniční přechod:  _____________________________   
35. Podle typu přepravy musí příjemce zaslat potvrzeni o p říjmu spolu s částí B -5: 
— typ MM nebo IM: příslušnému orgánu členského státu určení,  
— typ ME nebo TT: žadateli (typ ME: držiteli, typ TT: osobě odpovědné za přepravu v členském státě, kde 
vyhořelé palivo vstupuje do Společenství), podle položky 4 (část B -1). 
Datum přijetí vyhořelého paliva:  ________________________________ ____________________   (dd/mm/rrrr)  
Datum odeslání potvrzeni o přijetí:  ________________________________ __________________   (dd/mm/rrrr)  
Já jako příjemce potvrzuji, že údaje v této části (a přiloženém seznamu) jsou podle mého nejlepšího vědomi a 
svědomí pravdivé.  
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítk o) (podpis)  
  - 99 - 
36.  Nepoužije se.  
 Přeprava typu ME nebo TT: žadatel zasílá potvrzení o přijeti a případné prohlášeni příjemce orgánu, který 
vydal povoleni.  
1. Příjemce se sídlem mimo Evropskou unii může přijetí vyhořelého paliva potvrdit prohlášením nebo 
osvědčením uvádějícím alespoň údaje uvedené v položkách 31 až 36.  
2. Příslušný orgán, který obdrží originál potvrzeni o přijmu. musí zaslat jeho kopie ostatním příslušným 
orgánům,  
3. Originály části B -5 a B*6 musí být nakonec zaslány příslušnému orgánu, který  vydal povoleni.  
4. U přepravy mezi členskými státy musí příslušný orgán členského státu původu nebo státu, kde zásilka 
poprvé vstoupí do Společenství, zaslat kopií potvrzeni o přijetí držiteli.  
 Datum odeslání potvrzeni o přijetí  
(spolu s částí B -5):  ________________   (dd/mm/rrrr)  Hraniční přechod výstupu ze Společenství:  
 Země:  Hraněni přechod:  
 
 ________________________________ ________________________________ _______________________   
(datum a místo)  (razítko)  (podpis)  
 
  - 100 - 
 
 
Annex  6 to Decree  No …………  
 
Standard Document (Commission Decision 2008/312/Euratom)  
 
General notes  
Sections A -1 to A -6: to be comple ted for shipments of radioactive waste.  
Sections B -1 to B -6: to be completed for shipments of spent fuel (including spent fuel 
destined for final disposal and as such categorised as waste)  
Section A -1 or B -1 (Application for authorisation of shipments): to  be completed by the 
applicant, this is the following, depending on the type of the shipment:  
— the holder in case of a shipment between Member States (type MM) or an export from the 
Community into a third country ( Type ME),  
— the consignee in case of an i mport into the Community from a third country ( Type IM),  
— the person responsible for the shipment in the Member State by which the radioactive 
waste or spent fuel enters the Community in case of a transit through the Community 
(Type TT).  
Section A -2 or B -2 (Acknowledgement of receipt of application): to be completed by the 
relevant competent authorities concerned, which are – depending on the type of the shipment – 
the competent authorities:  
— of origin in case of a shipment Type MM or ME,  
— of destination  in case of a shipment Type IM,  
— where the shipment first enters the Community in case of a Type TT shipment, and all 
competent authorities of the Member States of transit, if any.  
Section A -3 or B -3 (Refusal or consent): to be completed by all competent authorities 
concerned.  
Section A -4a/A -4b or B -4a/B -4b (Authorisation or refusal of shipment): to be completed by 
the competent authority responsible for issuing the authorisation, which is – depending on the 
type of the shipment – the competent authority o f: 
— the Member State of origin in case of shipments type MM and ME shipments,  
— the Member State of destination in case of Type IM shipments, or  
— the first Member State of transit, where the shipment enters the Community in case of 
Type TT shipments.  
Section A -5 or B -5 (Description of consignment/List of packages): to be completed by the 
applicant as referred to in Section A -1 or B -1. 
Section A -6 or B -6 (Acknowledgement of receipt of shipment): to be completed by the 
consignee (in case of MM and IM shipme nts) or the holder (in case of ME shipments) or the 
person responsible for the shipment (in case of TT shipments).  
32008D0312 - 101 - 
  - 102 - 
  - 103 - 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
  - 104 - 
  - 105 - 
 
 
  - 106 - 
  - 107 - 
 
  - 108 - 
  - 109 - 
  - 110 - 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
  - 111 - 
  - 112 - 
  - 113 - 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
  - 114 - 
  - 115 - 
 
 
 
  - 116 - 
  - 117 - 
 
 
  - 118 - 
  - 119 - 
  - 120 - 
 
  - 121 - 
 
Annex  7 to Dec ree No …………  
 
REQUIREMENTS FOR CAL CULATION OF ACTIVITY  VALUES FOR 
EXCEPTION OF A PACKA GE FOR TRANSPORT OF RAD IOACTIVE OR FISSILE 
MATERIAL IN INSTRUME NTS OR PRODUCTS  
 
Principles and methods for calculation of activity values for exception of a package for 
transport of radioactive or fissile material in instruments or products are stipulated in IAEA 
document Radiation Protection and Safety of Radiation Sources: International Basic Safety 
Standards, General Safety Requirements, IAEA Safety Standards Series No.  GSR, Part 3, 
International Atomic Energy Agency, Vienna, 2014.