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1. ------IND- 2008 0078 CZ- EN- ------ 20080331 --- --- PROJET

Draft

DECREE

of [date] 2008

on type approval of packaging sets for transportation, storage and disposal of nuclear materials and radioactive substances, on type approval of sources ionising radiation and on transportation of nuclear materials and radioactive substances (on type approval and transportation)

The State Office for Nuclear Safety will assess according to Section 47(7) for the implementation of Section 9(1)(m) and (p), Section 13(3)(d), Section 20(1)(b) and (d) and Section 23 of Act No. 18/1997 Coll., on the peacetime use of nuclear energy and ionising radiation (Nuclear Act) and on changes and amendment of certain laws, as amended by Act No. 13/2002 Coll., Act No. 253/2005 and Act No. 186/2006 Coll., (hereinafter only as “Act”):

PART ONE

INTRODUCTORY PROVISIONS

Section 1

Subject of legislation

(1) This Decree was announced in accordance with Directive 98/34/EC of the European Parliament and of the Council of 22 June 1998 laying down a procedure for the provision of information in the field of technical standards and regulations.

(2) This Decree

a) establishes packaging sets for transportation, storage and disposal of nuclear materials and radioactive substances, which are subject to type approval by the State Office for Nuclear Safety (hereinafter only as “Office”),

b) amends the requirements of application for type approval and documents, which need to be enclosed with the application, and the method of approval by the Office,

c) amends the extent and method of documenting compliance of packaging sets, which are subject to type approval, with approved type,

d) specifies nuclear materials and radioactive substances, for the preparation of which one needs a permit, extent and method of performance of documentation being approved, which is a part of the application for permit,

e) defines a method for securing the shipping and transportation of radioactive substances,

f) implements the appropriate regulation of the European Community1) and methods of international shipping of radioactive waste and spent nuclear fuel.

§ 2

Basic concepts

For the purposes of this Decree, the following definitions shall apply:

a) A1 is the value of activity of special form of radioactive substance, stated in table 1 (1) of Annex No. 3 or derived in accordance with points 1 through 6 of Annex No. 3 and used to determine activity limits,

b) A2 is the value of activity of other than special form of radioactive substance, stated in table 1 (1) of Annex No. 3 or derived in accordance with points 1 through 6 of Annex No. 3 and used to determine activity limits,

c) alpha emitter with low toxicity natural uranium, depleted uranium, natural thorium, 235U or 238U, 232Th, 228Th and 230Th contained in ores and chemical concentrates or alpha emitter with a half-life of less than ten days,

d) Means of transportation for shipping radioactive substances1. for air transportation an airplane, 2. for ship transportation a vessel, part of the cargo area or defined deck surface of

vessel, or

3. for road or rail transportation a vehicle,

e) the holder of radioactive waste or depleted nuclear fuel is a physical or legal entity who, before shipping, is liable for the radioactive waste or depleted nuclear fuel and intends to ship it to the recipient,

f) fixed contamination is any contamination other than non-fixed contamination,

g) Criticality Safety Index (CSI) number, which proves the maintenance of a criticality state of the radioactive cargo, external package or shipping container containing fissile material, during their storage and throughout transportation,

h) contamination occurrence of radioactive substance on the surface of packaging set or transportation means in amount surpassing 0.4 Bq/cm2 for beta, gamma or alpha emitters with low toxicity or 0.04 Bq/cm2 for other alpha emitters,

i) substance with low-specific-activity (LSA) is a radioactive substance, which has its own limited specific activity or radioactive substance, the average specific activity of which was intentionally limited; external shielding materials surrounding the substance with low specific activity are not taken into consideration in determining the average specific activities; substance with low-specific-activity (LSA) is furthermore subdivided into:1. LSA-I, which is furthermore broken down into

aa) other radioactive substances, in which the activity is completely dispersed and the determined average specific activity does not exceed thirty times the value determined according to point 1 through 6 of Annex No. 3with the exception of fissile material in quantities not exempt from requirements on fissile material according to point 72 part I of Annex No. 1,

1 ) Council Directive 2006/117/Euratom from November 20th 2006 on supervision over transportation of radioactive waste and spent fuel and on its control.

bb) solid irradiated uranium, depleted uranium, natural thorium or their solid, possibly liquid compounds or mixtures,cc) radioactive substance for which the value A2 is unlimited with the exception of fissile material in quantities which are not exempt from the requirements on fissile material according to point 72 part I of Annex No. 1,dd) uranium and thorium ores, concentrates of these ores and other ores containing naturally appearing radionuclides, which are intended for processing in order to utilize these radionuclides,

2. LSA-II, which are furthermore broken down intoaa) other substances, in which the activity is completely dispersed and the determined specific activity does not exceed 10-4 A2/g for solid substances and 10-5 A2/g for liquids,bb) water with tritium and concentration of up to 0.8 TBq/l,

3. LSA-III, which are solid substances (for example solidified wastes, activated materials) with the exception of powders, in this simultaneouslyaa) radioactive substance is completely dispersed in solid substance or in solid objects or is essentially evenly dispersed in a compact bonding substance (such as concrete, bitumen, ceramics etc.),bb) radioactive substance is relatively insoluble or is suspended in a relatively insoluble base, so that even in the event of loss of functionality of the packaging set the leak of radioactive substances from one packaging set by leaching in water for the period of seven days would not exceed 0.1 A2 andcc) the determined average specific activity of a solid substance without shielding material does not exceed 2.10-3 A2/g,

j) maximum normal operational pressure is maximum overpressure, which can be formed in a retaining system for the period of one year at a temperature and sun exposure corresponding to the surrounding conditions during transportation under the presumption that ventilation is not used, of external cooling by an auxiliary system or operational checks during transportation,

k) non-fixed contamination is a contamination which can be removed from the surface of the packaging set or a means of transportation under usual transport conditions,

l) non-irradiated thorium is thorium which contains a maximum of 10-7 g 233U per gram of 232Th,

m) non-irradiated uranium is uranium which contains a maximum of 2.103 Bq plutonium per gram of 235U, a maximum of 9.106 Bq of fissile products per gram 235U and a maximum of 5.10-3 g 236U per gram 235U,

n) packaging set is a set of parts essential for complete closure of radioactive content,

o) limiting system of arrangement of fissile materials in packaging set or arrangement of packaging set parts in such a way in order for the criticality state to be ensured,

p) description of the construction type documentation, which contains a description of a special form of radioactive substance, radioactive substance with low dispersibility, radioactive cargo or packaging set; documentation contains especially material specifications, technical drawings and reports proving compliance with the defined requirements,

q) surface contaminated object is a solid object, which in and of itself is not radioactive and on the surface of which a radioactive substance is dispersed; surface contaminated objects are categorized into two groups: 1. SCO I, where

aa) fixed contamination on an accessible surface with an average area of 300cm2 (or on the entire if such is less than 300cm2) does not exceed 4.104 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 4.103 Bq/cm2 with all other alpha emitters, and bb) non fixed contamination on an accessible surface with an average area of 300cm2 (or on the entire surface if such is less than 300cm2) does not exceed 4 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 0.4 Bq/cm2 with all other alpha emitters, cc) the sum of fixed contamination and non-fixed contamination on an inaccessible surface with an average area of 300cm2 (or on the entire surface if such is less than 300cm2) does not exceed 4.104 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 4.103 Bq/cm2 with all other alpha emitters,

2. SCO II, on the surface of which the fixed or non-fixed contamination or their sum exceed the limits stated in point 1, and on whichaa) fixed contamination on an accessible surface with an average area of 300cm2 (or on the entire surface if such is less than 300cm2) does not exceed 8.105 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 8.104 Bq/cm2 with all other alpha emitters, andbb) non fixed contamination on an accessible surface with an average area of 300cm2 (or on the entire surface if such is less than 300cm2) does not exceed 400 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 40 Bq/cm2 with all other alpha emitters, cc) the sum of fixed contamination and non-fixed contamination on an inaccessible surface with an average area of 300cm2 (or on the entire surface if such is less than 300cm2) does not exceed 8.105 Bq/cm2 with beta and gamma emitters and alpha emitters with low toxicity, or 8.104 Bq/cm2 with all other alpha emitters,

r) reprocessing means a process or an operation, the purpose of which is the extraction of radioactive isotopes from spent fuel for further use,

s) transportation index is a number assigned by the shipper to the packaging set, external cover, transportation container, non-packed substance with low specific activity (LSA-I) or non-packed surface contaminated object (SCO-I), and used to check irradiation exposure,

t) transportation container is an apparatus for the transportation of packed or non-packed merchandise via one or more methods of transportation without reloading individual items of its content; the transportation container is fitted with a steady cover, it is sufficiently sturdy and resistant for repeated use and is equipped with an apparatus enabling its handling, especially reloading between means of transportation from one type of transportation to the other; it is subdivided into

1. IBC, which is a large tank for bulk cargo substances or transportation cover means, the volume of which from the perspective of radioactive materials is maximum of 3 m3, is constructed for mechanical handling and is resistant to strain during handling and transportation,

2. small transportation container, which has all external dimensions less than 1.5 m or internal content not greater than 3 m3,

3. large transportation container,

u) Transportation of radioactive waste or spent nuclear fuel outside of the European Union is such transportation where the state of origin or a state of destination are third party states,

v) Transportation of radioactive waste or spent nuclear fuel within the European Union is such transportation where the state of origin or a state of destination are its Member States

w) Transportation under special conditions is transportation during which, considering economic and social perspectives, all requirements of section 9 cannot be fulfilled and these requirements are replaced with special conditions which ensure that the level of nuclear safety and radiation protection during transportation is equal or greater,

x) Recipient of radioactive waste or spent nuclear fuel is a physical or legal entity to which radioactive waste or spent nuclear fuel is scheduled to be or already is transported,

y) Radioactive substance with low dispersibility is a radioactive substance in a solid state, which is not powder, is either separate or in a closed casing, and has a limited ability to disperse, which complies with requirements of point 5 part I of Annex No. 1,

z) Radioactive substance of special form is a solid non-dispersible substance or a tightly sealed casing containing radioactive substance; radioactive substance of special form complies with requirements of points 2. to 5. of part I of Annex No. 1,

aa) Radioactive shipment is a packaging set including radioactive content handed over for transportation; individual types of radioactive shipments are:1. industrial shipment type IP-1 (type IP-1),2. industrial shipment type IP-2 (type IP-2),3. industrial shipment type IP-3 (type IP-3),

4. radioactive shipment type A,5. radioactive shipment type B(M),6. radioactive shipment type B(U),7. radioactive shipment type C,8. exempt shipments,

bb) Radioactive content is a radioactive substance with all contaminated or activated solid substances, liquid substances and gases inside of packaging set.

cc) Properly completed application is a standard document completed in part A-1 for radioactive waste or in part B-1 for spent radioactive fuel,

dd) Standard document is a form, a specimen of which and method of completion is stated in Annex No. 5

ee) State of origin is a state where the transportation of radioactive waste or spent nuclear fuel is to be or already has been started,

ff) State of transit is a state over the territory of which the transportation of radioactive waste or spent nuclear fuel is scheduled to be or is being realized and which is not a state of destination or origin,

gg) State of destination is a state to which the transportation of radioactive waste or spent nuclear fuel is to be or already has been started

hh) Fissile material is special fissile material2) and 241Pu or any combination of the stated radionuclides,

2) Section 2 letter j) par 1 letter b) of Act No. 18/1997 Coll., as amended by Act No. 13/2002 Coll.

ii) uranium1. enriched uranium with a higher mass share of 235U than 0.72% of mass; in enriched

uranium there is a trace mass share of 234U, 2. depleted uranium with a lower mass share of 235U than is contained in natural

uranium; in depleted uranium there is a trace mass share of 234U,

3. natural uranium, including chemically separated uranium, and which contains uranium isotopes in quantities of approx. 99.28% of 238U mass, approx 0.72% of 235U mass and also trace mass percentage of 234U,

jj) external cover is a protective case, which is used by a single shipper as one handling unit to transport one or more radioactive shipments,

kk) spent nuclear fuel is nuclear fuel which was irradiated in an active reactor zone and permanently removed from it; spent nuclear fuel can be deemed as a usable source, which can be reprocessed, or can be determined for final storage, if no further use is expected and it is handled as radioactive waste,

ll) exclusive use of a means of transportation or a transport container by a single shipper who manages all loadings and unloading during the course of the transportation,

mm) retaining system – arrangements of part of the packaging set in such a way that leak of radioactive substance is prevented during transportation; this arrangement is stated in the description of construction type.

PART TWO

TYPE APPROVAL

Section 3

Type approved products

(To Section 23 paragraph 1 of Act )

(1) The following are subject to type approval

a) these types of packaging sets intended for transportation, storage and disposal of nuclear material and radioactive substance:

1. packaging sets of type IP - 1, IP - 2 a IP - 3 for transportation of fissile material,2. packaging sets for transport of 0.1kg and more of uranium hexafluoride,3. packaging sets of type A for transportation of fissile material,4. packaging sets of type B(U), B(M) and C for transportation of radioactive

substances,5. packaging sets of type B(U), B(M) and C for transportation of fissile material,6. packaging sets of type D, intended for disposal of spent or irradiated nuclear fuel or

radioactive wastes created by its reprocessing,7. packaging sets of type S, intended for storage of fissile materials and radioactive

substances for radioactive substances of special forms whose activity ten times exceeds A1 values, or for radioactive substances other than ones of special form whose activity ten times exceeds A2 values,,

b) radioactive substances of special form and radioactive substances with low

dispersibility, c) these sources of ionising radiation:

1. radiation generators, with the exception of insignificant sources of ionising radiation,

2. closed radionuclide radiators contained within the radiators,3. opened radionuclide radiators intended for use in industrial applications,4. ionising fire alarms,5. light sources with radionuclide radiatorswith the exception of those sources of ionising radiation where compliance is with procedures according to another legal regulation3).

(2) Products that are also subject to type approval are products stated in paragraph 1 letters b) and c) if they are introduced to the market as used or following an overall repair and products stated in paragraph 1 letter a) in cases where a decision on type approval so prescribes.

(3) Products stated in paragraph 1, which are intended for demonstration or testing and are not intended for market introduction, are not subject to type approval.

(4) Products that are also subject to type approval are products stated in paragraph 1 letter a) point 4, letters b) and c) and paragraph 2 if they were produced or introduced to the market in some European Union Member State or have their origin in some European Union of free trade, which are at the same a contracting party of the European economic zone, under the presumption that such product complies with

a) technical regulations binding for production or introduction to the market, possibly for the use of such product in some of these states,

b) technical standards or rules of correct practice issued by the national standardization body or entity placed on its level, in accordance with legal regulations and state requirements, which is a contracting party of the European Economic Zone,

c) international technical standards rightfully used in some of these states, or d) traditional or innovative production methods used in some of these states in accordance

with its legal regulations, for which there is a sufficient detailed technical documentation providing that this product can be evaluated for the given purpose, in the event of need also based on additional (not identical) product tests,

if these technical regulations, technical standards, rules for correct practice or procedures ensure a level of protection of lawful interest corresponding to the level of this protection in the Czech Republic.

Section 4

Pertinence of application for type approval

(to Section 23 paragraph 2 of Act )

3) Act No. 22/1997 Coll., on technical requirements of products and on change and amendment of certain laws, as amended.

(1) Application for type approval contains

a) for a physical entity a name, possibly names, date of birth, permanent residence address or other residence on the territory of the Czech Republic or an address of residence outside of the Czech Republic, identification number, if such was assigned, possibly a first and last name, date of birth, permanent address, authorized representative4), if such is appointed; for a legal entity a name or a business name, registered seat, identification number, if such was assigned, name, possibly names, and last names of a person who is the statutory body and address of permanent residence, or a name, possibly names, and a last name of appointed authorized representative and address of permanent residence,

b) identification of manufacturer of packaging set, radioactive substance of special form,

radioactive substance with low dispersibility or a source of ionising radiation, if different from applicant,

c) identification of product being approved, name, description, construction type name, its parts, classification5) , application and with packaging set the limit values for its use,

d) description of use and method for introduction of the product to the market and with sources of ionising radiation also the justification of its use in accordance with Section 4 par 2 of Act,

e) introduction of the list of legal regulations and technical standards used in documents for type approval,

f) determination of a period for regular operational inspections and their method and extent, with sources of ionising radiation also the proposal of extent and method of performance of acceptance tests, tests for long term stability and operational stability according to another legal regulation5),

g) operational manual in Czech containing rules for safe product handling,

h) required time of Effectiveness of type approval,

i) description of the method of ensuring manufacturer quality in the extent defined in another legal regulation6),

j) documentation of tests according to Section5.

(2) Application for type approval is documented

a) for all packaging sets 1. material specification of radioactive substances or fissile materials, for which the

packaging set is designed, especially by a description of their physical and chemical state,

2. detailed description of packaging set type, especially retaining and limiting system, including construction documentation, technical blueprints, list of materials and technical procedures, which were used for its production,

4) Act No. 455/1991 Coll., on trade entrepreneurship (trade license Act), as amended.5) Decree No. 307/2002 Coll., on radiation protection, as amended by Decree No. 499/2005 Coll. 6) Decree No. 214/1997 Coll., on ensuring quality during activities related utilization of atomic energy and activities leading to irradiation and on determining criteria for classification and division of select equipment into safety classes

3. a document of approval of the packaging set abroad, if this regards a packaging set, which was similarly type approved abroad,

4. technological and production documentation with detailed description of materials and technological processes used in the production of the retaining (containment) system, description of sample taking and types of tests to be performed if the packaging set is designed for a maximum standard operational overpressure higher than 100 kPa,

5. documents on securing radiation protection or documents on securing nuclear safety, if the packaging set is designed for fissile materials,

6. account and justification of presumptions relative to characteristics of the irradiated nuclear fuel, used in safety analysis in calculations of sub-criticality, if the packaging set is designed for irradiated nuclear fuel,

7. account of special requirements necessary to remove heat with packaging sets containing fissile fuels or heat producing radioactive substances, in relation to specific type of transportation and means of transportation,

8. printable illustration of the appearance of the packaging set in A4 format with maximum dimensions 21cm by 30cm,

b) for type B(M) packaging sets1. a list of additional technical, operational and administrative measures to provide

nuclear safety and radiation protection, if this packaging set does not comply with requirements stated in points 43,59, 60 & 63 through 70 of part I of Annex No. 1,

2. data about restrictions with regards to type of transportation and on all special procedures during loading, transportation, unloading or handling,

3. highest and lowest values of external influences (heat, sunlight) which can be expected during transport and which were presumed during type construction design,

c) for packaging sets for transportation of 0.1kg and more of uranium hexafluoride data on compliance with requirements stated in points 30 & 31 of part I of Annex No. 1 and on using procedures stated in pint 32 of part I of Annex No. 1.

d) for sources of ionising radiation 1. detailed description of basic technical data on a specific type, construction

blueprints, labels and footnotes used in production,2. list of legal regulations and technical standards, which were applied in production, in

case standards were not used descriptions of technical design and documents on observance of requirements on securing radiation protection,

3. test report prepared by equipment manufacturer, containing data on actual operational parameters,

e) with sources of ionising radiation, which are radionuclide radiators,1. data on type of radionuclide, its type, manufacturer, activity, chemical and physical

form, description of requirements on radiation protection, document on approval of production in land of origin, with open radionuclide radiators the original accompanying document of open radionuclide radiator issued by manufacturer, with closed radionuclide radiators the classification of resistance, method of closeness, description of construction, recommended closeness checks, recommended time of radionuclide radiator use, possibly certificate of closed radionuclide radiator issued by the manufacturer,

2. concept of their decommissioning also containing a description of safe method of handling radioactive waste.

(3) Documentation required for submission according to letters a) through c) does not

have to be submitted, if it was already submitted to the Office in previous proceedings and if there were no changes in these documentations; in such a case the applicant will attach a declaration to the application, where he will give an account of previously submitted documentation.

Section 5

Test documentation

(For Section 23 par 2 and 3 of the Act) (1) Products for which test documentation is required to make a decision on type approval are packaging sets, radioactive substances of special form, radioactive substances with low dispersibility, radiation generators, closed radionuclide radiators, equipment containing radionuclide radiators, open radionuclide radiators, ionising fire alarms, sources of ionising radiation during the operation of which radionuclides are formed, and consumer products, which contain radioactive substances and to which radioactive substance were added during their production.

(2) Test documentation is

a) with packaging sets results of test performed in accordance with points 13 through 37 part II of Annex No. 1 and evaluated in accordance with points 1 and 2 of parts II of Annex No. 1, which prove the compliance of relevant requirements further stated in points 1 through 9, and these are1. requirements in points 6 through 16 of part I of Annex No. 1 for all packaging sets,2. requirements in points 21 through 28 of part I of Annex No. 1 for packaging sets type IP – 1, IP – 2 and IP – 3,3. requirements in points 29 through 32 of part I of Annex No. 1 for packaging sets for the transportation of 0.1kg and more of uranium hexafluoride,4. requirements in points 33 through 49 of part I of Annex No. 1 for packaging sets type A,5. requirements in points 50 through 64 of part I of Annex No. 1 for packaging sets type B(U),6. requirements in points 65 and 66 of part I of Annex No. 1 for packaging sets type B(M),7. requirements in points 67 through 70 of part I of Annex No. 1 for packaging sets type C,8. requirements in points 71 through 82 of part I of Annex No. 1 for packaging sets containing fissile materials,9. requirements of Annex No. 2 for packaging sets type D and packaging sets type S,

b) with radioactive substances of special form results of tests performed in accordance with points 4 through 11 part II of Annex No. 1,

c) with radioactive substances with small dispersibility results of tests performed in accordance with point 12 part II of Annex No. 1,

d) with radiation generators tests results show a compliance with relevant technical

standards, e) with closed radionuclide radiators test results show their tightness and level of resistance

in accordance with corresponding technical standards,

f) with equipment containing radionuclide radiators test results show the compliance of the given equipment and its classification in accordance with technical standards and protocols on test results proving that the declared properties fulfill radiation protection from the purpose and use of ionising radiations source,

g) with open radionuclide radiators, possibly with products containing open radionuclide radiators test results in the extent of accompanying document of open radiator defined by other legal regulations5),

h) with ionising fire alarm with closed radionuclide radiator test results showing level of

resistance against fire, very high temperatures and tightness in accordance with relevant technical standards,

i) with ionising radiation sources, during the operation of which radionuclides are formed, protocols on results proving that the declared properties comply with requirements on radiation protection from the perspective and use of source,

j) with consumer products which contain radioactive substances and to which radioactive

substances were intentionally added during production, a document proving ensuring of basic requirements on radiation protection for the entire time of their use.

(3) Tests are performed on products, prototypes or models made in a way to truly

simulate properties essential for evaluation of nuclear safety, radiation protection and designed radionuclide content.

(4) Test documentation of products can be supplemented by a reference to previous satisfactory test results for the same product or a similar use and properties, documentation of alternative tests or documentation of calculations performed by persons authorized or appointed by the Office and if reliability or conservatism of calculation methods and used parameters are acceptable for evaluation by the Office

Section 6

Approval method

(To Section 23 paragraph 2 of the Act)

In decision on type approval the Office will state

a) applicant information in the extent according Section4 par 1 letter a), b) manufacturer information in the extent according Section4 par 1 letter b), c) product information in the extent according Section4 par 1 letter c),

d) extent and method of approval according to Section7, e) conditions under which the product approval is issued; with packaging set, radioactive

substances of special form and radioactive substance with low dispersibility their identification mark,

f) with sources of ionising radiation their classification, frequency and minimum extent of the acceptance tests, test for long term stability and operational steadiness,

g) with small sources of ionising radiation and with insignificant sources of ionising

radiation containing radionuclide radiators approval of user’s manual containing rules for safe manipulation with it and their safe disposal,

h) period of validity of decision on type approval.

Section 7

Verification, extent and method of documenting compliance with approved type

(To Section23 par 4 and 5 of the Act)

(1) The manufacturer, importer or an entity introducing a product on the market will provide the verification of compliance with approved type

a) for every closed radionuclide radiator by a tightness test and other tests in the extent of certification of the closed radiator defined by another legal regulation5), possibly in the extent defined in the decision on type approval,

b) for every open radionuclide radiator in the extent of open radionuclide radiator accompanying document defined by another legal regulation5), possibly in the extent defined in the decision on type approval,

c) for sources of ionising radiation, which are not radioactive substances,1. procedures according to another legal regulation3), 2. with other sources of ionising radiation on every product or on a statistically selected

sample, if such is determined by the Office in the type approval,

d) for every packaging set.

(2) Compliance of products is documented by the manufacturer or an entity introducing the product on the market

a) certification for closed radionuclide radiators, b) accompanying document for open radionuclide radiators,

c) written declaration on compliance of products in Czech for1. packaging sets, with the exception of packaging sets for the transportation, storage

and disposal of spent nuclear fuel, classified in safety class 2, with which the evaluation is performed in accordance with another legal regulation7),

7) Decree No. 309/2005 Coll., on ensuring safety of select equipment.

2. radioactive substances of special form, 3. radioactive substances with low dispersibility, 4. for sources of ionising radiation of other than radionuclide radiators with the

exception of ionising radiation sources, where the evaluation of compliance is performed in accordance with another legal regulation3); written declaration of product compliance in Czech furthermore contains the stated pertinent details:aa) identification information on the manufacturer or importer, who issues the

declaration of compliance in the extent of Section4 par 1 letter a),bb) identification information on the product, at least in the extent of Section4 par 1

letter c), for pressure equipment forming the construction part of the hermetical envelope designed for internal overpressure description of influenced specially designed select equipment and their parts ensuring its hermetical seal under maximum designed accident,

cc) declaration that the product is safety and suitable for given purpose,dd) the method used to verify compliance and the list of legal regulations and

technical standards used in verifying compliance,ee) references to documents issued during compliance verification,ff) name, address of registered seat and identification number of entity, who has

participated on evaluating compliance,gg) date of issuing the declaration of compliance, name and position of the

responsible person.

(3) The manufacturer, importer or a person introducing the product on the market issues a new declaration of compliance, if there is a change in information, which can have an impact on product properties from the point of view of nuclear safety or radiation protection, and the product is to be launched on the market even following this change.

(4) For sources of ionising radiation for which compliance was evaluated according to another legal regulation3), manufacturer, importer or entity introducing the product on the market will state the product classification and the minimum extent of acceptance tests, test for long term stability and operational steadiness.

PART THREE

TRANSPORTATION OF SPECIFIED NUCLEAR MATERIALS AND RADIOACTIVE SUBSTANCES

Section 8

Transportation permit

(To Section 9 paragraph 1 letter m) of the Act)

Office permit is necessary for transportation of

a) fissile material, b) radioactive substances of special form with activity higher than 3.103 of A1 value and

radioactive substances other than of special form with activity higher than 3.103 of A2

value or radioactive substances with activity higher than 1000 TBq according to which one of the stated values is lower,

c) radioactive substances in packaging sets type B(M), which are not constructed for extent of temperatures from minus 40°C to plus 70°C or constructed in a way to allow sporadic controlled ventilation,

d) fissile materials and radioactive substances under special conditions,

e) fissile material or radioactive substances via a ship designer for such with specified method of securing radiation protection,

f) fissile material or radioactive substances, containing nuclides, A1 and A2 values of which are not stated in table 1(1) of Annex No. 3, were determined by calculation.

Section 9

Securing shipping and transport by the shipper

(To Section20 par 1 letter b) and d) of the Act)

(1) During transport of fissile materials and radioactive substances according to Section8 the shipper

a) announces start of transport to the Office 7 days ahead of time, unless specified otherwise according to another legal regulation8),

b) will document in writing that all cooperation in solving an exceptional situation with

third parties is ensured; if the accident guidelines specify cooperation with the fire departments in multiple regions, he will provide through the Ministry of Interior – general headquarters of the Fire Department of the Czech Republic,

c) will document in writing that all transport participants stated in the transport instructions were demonstrably introduced with the accident guidelines,

d) will ensure physical protection of transport according to other legal regulations9)10),

e) fulfills corresponding requirements stated in Annex No. 4 and requirements of other legal regulations11).

8) Decree No. 145/1997 Coll., on evidence and control of nuclear materials and on its detailed specification, as amended by Decree No. 316/2002 Coll.9) Decree No. 144/1997 Coll., on physical protection of nuclear materials and nuclear facilities and on their classification into individual categories, as amended by Decree No. 500/2005 Coll.10) Act No. 283/1991 Coll., on Police of the Czech Republic, as amended.11) For example Act No. 266/1994 Coll., on railways, as amended by later regulations, Decree of the government of the Czech Republic No. 1/2000 Coll., on railway transport code for public railway cargo transportation, as amended, Decree No. 8/1985 Coll., on Convention concerning International Carriage by Rail(COTIF), as amended , Decree No. 64/1987 Coll., on European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR), as amended, Act No. 111/1994 Coll., on road transportation, as amended, Act No. 114/1995 Sb., on domestic voyages, as amended, Decree No. 222/1995 Coll., on waterways, voyage operations in docks, common accident and transport of dangerous goods, as amended, Act No. 49/1997 Coll., on civil aviation, as amended, Decree No. 17/1966 Coll., on air transportation code, as amended.

PART FOUR

INTERNATIONAL TRANSPORT OF RADIOACTIVE WASTESection 10

Extent and method of performance of international transport of radioactive wastes, documentation for approval and overseeing this transport

(To Section 9 par 1 letter p) and to point P of Annex to the Act)

(1) Permit in accordance with Section 9 par 1 letter p) of the Act is required for international transport of radioactive waste or spent nuclear fuel

a) if their activity and mass activity exceeds the levels stated in table No. 1 of Annex No. 1 of another legal regulation5), and

b) if the state of origin, state of destination or the first state of transit within the European Union is the Czech Republic.

(2) Permit in accordance with Section 9 par 1 letter p) of the Act is not required for the transport of unused sources to their supplier or manufacturer or to a recognized warehouse, for transportation of radioactive materials obtained by reprocessing and intended for further use and for trans border transport of waste, which contains only naturally occurring radioactive substances. Furthermore the permit according to Section 9 par 1 letter p) is not required for transport of radioactive waste or spent nuclear fuel from a European Union Member State to the Czech Republic or for their transit over the Czech Republic, if the Czech Republic is not the first European Union state onto whose territory the radioactive wastes or spent nuclear fuels enter.

(3) The applicant for approval of radioactive waste or spent nuclear fuel transport will submit a properly completed application and other information to the Office in languages acceptable for the relevant stated authorities to which the transport is related. The Office will inform the applicant of the acceptable languages. A standard document, completed in sections A-1, A-4 and A-5 must be attached with the documents transported with the radioactive waste or, completed in sections B-1, B-4 and B-5, must be attached to documents transported with spent nuclear fuel in such a way that it is available for the relevant authorities in country of origin, country of destination and all countries of transit.

(4) One application for permit can be used to apply for multiple transport permits, if

a) radioactive waste or spent nuclear fuel has basically the same physical, chemical and radioactive characteristics,

b) transports are performed only between the holder and recipient and fall under the same relevant authorities,

c) the transports concern a state which is not a Member State of the European Union and are at the same time performed over the same European Union border crossings; the appropriate authorities can however decide otherwise.

Section 11

Transport within the European Union(To Section 9 par 1 letter p) and to point P of Annex to the Act)

(1) The holder of radioactive waste or spent nuclear fuel during international transport of radioactive waste or spent nuclear fuel from the Czech Republic to a European Union Member State

a) will submit to the Office a properly completed application for a permit to transport radioactive waste or spent nuclear fuel

b) will ensure the return of radioactive waste or spent nuclear fuel at own cost, if the transport cannot be completed or if the transport conditions are not in compliance with provisions of the Act, this Decree, or with other European Union legal regulations12), or international legal regulations on transport of radioactive substances and if no other safety measures can be taken; it will at the same time ensure that the shipper in case of a need accepts correctional safety measures.

(2) The Office during international transport of radioactive waste or spent nuclear fuel from the Czech Republic to a European Union Member State

a) will send a copy of the application completed according to par 1 letter a) to the relevant state of destination authorities, possibly to transit states which are European Union Member States,

b) will accept necessary measures to provide protection for all information concerning the transport against their abuse,

c) in the event that the relevant state authority that the transport concerns requests additional information, it shall ensure their submission in the shortest time possible,

d) will pass without delay a decision on permitting the international transport of radioactive waste or spent nuclear fuel following the receipt of confirmation of application acceptance and positive standpoints to the transport from the relevant authorities of all states that received a copy of the properly completed request according to par 1 letter a); if the Office does not receive a reply within a period of two months from the receipt of confirmation of application acceptance by the relevant authority or in a period of three months, if the relevant authority has asked for an additional time extension, it is deemed that the relevant authority agrees with the proposed transport,

e) in determining conditions for transport and the period for which the permit is issued, which can be at most 3 years, it takes into consideration the standpoints of the relevant

1212) Council Directive 94/55/EC of 21 November 1994 on the approximation of the laws of the Member States with regard to the transport of dangerous goods by road, Council Directive 96/49/EC of 23 July 1996 on the approximation of the laws of the Member States with regard to the transport of dangerous goods by rail , Directive 98/91/EC of the European Parliament and of the Council of 14 December 1998 relating to motor vehicles and their trailers intended for the transport of dangerous goods by road and amending Directive 70/156/EEC relating to the type approval of motor vehicles and their trailers, Council Directive 89/684/EEC of 21 December 1989 on vocational training for certain drivers of vehicles carrying dangerous goods by road. Council Directive on the appointment and vocational qualification of safety advisers for the transport of dangerous goods by road, rail and inland waterway.

authorities,

f) on issuance of permit for transport it informs all relevant authorities of states that the transport concerns,

g) it sends a copy of the announcement of acceptance of radioactive waste or spent nuclear fuel in the form of a completed section 6-A or 6-B of the standard document, which it has received from a relevant state of destination authority, holder of the radioactive waste or spent nuclear fuel,

h) it will report cases of unjustified delays or lack of cooperation from the side of the relevant authorities of another Member State to the European Commission,

i) the Office can decide that the transport cannot be completed if the conditions for transport are not in accordance with permits or agreements issued by relevant European Union Member State authorities, with provisions of the Act, this Decree, other legal regulations, with legal regulations of the European Union or international legal regulations, with legal regulations on transportation of radioactive substances and immediately report this to the relevant authorities of other states that the transport concerns.

Section 12

Transport from Czech Republic out of European Union(To Section 9 par 1 letter p) and to point P of Annex to Law)

(1) The holder of radioactive waste or spent nuclear fuel during international transport

of radioactive waste or spent nuclear fuel from the Czech Republic to a state that is not a member of the European Union, including transit through European Union Member States

a) will submit to the Office a properly completed application for a permit to transport radioactive waste or spent nuclear fuel,

b) will ensure the return of radioactive waste or spent nuclear fuel at own cost, if the transport cannot be completed or if the transport conditions are not in compliance with provisions of the Act, this Decree, or with other European Union legal regulations13) or international legal regulations on transport of radioactive substances and if no other safety measures can be taken; it will at the same time ensure that the shipper in case of need accepts correctional safety measures,

c) will ensure that the recipient immediately after the acceptance of radioactive waste or spent nuclear fuel sends a notification of acceptance of radioactive waste or spent nuclear fuel in the form of a completed section 6-A or 6-B of the standard document, or

1313) Council Directive 94/55/EC of 21 November 1994 on the approximation of the laws of the Member States with regard to the transport of dangerous goods by road, Council Directive 96/49/EC of 23 July 1996 on the approximation of the laws of the Member States with regard to the transport of dangerous goods by rail , Directive 98/91/EC of the European Parliament and of the Council of 14 December 1998 relating to motor vehicles and their trailers intended for the transport of dangerous goods by road and amending Directive 70/156/EEC relating to the type approval of motor vehicles and their trailers, Council Directive 89/684/EEC of 21 December 1989 on vocational training for certain drivers of vehicles carrying dangerous goods by road. Council Directive on the appointment and vocational qualification of safety advisers for the transport of dangerous goods by road, rail and inland waterway.

its own declaration of equal content and states the last customs office of the European Union through which the transport passed,

d) will send to the Office within 15 days of the handover of the radioactive waste or spent nuclear fuel a report completed by the recipient on acceptance of radioactive waste or spent nuclear fuel in the form of a completed section 6-A or 6-B of the standard document and will state the last customs office of European Union through which the transport passed; if the recipient does not use a standard document, it will be completed by the holder of the radioactive waste or spent nuclear fuel and it will document it by a statement of the recipient in accordance with letter c).

(2) The Office during international transport of radioactive waste or spent nuclear fuel from the Czech Republic to a non-European Union Member State including transit through European Union Member States

a) informs the relevant state authorities about the planned transport and will request their agreement and will send a copy of the application completed according to par 1 letter a) to the relevant transit Member State authorities in the European Union,

b) proceeds in accordance with Section 11 par 2 with exception of letters a) and g).

Section 13

Transportation to the Czech Republic from a state outside of the European Union(To Section 9 par 1 letter p) and to point P of Annex to the Act)

(1) The recipient of radioactive waste or spent nuclear fuel during international transport of radioactive waste or spent nuclear fuel from a state that is not a member of the European Union to the Czech Republic, including transit through European Union Member States,

a) will ensure that the holder of radioactive waste or spent nuclear fuel passes it the information necessary for the proper completion of the application for a permit to transport radioactive waste or spent nuclear fuel and will submit this application to the Office,

b) it will submit to the Office proof that it has ensured by contract that the holder of radioactive waste or spent nuclear fuel will ensure the return of radioactive waste or spent nuclear fuel at own cost if the transport cannot be completed or the conditions are not in compliance with provisions of the Act, this Decree, or with other European Union legal regulations or international legal regulations on transport of radioactive substances and if no other safety measures can be taken; this contract must be approved by relevant authorities of state of origin; at the same time the stated holder must ensure that the shipper accepts in case of need for correctional safety measures,

c) will send to the Office within 15 days from acceptance of the radioactive waste or spent nuclear fuel a report on acceptance of radioactive waste or spent nuclear fuel in the form of a completed section 6-A or 6-B of the standard document.

(2) The Office during international transport of radioactive waste or spent nuclear fuel from a state that is not a member of the European Union to the Czech Republic, including

transit through European Union Member States,

a) will send a copy of the application in accordance with paragraph 1 letter a) to the relevant transit state authorities in the European Union,

b) proceeds in accordance with Section 11 par 2 with the exception of letters a) and g).

c) sends a copy of the report on acceptance of radioactive waste or spent nuclear fuel in the form of completed section 6-A or 6-B of the standard document to the relevant authorities of all states through which the transport has passed.

Section 14

Transit(To Section 9 par 1 letter p) and to point P of Annex to Law)

(1) The entity responsible for performance of transport on the territory of the Czech Republic during international transport of radioactive waste or spent nuclear fuel from a non European Member State to the Czech Republic, with transit through European Union Member States, while the Czech Republic is the first European Union Member State on the territory of which the radioactive waste or spent nuclear fuel is entering,

a) will ensure that the holder of radioactive waste or spent nuclear fuel hands over a properly completed application for a permit to transport radioactive waste or spent nuclear fuel and will submit this application to the Office,

b) will submit to the Office proof that it has ensured by contract that the holder of radioactive waste or spent nuclear fuel will ensure the return of such radioactive waste or spent nuclear fuel at own cost if the transport cannot be completed or the conditions are not in compliance with provisions of the Act, this Decree, or with other European Union legal regulations or international legal regulations on transport of radioactive substances and if no other safety measures can be taken; this contract must be approved by relevant authorities of the state of origin; at the same time the stated holder must ensure that the shipper accepts in case of need correctional safety measures,

(2) The permit holder

a) will ensure that the recipient immediately following the acceptance of radioactive waste or spent nuclear fuel sends him a declaration that the radioactive waste or spent nuclear fuel have reached their destination where he will state the last customs office of a non-European Union Member State through which the transport has passed,

b) will send to the Office within 15 days from handover of the radioactive waste or spent nuclear fuel a report to the recipient that the radioactive waste or spent nuclear fuel have reached their destination where it will state the last customs office within the European Union territory through which the transport passed and recipient declaration in accordance with par 2 letter a),

(3) The Office during international transport of radioactive waste or spent nuclear fuel

between non-European Union Member States with a transit through European Union Member States, while the Czech Republic is the first European Union Member State on the territory of which the radioactive waste or spent nuclear fuel is entering

a) will send a copy of the application according to paragraph 1 letter a) to relevant authorities of transit states in the European Union

b) proceeds in accordance with Section 11 par 2 with exception of letters a) and g).

Section 15(To Section 9 par 1 letter p) and to point P of Annex to the Act)

Transit not requiring Office permit

(1) Transport of radioactive waste or spent nuclear fuel for which the Office permit is not required

a) and during which the Czech Republic is a transit state, but not the first European Union Member State through which the radioactive waste or spent nuclear fuel is entering the European Union, the Office1. within 20 days of the delivery of an application and agreement with transport of

radioactive waste or spent nuclear fuel from the relevant membership state authorities permitting the transport, it will verify whether the application is properly completed and will possibly ask to fill in the missing information, if necessary; it will also inform the other relevant authorities of the fact that it has requested additional completion of the application, while it will accept necessary measures to protect all information relative to the transport against unauthorized use,

2. will send a copy of the acceptance of the application to the relevant membership state authorities, which permit transport no later than 10 days following the delivery of the missing information and no earlier than following the expiration of the 20 day period determined in point 1; the period determined according to point 1 and 2 can be shortened, if the application is completed properly,

3. within 2 months from the issuance of confirmation of application acceptance it will announce to the relevant membership state authorities, which permit the transport, its agreement or conditions for the intended transport and it will state the reasons leading it to set such conditions attached to the granted agreement or to reject the agreement, which must be in compliance with provisions of the Act, this Decree, other legal regulations, European Union legal regulations or international legal regulations on transport of radioactive substances,

4. can ask the relevant membership state of origin authority to extend the period according to point 2 however by no more than a month,

5. if it does not issue a statement in accordance with point 3 or 4 it is deemed that it agrees with the transport,

6. grants an agreement with the return transport of radioactive waste or spent nuclear fuel, if it has already previously granted an agreement with transit transportation in the event that the previous agreement was granted for the purpose of processing or reprocessing, if this regards a return transit of radioactive waste or other products corresponding with the original material following the processing or reprocessing and if all related legal regulations were observed and if the state of destination, origin or transit decides that the transport cannot be completed and if the return transport is realized under the same conditions and with same specifications,

b) and if this regards a transport of radioactive waste or spent nuclear fuel from a European Union Member State to the Czech Republic,1. the recipient of radioactive waste will send to the Office within 15 days from

acceptance of the radioactive waste a report on acceptance of radioactive waste or spent nuclear fuel in the form of a completed section 6-A or 6-B of the standard document,

2. the Office proceeds in accordance with letter a) of this paragraph and following the delivery of the report on acceptance of radioactive waste or spent nuclear fuel in accordance with point 1, it will send a copy of it to the relevant state authorities through which the transport has passed.

(2) The Office can decided that the transport cannot be completed if the transport conditions are already not in accordance with provisions of the Act, this Decree, with other legal regulations, with European Union regulations or international legal regulations on transport of radioactive substances and immediately informs the relevant state authorities through which the transport has passed.

PART FIVE

FINAL PROVISIONS

Section 16

Common and temporary provisions

(1) Products stated in Section3 par 1 of the approved existing legal regulations is deemed as type approved in accordance with this Decree; the period of validity of the decision on type approval is not influenced by this Decree.

(2) Proceedings on type approval and on transport permit in accordance with Section 9 par 1 letter p) of the Act held by the Office, initiated before the day of effectiveness of this Decree and not lawfully completed on the day this Decree comes into effect, will be completed and the rights and obligations derived therefrom will be evaluated according to existing regulations.

(3) In order to decide on applications and permits not lawfully completed before 25 December 2008, for more than one transport of radioactive waste or spent nuclear fuel to destination states outside of the European Union it will take into consideration all relevant circumstances, especially

a) presumed time schedule for realization of all transports pertaining to one application b) justification for including all transports into a single application,c) suitability of granting a permit for a lower number of transports than the number stated

in the application.

Section 17

Cancellation provision

Decree No. 317/2002 Coll., on type approval of packaging sets for transportation,

storage and disposal of nuclear materials and radioactive substances, on type approval of ionization radiation sources and on transportation of nuclear materials and specified radioactive substances (on type approval and transport) is cancelled.

Section 18

Effectiveness

This Decree comes into effect on 1 July 2008.

Chairwoman:

Ing. Drábová executive director

Annex No. 1 to Decree No. …………Coll.

Requirements and type approval testing procedures

PART I

REQUIREMENTS ON FISSILE MATERIALS, PACKAGING SETS AND RADIOACTIVE SHIPMENTS

REQUIREMENTS ON FISSILE MATERIALS Requirements on radioactive substance with a low mass activity of group LSA III

1. (601.) ) Radioactive substance of group LSA III must be a solid substance of such nature that following the exposure of the complete content of a packaging set to a test, stated in point 3 part II of Annex No. 1, the activity in water will not exceed 0.1 A2

value.

Requirements on radioactive substance of special form

2. (602.) Radioactive substance of special form must have at least one dimension greater than 5 mm.

3. (603.) Radioactive substance of special form must be at least of such nature or be manufactured in such a way that following the performance of tests in accordance with points 4. – 11. of part II of Annex No. 1 it complies with the following requirements:

(a) does not crack or crumble during test for impact, pressure and flexing according to points, 5., 6., 7. and 9. (a) of part II of Annex No. 1,

(b) does not melt or disperse during thermal tests specified in point 8. or p. (b) of part

II of Annex No. 1,

(c) water activity during determination of eluability in accordance with points 10. and 11. of part II of Annex No. 1 does not exceed 2 kBq, or with closed radiators the speed of the volume leak during a test evaluating a value leak, specified in publication of International Organization for Standardization: “Radiation protection – closed radioactive radiators – methods for testing leakage, ISO 9987:1992 E, ISO, Geneva, 1992”, complies with relevant specified criteria approved by the Office.

4. (604.) If part of the radioactive substance of special form is a hermetical envelope, it must be manufactured in a way that it can be opened only by destruction.

Requirements on radioactive substance with low dispersibility) Note:Position numbers printed in parentheses next to point numbers, possibly tables and images correspond to numbering in recommendation by the International Atomic Energy Agency, “IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, Safety Requirements, International Atomic Energy Agency, Vienna, 2005”.

5. (605.) Radioactive substance with low dispersibility must be of such nature in order for the total quantity of this radioactive substance in the shipment to comply with the following requirements:

(a) value input of batch equivalent in the distance of 3 m from unshielded radioactive substance cannot exceed a value of 10 mSv/hour,

(b) following the performance of tests specified in points 36. and 37. of part II of

Annex No. 1, the activity of released aerosols in the form of gaseous or solid particles exceed, up to aerodynamic equivalent in the average of 100 m, a value of 100 A2, for each test a different sample may be used,

(c) following the performance of a test in accordance with point 3. of part II of Annex

No. 1, activity in water cannot exceed 100 A2. Damage caused by tests stated in point (b) cannot be taken into consideration during this test.

General requirements on all packaging sets and radioactive shipments

6. (606.) Radioactive shipment must be manufactured in a way that it can be easily and safely transported with regards to mass, volume and shape. On top of this it also must be manufactured in a way that it can be properly secured in the transportation vessel.

7. (607.) Construction type of radioactive shipment must ensure that any fastening

equipment on the packaging set works, if it is used in a way that is prescribed by the manufacturer and that in the event of a breakdown of this equipment the radioactive shipment complies with other requirements set by this Decree. Construction type must comply with relevant safety factors for the event that the radioactive shipment is lifted by jerk.

8. (608.) Fastening equipment and any other clamps on the external surface of the radioactive shipment, which can be used to lift it, must be manufactured in a way that they hold its mass in compliance with requirements of point 12. part I of Annex No. 1, otherwise they must be removed, or differently prevented from being functional for the duration of transport.

9. (609.) Packaging set must be manufactured without parts of the external surface being salient so that it can be easily decontaminated, if this would not limit a more significant safety requirement.

10. (610.) The external surface of the radioactive shipment must be manufactured in such a

way that water does not condense or stick on it, if this would not limit a more significant safety requirement.

11. (611.) Any equipment transported with a radioactive shipment, which is not its component, cannot lower its safety.

12. (612.) A radioactive shipment must be able to resist influences of acceleration, vibration or resonances from vibrations, which can arise as a result of conditions predictable under common transportation conditions, the Effectiveness of closing equipment on radioactive shipment containers cannot be lowered or there cannot be a breach in the integrity of itself as a unit. Especially nuts, pins and other securing equipment must be manufactured in such a way that their unintentional loosening or loss is prevented even in repeated use.

13. (613.) Packaging set materials and any of its parts must be mutually, even relative to

radioactive content, physically and chemically compatible. Physical and chemical compatibility must be preserved with all material, even following irradiation.

14. (614.) All closings through which radioactive content can leak must be secured before uncontrolled unauthorized use.

15. (615.) Construction of a radioactive shipment must accommodate temperatures and

pressures of the external environment, which can occur during common transportation conditions.

16. (616.) For fissile materials or radioactive substances that display other hazardous

properties, the construction type must accommodate these hazardous properties as well, see point 7 of Annex No. 4.

Additional requirements on radioactive air transported shipments

17. (617.) The temperature of accessible radioactive surfaces on air transported shipments may not exceed 50ºC under surrounding temperature of 38ºC, while sun irradiation is not taken into consideration.

18. (618.) Radioactive air transported shipments must be manufactured in such a way that in

case of exposure to temperatures of minus 40ºC to 55ºC the integrity of the containment (hereafter only as retaining) system is not violated. The arrangement of the packaging system parts designed and described by the designer must prevent leakage of fissile material or radioactive substance during transport.

19. (619.) Radioactive shipments containing radioactive substances intended for air transport must be able to withstand internal pressure corresponding to at least the pressure difference created by a sum of the maximum normal operational pressure and pressure 95 kPa.

Requirements on excluded shipments

20. (620.) Excluded shipments must be produced in such a way that they comply with requirements specified in points 6. – 16. of part I of Annex No. 1, and furthermore compliance in accordance with 17. – 19. of part I of Annex No. 1, if they are air transported.

Requirements on industrial shipments

Requirements on type IP-1

21. (621.) Type IP-1 must be manufactured in order to comply with requirements in points 6. – 16. of part I of Annex No. 1 and furthermore requirements in points 17. – 19. of part I of Annex No. 1, if it is air transported.


22. (622.) Type IP-2 must be manufactured in order to comply with requirements on type IP-1, specified in point 21. of part I of Annex No. 1 and furthermore, if it is examined according to points 22. and 23. of part II of Annex No. 1, it has to prevent

(a) loss or dispersion of radioactive content and

(b) loss of shielding efficiency, which would cause more than 20% growth in input of batch equivalent in any place on the external surface.


23. (623.) Type IP-3 must be manufactured in order to comply with requirements on type IP-1, specified in point 21. of part I of Annex No. 1 and furthermore, if it is examined according to points 34. - 47. of part I of Annex No. 1, it has to prevent.

Alternative requirements on type IP-2 and type IP-3

24. (624.) Radioactive shipments can be used as type IP-2 and type IP-3 under the presumption that:

(a) they comply with requirements of type IP-1, specified in point 21. of part I of Annex No. 1,

(b) they are manufactured to comply with standards prescribed in chapter General

Recommendations for Packaging in the UN publication “United Nations Recommendations on the Transport of Dangerous Goods, ninth revised edition, ST/SG/AC. 10/1/Rev. 9, UN, New York and Geneva, 1995" or other standards at least equal to these and

(c) following the performance of tests for packaging group I and II according to chapter General Recommendations for Packaging in the UN publication “United Nations Recommendations on the Transport of Dangerous Goods, ninth revised edition, ST/SG/AC. 10/1/Rev. 9, UN, New York and Geneva, 1995”, must prevent:(i) loss and dispersion of radioactive content and (ii) loss of shield efficiency, which would cause more than 20% growth of input

of batch equivalent at any point on its external surface. 25. (625.) Such tanker containers can be used as type IP-2 and type IP-3 under the

presumption that:

(a) they comply with requirements of type IP-1, specified in point 21. of part I of Annex No. 1,

(b) they are manufactured to comply with standards prescribed in chapter Recommendations for Multimodal Tanker Transportation in the UN publication “United Nations Recommendations on the Transport of Dangerous Goods, ninth revised edition, ST/SG/AC. 10/1/Rev. 9, UN, New York and Geneva, 1995” or other equal standards and must be able to withstand a test pressure 265 kPa and

(c) are manufactured in a way that each additional shielding they are equipped with will be able to withstand static and dynamic tensions resulting from manipulation under common transport conditions and will prevent the loss of shielding abilities leading to a greater than 20% growth of input of batch equivalent at any point on its external surface of used tanker container.

26. (626.) Tankers, other than tanker containers can be used as type IP-2 and type IP-3 for

transport LSA I and LSA II in the form of gas or liquid, as is prescribed in table 1 (4.) in Annex No. 4 under the presumption that they comply with equivalent standards, which are stated in point 25. of part I of Annex No. 1.

27. (627.) Transport containers can be used as type IP-2 and type IP-3, under the presumption that:

(a) radioactive content will be limited to solid substances; (b) it fulfills requirements on type IP-1 specified in point 21. of part I of Annex No. 1

and

(c) they are manufactured in order to satisfy standards prescribed in the document of the International Organization for Standardization: “Series 1 freight containers -- Specification and testing -- Part 1: General cargo containers for general purposes, ISO1496/1, 1990 E, ISO, Geneva, 1990“, with the exception of dimensions. They must be produced in such a way that following the performance of tests prescribed in the cited document and under accelerations corresponding to common transportation conditions prevented:(i) loss and dispersion of radioactive content and (ii) loss of shield efficiency, which would cause more than 20% growth of input

of batch equivalent at any point on external surface of freight container.

28. (628.) Middle size metal containers for loosely placed cargo can be used as type IP-2 and type IP-3, if:

(a) they fulfill requirements on type IP-1 specified in point 21. of part I of Annex No. 1

(b) they are manufactured in order to satisfy standards prescribed in the chapter on

Recommendations on mid-size containers, for packaging group I and II, in the UN publication “United Nations Recommendations on the Transport of Dangerous Goods, ninth revised edition, ST/SG/AC. 10/1/Rev. 9, UN, New York and Geneva, 1995” and following the performance of tests prescribed in the cited document with the exception of a free fall test performed in the most harmful manner will prevent:(i) loss and dispersion of radioactive content and (ii) loss of shield efficiency, which would cause more than 20% growth of input

of batch equivalent at any point on external surface of freight container

Requirements on a radioactive shipment containing uranium hexafluoride

29. (629.) With the exception permitted in point 32. of part I of Annex No. 1, uranium hexafluoride must be packed and transported in accordance with the document of the International Organization for Standardization: “Packaging of uranium hexafluoride (UF6) for transport ISO 7195:1993, E, ISO, Geneva, 1993”, and with requirements of points 30. - 31. of part I of Annex No. 1. A radioactive shipment must also comply with requirements related to radioactive and fissile properties of this substance.

30. (630.) Each radioactive shipment designed for content of 0.1kg or more of uranium hexafluoride must be manufactured in such a way to comply with the following requirements:

(a) satisfy the test of unacceptable burden without a leak, according to the specification included in the document of the International Organization for Standardization: “Packaging of uranium hexafluoride (UF6) for transport ISO 7195:1993, E, ISO, Geneva, 1993”, static test specified in point 18. of part II of Annex No. 1,

(b) satisfy the test specified in point 22. of part II of Annex No. 1 without loss or dispersion of uranium hexafluoride,

(c) satisfy the test specified in point 28. of part II of Annex No. 1 without a rupture of the retaining system.

31. (631.) A radioactive shipment designed for content of 0.1kg or more of uranium

hexafluoride may not be equipped with pressure lowering devices.

32. (632.) A radioactive shipment designed for content of 0.1kg or more of uranium hexafluoride can be transported only following approval by the Office, if it is designed:

(a) according to other requirements than the requirements of the International Organization for Standardization: “Packaging of uranium hexafluoride (UF6) for transport ISO 7195:1993, E, ISO, Geneva, 1993”, under the presumption that the same level of nuclear safety and radiation protection are guaranteed,

(b) to satisfy the test of unacceptable burden with a testing pressure of up to 2.76 MPa without a leak according to point 18. of part II of Annex No. 1, or

(c) for content of 9000kg or more of uranium hexafluoride and at the same time it

does not comply with requirements according to point 30 (c) of part I of Annex No. 1.

Requirements on radioactive shipments type A33. (633.) Radioactive shipment type A must be manufactured in a way to comply with

requirements specified in points 6. - 16. of part I of Annex No. 1, for the case of air transport also requirements in accordance with points 17. – 19. and points 34. – 49. of part I of Annex No. 1.

34. (634.) The smallest external dimension of a radioactive shipment cannot be less than 10cm.

35. (635.) External closure of a radioactive shipment must contain a device enabling to affix a plug or a seal, which is not easily violable and which, if not violated, is proof that the radioactive shipment was not opened.

36. (636.) Any radioactive shipment clamps must be produced in such a way that the forces

created in these clamps under normal transport conditions and even accident conditions during transport do not disrupt the ability of the radioactive shipment to suit the set requirements.

37. (637.) Construction type of radioactive shipment for individual components of a packaging set must accommodate being subjected to temperatures ranging from minus 40ºC to plus 70ºC. Special attention must be paid to low temperatures in the case of liquid contents and potential impairment of packaging materials in the given temperature span.

38. (638.) Construction type and technology of material processing and production of

packaging set must comply with ensuring quality according to another legal regulation or international standards acceptable to the Office.

39. (639.) Construction type must contain a safely sealable retaining system, which cannot

be opened incidentally or as a result of pressure, which can be created in a radioactive shipment.

40. (640.) A radioactive substance of special form can be considered a part of the retaining system.

41. (641.) If the retaining system forms a special unit of radioactive shipment, it must be safely sealable by a mechanism independent of any part of the radioactive shipment.

42. (642.) Design project of any part of the retaining system must take into account, if possible, radiolytic decay of liquids and other unstable substances and the creation of gas through a chemical reaction and radiolysis.

43. (643.) The retaining system must hold the radioactive content during the drop of external pressure to 60 kPa.

44. (644.) All valves, with the exception of safety, must be equipped with a cap, which will

prevent any kind of leak. 45. (645.) Shielding, which surrounds part of the radioactive shipment specified as part of

the retaining system, must be manufactured in such a way that it prevents undesirable leaks of this part from the shielded area. If a radiation shielding and such part inside of it form a special unit, this unit must be safely sealable by a closing mechanism independent of any other arbitrary part of the packaging set.

46. (646.) Radioactive shipment must be manufactured in a way that following the performance of tests in points 19. – 24. of part II of Annex No. 1, it prevents:

(a) loss and dispersion of radioactive content and (b) loss of shield efficiency, which would cause more than 20% growth of input of batch equivalent at any point on external surface of freight container.

47. (647.) Construction type of radioactive shipment intended for liquid fissile materials or radioactive substances must, with its construction, respect all changes in content volume and free space in packaging set depending on temperature changes, dynamic occurrences and dynamics of filling.

48. (648.) Radioactive shipment type A, designed for liquids must in addition:

(a) comply with conditions stated in point 46 (a) of part I of Annex No. 1 following the performance of tests specified in point 25. of part II of Annex No. 1 and furthermore it must:

(i) contain sufficient absorption material, which absorbs at least a double volume of liquid radioactive content and this absorption material must be suitably arranged in order for it to be in contact with the liquid in case of its leak, or

(ii) have installed a retaining system composed of primary internal and secondary external parts, which are manufactured in such a way to provide retention of liquid content inside a secondary external part even in the case that the primary internal part has a leak.

49. (649.) Radioactive shipment type A, designed for gases, must prevent loss or dispersion of radioactive content during a test performed in accordance with point 25. of part II of Annex No. I. Radioactive shipment type A, designed for gaseous tritium or for rare gases, does not have to comply with this requirement.

Requirements on radioactive shipments type B (U)

50. (650.) Radioactive shipment type B must be manufactured in such a way to comply with requirements specified in points 6. - 16. of part I of Annex No. 1, for the case of air transport also requirements in accordance with points 17. – 19. and points 34. – 49. of part I of Annex No. 1, with the exception of requirements in point 46. (a) of part I of Annex No. 1 and also requirements in points 51. – 64. of part I of Annex No. 1.

51. (651.) Radioactive shipment must be manufactured in such a way that the heat produced inside the radioactive shipment during external conditions specified in points 53. and 54. of part I of Annex No. 1 and under normal transport conditions, specified in points 19. – 24. of part II of Annex No. 1, did not have such a negative impact on radioactive shipment that it would not comply with requirements on a retaining system and shielding if left without supervision for one week. Special attention must be paid to heat impacts, which can:

(a) change the arrangement, geometrical shape or physical state of radioactive content, or if the fissile material or a radioactive is sealed in a package or a container (e.g. fuel covers) cause a deformation of this container or package or directly the radioactive content or to melt these, or

(b) decrease the efficiency of the set through a differential thermal expansion or cracking or melting of the shielding material, or

(c) speed up corrosion in combination with humidity.

52. (652.) Radioactive shipment must be produced in a way that during external conditions

specified in point 54. of part I of Annex No. 1 and if it is not exposed to irradiation from the sun maximum temperature on any part of the easily accessible surface of the radioactive shipment would not exceed 50°C, with the exception of radioactive shipment transport under conditions of exclusive use.

53. (653.) With the exception of the requirement according to point 17 of part I of Annex No. 1 on air transported radioactive shipments, maximum temperature of any part of the easily accessible radioactive shipment’s surface transported under conditions of exclusive use and if not exposed to irradiation by the sun under external conditions specified in point 54. of part I of Annex No. 1 may not exceed 85°C. To protect transportation workers it is possible to take into account barriers or walls, while these barriers or walls do not have to be tested

54. (654.) External (surrounding) temperature is deemed to be 38°C.

55. (655.) Conditions for exposure to sun irradiation and its values intended to be used are described and determined in table 1. (11.) of Annex No. 1 to this Decree.

Table 1. (11.) Sun irradiation values

Case Shape and placement of surfaces Sun irradiation for a period of 12 hours per day (W/m2)

1 Flat surfaces transported horizontally–turned face down 02 Flat surfaces transported horizontally–turned face up 8003 Surfaces transported vertically 200a)

4 Other surfaces turned face down (not horizontal) 200a)

5 All other surfaces 400a)

a) Alternatively the sinus function along with accepted absorption coefficient can be used for calculation and possible effect of reflection from surfaces of neighboring objects can be neglected. 56. (656.) Radioactive substances, part of which is thermal protection, intended to comply

with requirements stated in point 28. of part II of Annex No. 1, must be designed in such a way that this protection is effective even following the performance of tests specified in points 19. – 24. and 27. (a) or 27 (b) and 27 (c) of part II. of Annex No. 1; no such protection of the external surface of radioactive shipment can be eliminated from activity by puncture, cutting, dragging, abrasion or abusive handling.

57. (657.) Radioactive shipment must be manufactured in a way to satisfy:

a) tests described in points 19. – 24. of part II of Annex No. 1 and reduces the loss of radioactive content to at most 10-6 A2 per hour and

b) tests described in points 26., 27. (b), 28. and 29. of part II of Annex No. 1 and also tests:

(i) stated in point 27. (c) of part II of Annex No. 1, if the mass of the radioactive shipment is at most 500kg and total density determined based on external dimensions is at most 1000kg/m3 and the activity value of radioactive content

is greater than 1000 A2, however not in the case of radioactive substance of special form, or

(ii) stated in point 27. (a) of part II of Annex No. 1 for all other radioactive shipments.

(c) the following requirements:

(i) to preserve sufficient shielding ensuring input of batch equivalent at a distance of 1 m from the surface of the packaging set less than 10 mSv/h under a maximum radioactive content, for which the radioactive shipment is designed,

(ii) to reduce the total loss of radioactive content per week to at most 10 A2 for crypton-85 and at most A2 for all other radionuclides.

NoteIf this regards a mixture of various radionuclides, the provisions in points 4. – 6. of Annex No. 3 with the exception of crypton-85 must be applied and here it is possible to use effective values A2(i) equal to 10 A2. For case (a) stated above, non-fixed surface contaminations on external surfaces stated in point 8 of Annex No. 4 must be also taken into consideration.

58. (658.) Radioactive shipment designed for the transport of radioactive content with activity higher than 10E5 A2 must be manufactured in a way that during an expanded test by submersion into water stated in point 30. of part II of Annex No. 1 no rupture of the retaining system occurs.

59. (659.) Compliance with the permissible range of activity leaks cannot be dependent on

filters nor on a mechanical cooling system.

60. (660.) Radioactive shipment in a retaining system cannot include a safety pressure system, which under testing conditions stated in points 19. - 24. and 26. - 29. of part II of Annex No. 1 will enable a leak of radionuclides into the surrounding environment.

61. (661.) Radioactive shipment must be manufactured in such a way that even in the event

of maximum normal operational pressure during performance of tests stated in points 19. - 24. and 26. - 29. of part II of Annex No. 1 that tension in the retaining system does not achieve values which would have such an impact on the radioactive shipment that it would not comply with the requirements necessary.

62. (662.) Radioactive shipment cannot have a normal operational pressure greater than 700 kPa.

63. (663.) Radioactive shipment containing radioactive substance with low dispersibility

must be designed in such a way that no devices connected to radioactive substance with low dispersibility, which are not its parts, or any other components of the packaging set cannot have a negative impact on the radioactive substance with low dispersibility.

64. (664.) Radioactive shipment must be manufactured for the range of surrounding temperatures from minus 40ºC to plus 38ºC.

Requirements on radioactive shipments type B (M)65. (665.) Radioactive shipment type B(M) must comply with the requirements on

radioactive shipments type B (U) stated in point 50. of part I of Annex No. 1 with the exception of requirements on radioactive shipments intended for transport exclusively inside the Czech Republic or between the Czech Republic and certain states, if the Office, or more precisely the Office and relevant competent authorities of these states, agree with the change in requirements in comparison to those, which are stated in points 37., 53. - 55. and 58. - 64. of part I of Annex No. 1. Requirements on shipments type B(U) stated in points 53. and 58. - 64. of part I of Annex No. 1 are to be satisfied if technically feasible.

66. (666.) Periodical ventilation radioactive shipments type B (U) is possible if permitted by the Office, or more precisely the relevant competent authorities.

Requirements on radioactive shipments type C

67. (667.) Radioactive shipment type C must be manufactured in such a way that it complies with requirements specified in points 6. - 19., points 34. - 47. with the exception of requirements in point 46. (a) and requirements of points 51. – 55 and 59. – 64. and additionally requirements of points 68. - 70. of part I of Annex No. 1.

68. (668.) Radioactive shipment type C following a thermal test performed in an

environment with a defined heat conductivity of 0.33 W/m.K) and heat of 38°C in a stable state must, with its construction, satisfy the evaluation criteria prescribed for tests in points 57. (b) and 61. of part I of Annex No. 1. The initial condition for evaluation must stem from the presumption that any thermal insulation of a radioactive shipment remains unaffected and radioactive shipment is used at a maximum normal operational pressure and surround temperature of 38ºC.

69. (669.) Radioactive shipment type C must be manufactured in a way that under

maximum normal operational pressure it satisfies: (a) the tests specified in points 19. - 24. of part II of Annex No. 1, while it reduces the

loss of radioactive content to less than 10-6 A2 per hour,

(b) gradually the tests specified in point 34. of part II of Annex No. 1, while:(i) its shielding must ensure input of batch equivalent at a distance of 1 m from

the surface of the radioactive shipment in order for it not to exceed 10 mSv/h under a maximum radioactive content, for which the radioactive shipment is designed,

(ii) it must reduce the total accumulated loss of radioactive content for a period of one week to less than 10 A2 for crypton-85 and A2 for all other radionuclides.

NoteIf this regards a mixture of various radionuclides, the provisions in points 4. – 6. of Annex No. 3 with the exception of crypton-85 must be applied and here it is possible to use effective values A2(i) equal to 10 A2. For case (a) stated above, contaminations on external surfaces stated in point 8 of Annex No. 4 must be also taken into consideration.

70. (670.) Radioactive shipment type C must be manufactured in such a way that following an expanded test by submersion into water stated in point 30. of part II of Annex No. 1 no rupture of the retaining system occurs.

Requirements on radioactive shipments containing fissile materials

71. (671.) Fissile materials must be transported in such a way that:

(a) the sub critical status during the course of the conditions of common transport even under accident conditions, and in order to sustain a sub critical state especially the following factors must be considered:

(i) water penetrating into radioactive shipment or leaking from it,

(ii) loss of efficiency of all built-in neutron absorbers or moderators,

(iii) change in geometrical arrangement of content either inside a radioactive shipment or as a result of a loss of part or the entireradioactive shipment content,

(iv) shrinking of spacing gaps between radioactive shipments or inside a radioactive shipment,

(v) radioactive shipments submersing into water or falling through snow and

(vi) temperature changes;

(b) and furthermore that these requirements are fulfilled::

(i) point 34. of part I of Annex No. 1 for fissile materials contained in radioactive shipments,

(ii) relative to radioactive properties of fissile material, prescribed anywhere in this Decree and

(iii) specified in points 73. – 82. of part I of Annex No. 1, if not excluded in accordance with point 72. of part I of Annex No. 1

Exceptions from requirements on radioactive shipments containing fissile materials

72. (672.) Fissile material compliant with one of the conditions stated in (a) – (d) of this point is excluded from the requirement to be stored or transported in a radioactive shipment fulfilling requirements of points 73. – 82. of part I of Annex No. 1 just as from other requirements related to fissile material. Only a single exclusion may be applied as part of a single delivery.

(a) Delivery may not contain beryllium nor deuterium in quantities exceeding 1% of the appropriate mass limit stated in table 2. (12.) of Annex No. 1 hereto, with the exception of deuterium naturally occurring in hydrogen. Mass limit for delivery is set by the below stated equation:

Mass of uranium - 235 (g) +mass of other fissile materials (g) ------------------------------- --------------------------------------------------- <= 1, X Ywhere X and Y are mass limits defined in table 2. (12.), under the presumption that

the smallest external dimension of every radioactive shipment is not less than 10cm and additionally:

(i) each individual radioactive shipment contains at most 15 g of fissile material; this mass limit is applied to delivery of unpacked material on a single transportation vehicle, or

(ii) fissile materials are homogenous water solutions or their mixtures, where the ratio of fissile nuclides to hydrogen is less than 5% mass, or

(iii) at most 5 g of fissile material is contained in an arbitrary ten liter volume.

(b) enriched uranium to 1 mass % of uranium-235 and with a total plutonium content and uranium-233 not exceeding 1 mass % of uranium-235 under the presumption that the fissile material is spread out fully homogenously in the entire volume. Furthermore, if uranium-235 is in the form of metal, oxide or carbide, it may not be arranged in lattice,

(c) liquid solutions of uranyl nitrate with enriched uranium to a maximum of 2 mass % of uranium-235, while the total content of plutonium and uranium-233 cannot exceed 0.002% of uranium mass and minimum ratio number of nitrogen atoms to uranium atoms (N/U) must be 2,

(d) radioactive shipment individually containing plutonium with a total mass no greater than 1kg, while no more than 20% of the plutonium mass may be formed by PU-239, Pu-241 isotopes or any combination of these radionuclides.

Table 2.(12.) Mass limits on delivery following exclusion from requirements on radioactive shipments containing fissile materials

Fissile material Mass of fissile material (g) mixed with substances having an average density of hydrogen atoms lower than or equal to the density of hydrogen atoms in water

Mass of fissile material (g) mixed with substances having an average density of hydrogen atoms higher than density of hydrogen atoms in water

Uran–235 (X)Other fissile materials (Y)

400

250

290

180

Specification of contents for evaluation of radioactive shipments containing fissile materials

73. (673.) Evaluation according to points 77. - 82. of part I of Annex No. 1 with a default presumption that each parameter whose value is not known has such value, which leads to maximum multiplication of neutrons corresponding to the conditions and parameters known in these evaluations must be performed if the chemical or physical form, isotopic composition, mass or concentration, slow down ratio or density, geometrical configuration are not known.

74. (674.) For irradiated fuel the evaluation of points 77. - 82 of part I of Annex No. 1 must be based on proven isotopic composition while considering:

(a) maximum multiplication of neutrons during the course of the irradiation, or

(b) conservative estimate of multiplication for evaluation of radioactive shipment. Following an irradiation, but before transportation, the measurements to confirm the conservative estimate of isotopic content must be performed.

Requirements on geometrical arrangement and temperature

75. (675.) Packaging set, following the performance of tests specified in points 19. – 24. of part II of Annex No. 1, may not permit an insertion of a cube with 10cm sides.

76. (676.) Radioactive shipment must be manufactured for a temperature range of minus

40ºC to plus 38ºC, unless otherwise specified by the Office in its decision on type approval.

Evaluation of individual radioactive shipment

77. (677.) In evaluating individual radioactive shipments the initial presumption must be that water can penetrate into all free spaces of the radioactive shipment including those located inside the retaining system and also to leak out of these. If the construction type includes special resources to prevent such water penetration into certain free spaces or the leaking out of water from these spaces and this even due to the fault of the service personnel, then it is possible to presume that water does not penetrate the stated spaces or leak out of them. Special resources are:

(a) multiple, highly effective barriers against water, while each one of them should remain water resistant even in the case that the radioactive shipment is subjected to tests in accordance with point 82. (b) of part I of Annex No. 1. Quality control during production and maintenance and repairs of the packaging set can be considered as special resources as well as the results of the test for proving seal tightness of each radioactive shipment before every transport,

(b) for radioactive shipments containing only uranium hexafluoride:

(i) tests according to point 82. (b) of part I of Annex No. 1, where there is no physical contact between the valve and any other part of the packaging set other than the original point of connection and where also following the performance of tests prescribed in point of part II of Annex No. 1 the valves remain sealed tight,

(ii) quality control during production and maintenance and repair of the packaging set and the results of the test for proving seal tightness of each radioactive shipment before every transport.

78. (678.) In evaluating individual radioactive shipments it must be presumed and assessed that there is a reflection caused by at least a 20cm water layer or a higher reflection, which can be additionally caused by surrounding material of the packaging set, in the immediate proximity of the confined (hereafter only limiting) system. If it is proven that the limiting system will remain inside the packaging set following the tests prescribed in point 82. (b) of part I of Annex No. 1, the caused reflection of neutrons caused by at least a 20cm water layer near the radioactive shipment can be considered in point 79. (c)

of part I of Annex No. 1, 79. (679.) Radioactive shipment must remain sub critical under the presumptions specified

in points 77. - 78. of part I of Annex No. 1, causing maximum neutron multiplication and under conditions corresponding to:

(a) common transport conditions (without accident), (b) tests specified in point 81. (b) of part I of Annex No. 1, (c) tests specified in point 82. (b) of part I of Annex No. 1.

80. (680.) For air transported radioactive shipments:

(a) radioactive shipment must be subcritical under the conditions in agreement with the test for type C according to point 34. of part II of Annex No. 1 herein and under presumption of a reflection caused by at least a 20cm water layer, but without the water penetrating inside, and

(b) in estimates according to point 79. of part I of Annex No. 1 herein no consideration can be given to special measures in accordance with point 77. of part I of Annex No. 1 herein, with the exception of a state where following tests for type C specified in point 34. and then in point 33. of part II of Annex No. 1 herein, the penetration of water inside the free spaces and water leaking out of them is prevented.

Evaluation of radioactive shipment sets under normal transport conditions

81. (681.) Number “N”, which is used to evaluate subcritical state of radioactive shipment set, is derived for the set five times “N” of radioactive shipments applies that they are in a subcritical state for the following arrangement, causing maximum multiplication of neutrons:

(a) nothing exists between radioactive shipments and the radioactive shipment set is from all sides exposed to the reflection of the water layer with at least a 20cm thickness, and

(b) radioactive shipments were tested, or their state following tests specified in points 19. - 24. of part II of Annex No. 1 is presumed and evaluated

Evaluation of radioactive shipment sets under transport accident conditions

82. (682.) Number “N” is derived that for the set two times “N” radioactive shipments applies that they are in a subcritical state for the following arrangement, causing maximum neutron multiplication:

(a) among radioactive shipments exists a hydrogen moderation and the radioactive shipment set is from all sides exposed to reflection of water layer with at least a 20cm thickness and

(b) radioactive shipments were tested, or their state must be presumed and assessed following the tests described in points 19. - 24. of part II of Annex No. 1 and then

following the most destructive test of the following:

(i) tests specified in point 27. (b) or 27. (c) of part II of Annex No. 1, or both for radioactive shipment less than or equal to 500kg and with a density less than or equal to 1000kg/m3 and taking into consideration external dimensions, or tests according to point 27. (a) for all other radioactive shipments, followed by a test in accordance with point 28. and finished with tests in accordance with points 31. - 33. of part II of Annex No. 1, or

(ii) test in accordance with point 29. of part II of Annex No. 1 and (c) any time any part of the fissile material leaks out of the retaining system,

following the test specified in point 82. (b) of part I of Annex No. 1, it must be considered and assessed that the fissile material has leaked out of every radioactive shipment in the set and the spatial arrangement and moderation, which lead to a maximum neutron multiplication and on top of that near this substance there is a reflection occurring that is caused by a water layer of at least 20cm.

PART II

TESTING PROCEDURES

Certifying compliance

1. (701.) Certification of compliance with the requirements stated in part I of Annex No. 1 must be performed by any method stated below or a combination of these methods:

(a) tests with samples representing radioactive substance with low mass activity of group LSA III, or radioactive substance of special form, or radioactive substance with low dispersibility or with prototypes or samples of packaging sets, where the sample content or a packaging set for test must as accurately as possible simulate the presumed extent of radioactive content. Samples or packaging materials to be tested must be prepared in such a way that they are handed over to transport.

(b) references on previous successful certifications of compliance in accordance with points a), c), and d) of sufficiently similar nature.

(c) tests with models of suitable scale having such properties, which are significant

with regards to tested items when the engineering practice has proven that the results of such tests are suitable for purposes of construction type. When a scaled down model is used, the necessity of rearranging certain test parameters must be taken into consideration, such as for example the diameter of a piercing rod or pressure load.

(d) calculation or documented argument, when the calculation methods and

parameters are generally deemed as reliable or conservative.

2. (702.) The corresponding or defined methods of evaluation must be used following the evaluation of tests to prove that requirements of part II of Annex No. 1 were satisfied in agreement with acceptability standards prescribed in part I of Annex No. 1.

Tests for substance with low mass activity of group LSA III

3. (703.) A solid substance sample representing a full content of radioactive shipment (no less) must be submersed in water for seven days (to determine eluability) at room temperature. The volume of water used for the test must be such that at the end of the seven day test period it ensures that the free volume of unabsorbed and un-reacted water will at least reach 10% of the solid substance volume. The water must have a starting pH of 6 – 8 and a maximum detectable conductivity 10-3mS/m at 20°C. The total activity of water volume must be measured following the termination of the seven day test.

Tests for radioactive substance of special form

General requirements

4. (704.) Samples containing or simulate a radioactive substance of special form must be subjected to a free fall test, impact test, flexible test and thermal test according to points 5.-9. of part II of Annex No. 1. Only one sample can be used for each of those tests. Determination of eluability or volume leak speed test of the given sample must be performed following each test through a method, which cannot be less sensitive than the methods specified in point 10. of part II of Annex No. 1 for a non-dispersible solid substance or according to point 11. of part II of Annex No. 1 for an encased substance.

Testing methods

5. (705.) During a free fall test the sample must fall on a mat (target) from a height of 9 m. The mat must comply with the definition in point 17. of part II of Annex No. 1.

6. (706.) During a penetration test the sample must be placed on a sheet of lead, supported by a smooth firm surface and it must be impacted by a face surface of a rod made of soft steel in such a way that it causes an impact corresponding to the consequences of 1.4kg mass free falling from 1 m. The bottom part of the rod must have a diameter of 25 mm with edges smoothed to a radius of 3.0 +/- 0.3 mm. Lead with hardness of 3.5 – 4.5 according to Vickers scale and with thickness of 25 mm must cover an area greater than the surface of the sample. For every impact a new lead surface must be used. The rod must impact the sample in the presumed place of greatest detriment.

7. (707.) Test by flexing must be performed only for long and thin sources, which are supposed to have a length of 10cm and at the same time a ratio of length to minimum width is at least 10. The sample must be firmly fastened in such a way that half of it overlaps over the edge of fastening. The placement of the sample must be such that it is damaged as much as possible, when its free end will be impacted by the front surface of a steel rod. The steel rod must impact the sample in a way that it causes an impact corresponding with the consequences of impact by a 1.4kg mass free falling from 1 m. The bottom part of the rod must have a diameter of 25 mm with edges smoothed to a radius of 3.0 +/- 0.3 mm.

8. (708.) During a thermal test the sample must be heated in the open air to a temperature of 800ºC, then it must be kept at this temperature for 10 minutes and then it must be allowed to cool.

9. (709.) Samples containing or simulating fissile material or radioactive substance closed in a hermetic casing do not have to be tested:

(a) and test prescribed in points 5. and 6. of part II of Annex No. 1 with the presumption that special form radioactive substance matter is:

(i) less than 200 g and alternately are exposed to impact test class 4, prescribed in publication of the International Organization for Standardization ISO 2919:1999 “Radiation protection -- Sealed radioactive sources -- General requirements and classification” or

(ii) less than 500 g and alternately are exposed to impact test class 5, prescribed in publication of the International Organization for Standardization ISO 2919:1999 “Radiation protection -- Sealed radioactive sources -- General requirements and classification” or

(b) test prescribed in point 8 of part II of Annex No. 1 with the presumption that they are alternatively exposed to impact test class 6, prescribed in publication of the International Organization for Standardization ISO 2919:1999 “Radiation protection -- Sealed radioactive sources -- General requirements and classification”.

Methods for determining eluability and rate of volume leak

10. (710.) For samples containing or simulating indispensable solid substance, the eluability determination must be performed as follows:

(a) the samples must be submersed in water for seven days (to determine eluability) at room temperature. The volume of water used for this test must be such that at the end of the seven day testing period it ensures that the free volume of unabsorbed and un-reacted water will reach at least 10% of the volume of the solid substance sample itself. Water must have a starting pH of 6 – 8 and a maximum conductivity of 1 mS/m at 20ºC;

(b) water with a sample must then be heated to a temperature of 50 +/- 5ºC and this

temperature must be maintained for a period of 4 hours; (c) afterwards water activity must be determined; (d) for this the sample must be left in a calm environment for a period of seven days

with a maximum temperature of 30ºC and a minimum relative humidity of 90%; (e) afterwards the sample must be submersed into water with the same specification as

in point (a) above and this water must then be heated to a temperature of 50 +/- 5ºC and this temperature must be maintained for a period of 4 hours;

(f) finally the water activity must be determined.

11. (711.) For samples containing fissile material or radioactive substance closed in a hermetic casing, the determination of eluability or rate of volume leak must be performed as follows:

(a) The eluability test must be comprised of the following steps:

(i) the sample must be submersed in water at room temperature. Water must

have a starting pH of 6 – 8 and a maximum conductivity of 1 mS/m at 20ºC;

(ii) water containing the sample must then be heated to a temperature of 50 +/- 5ºC and this temperature must be maintained for a period of 4 hours;

(iii) afterwards water activity must be determined;

(iv) following this the sample must be left in a calm environment for a period of seven days with a maximum temperature of 30ºC and a minimum relative humidity of 90%;

(v) the procedure according to points (i), (ii) and (iii) must be repeated. (b) Alternate determination of rate of volume leak must include any of the tests

prescribed in publication of the International Organization for Standardization: “Radiation protection -- Sealed radioactive sources -- Leakage test methods, ISO 9978:1992 E, ISO, Geneva, 1992”, which are acceptable by the Office.

Tests for radioactive substance with low dispersibility

12. (712.) A sample containing or simulating a radioactive substance with small dispersibility must be subjected to an expanded heat test specified in point 36. and impact test specified in point 37. of part II of Annex No. 1. For each of the tests a different sample can be used. Following each test the sample must be subjected to an eluability test specified in point 3. of part II of Annex No. 1. Following each test it must be determined whether the applicable requirements stated in point 5. of part I of Annex No. 1 were satisfied.

Tests for radioactive shipments

Preparation of sample for testing

13. (713.) All samples must be checked before being tested with the objective to identify and record defects or damages, including:

(a) deviations from construction type, (b) production defects, (c) corrosion or other damages, (d) deformation.

14. (714.) The retaining system of the radioactive shipment must be clearly specified.

15. (715.) External sample signs must be clearly identified so that it is possible to make a simple and clear reference to every sample part.

Testing integrity of the retaining system, shielding and evaluation of sub-criticality

16. (716.) Following the performance of appropriate test or tests specified in points 18. - 37.

of part II of Annex No. 1, the following must be performed:

(a) defects or damages must be identified and recorded, (b) find out whether the integrity of the retaining system and shielding in the extent

required in part I of Annex No. 1 with radioactive shipments is preserved and

(c) with radioactive shipments containing fissile materials, find out whether prerequisites and conditions used in evaluation required in points 71. – 82. of part I of Annex No. 1 for one or more radioactive shipments are satisfied.

Target for free fall tests

17. (717.) The target for free fall tests specified in points 5., 22., 25. (a), 27., 35. and 37. of part II of Annex No. 1 must be a flat, horizontal surface of such nature that any increase of its resistance to movement or deformation following the impact of the sample does not sufficiently damage the sample.

Tests for radioactive shipments designed for uranium hexafluoride content

18. (718.) Samples containing or simulating radioactive shipments designed for content of 0.1kg or more of uranium hexafluoride must be tested hydraulically for internal pressure of at least 1.38 MPa, but if the testing pressure is less than 2.76 MPa, the given construction type is subject to type approval by the Office, or more precisely by the relevant competent authorities of the country of origin of construction type, as well as the country through which or to which the delivery is to be transported. Any equivalent non-destructive testing may be used for the specified periodical testing of packaging sets, provided that it is approved by the Office, or more precisely by the relevant competent authorities of the country of origin of construction type, as well as the country through which or to which the delivery is to be transported.

Test proving the ability to withstand normal transportation conditions

19. (719.) This concerns tests by water spraying, free fall, pressure strain and penetration. Samples of radioactive shipments must be subjected to all tests; the water spraying test is always performed first. A single sample may be used for all tests under the presumption that all requirements according to point 20. of part II of Annex No. 1 are satisfied.

20. (720.) The time interval between the end of the water spraying test and the following test must be such that the water is absorbed as much as possible without a more significant drying of sample external surface. If the spray is applied from four sides simultaneously, this pause must be considered as two hours, unless it can be proven that another interval can be more conservative. However, if a gradual spraying side by side to all four sides is applied, then no pause can be taken.

21. (721.) In testing by spray the sample must be exposed to the spraying for at least an hour, which simulates rain with rainfall intensity of 5cm per hour.

22. (722.) In testing by free fall the sample must fall on the target in such a way that with regards to the test it suffers maximum damage, while:

(a) the height of the fall, measured from the lowest placed part of the sample to the upper target surface cannot be less that the distance specified for the appropriate mass in table 3. (13.) The target must correspond with the definition stated in point 17. of part II of Annex No. 1;

(b) for radioactive shipments of right angle shapes from fiber cardboard or from

wood, not exceeding a mass of 50kg, the sample must be tested by a free fall from a height of 0.3m for each corner;

(c) for radioactive shipments of cylindrical shapes from fiber cardboard, not

exceeding a mass of 100kg, the sample must be tested by a free fall from a height of 0.3m for both cylinder bases.

Table 3. (13.) Free fall height in testing radioactive shipment for normal transport conditions

Mass of packaging set with designed content (kg) Free fall height (m)

Less than 5 000 1.2More or equal to 5 000 and less than 10 000 0.9More or equal to 10 000 and less than 15 000 0.6More than 15 000 0.3

23. (723.) If during a pressure test the shape of the packaging set does not efficiently prevent compression, the sample must be exposed to a pressure strain for a period of 24 hours, which must be equally divided into two opposing sides of the sample, where one must be the base on which the radioactive sample normally rests with a mass equal to or greater than two of the following:

(a) quintuple of mass of radioactive shipment or (b) product of surface vertically projected cross section of radioactive shipment and

pressure 13 kPa.

24. (724.) During a penetration test the sample must be placed on a non-evasive flat horizontal surface, while:

(a) a rod with a diameter of 32 mm with a semi-rounded end and a mass of 6kg must hit in a vertical axis angle on the center of the weakest part of the sample in such a way that during a sufficiently deep penetration it hits the retaining system. The rod may not be significantly deformed during the test.

(b) the height of the fall of the rod measured from its most bottom end of the part

intended for impact to the upper edge of the sample must be 1 m. Additional tests for radioactive shipment type A designed for liquids and gases

25. (725.) Samples must be certified by each of the tests stated in this point, unless it is possible to prove that one of the tests is for the given sample more demanding than another, in such a case the sample must be certified by a more demanding test:

(a) free fall test, the sample must fall on the target in a way that it becomes damaged

as much as possible with regards to the retaining system. Height of the free fall measured from the most bottom part of the sample to the upper part of the target must be 9 m. Target must correspond to the definition stated in point 17. of part II of Annex No. 1;

(b) penetration test, the sample is tested for penetration in accordance with point 24.

of part II of Annex No. 1, however the height of the fall of the rod must be 1.7 m as opposed to 1 m specified in point 24. (b) of part II of Annex No. 1.

Tests proving the ability to withstand conditions of an accident during transport

26. (726.) The sample must be certified by the cumulative effects of tests stated in points 27. and 28. of part II of Annex No. 1 in the stated order. Following these tests the sample or a special sample tested by submersion into water according to point 29. and if applicable also point 30. of part II of Annex No. 1.

27. (727.) Mechanical test is comprised of three various fall tests. Each sample is study

tested according to the requirements in points 56. and 82. of part I of Annex No. 1. The order of tests must be such that following the termination of the mechanical test the damage to the sample during the ensuing thermal test is as extensive as possible, while:

(a) during free fall test I the sample must fall on a target in such a way that it becomes as damaged as possible, the height of the fall measured from the lowest part of the sample to the upper part of the target must be 9 m. The target must correspond with the definition stated in point 17. of part II of Annex No. 1;

(b) during free fall test II the sample must fall in such a way that it becomes damaged as much as possible following the impact on the rod attached vertically to the target. The height of the fall measured from the expected point of impact on the sample to the upper part of the rod must be 1 m. The rod must be made of firm soft steel with a circular profile and a diameter of 15.0cm ± 0.5cm and a length of 20cm, unless a longer rod would cause greater damage. If a longer rod would cause greater damage, the length of the used rod must be set to cause the greatest damage possible. The upper end of the rod must be flat, horizontal with rounded edges and a radius of no more than 6 mm. The target, to which the rod is attached, must correspond with definition stated in point 17. of part II of Annex No. 1;

(c) during test III the sample placed on the target is subjected to a dynamic crush by a

fall of an object with a mass of 500kg from a height of 9 m in such a way that it becomes as damaged as possible. The falling object must be a firm, medium hard steel plate with dimensions 1 m x 1 m and must fall in a horizontal position. The height of the fall must be measured from the bottom side of the plate to the upper edge of the sample. The target, on which the sample is resting, must correspond with the definition stated in point 17. of part II of Annex No. 1.

28. (728.) Before a thermal test the sample must be in a heat balance in surrounding

temperature of 38°C, under conditions of sun irradiation according to table 1.(11.) and at the same time while being exposed to maximum generation of inner heat provided by the radioactive content of the radioactive shipment. Alternately any of the stated parameters can have before and during the test a different value. A thermal test, during which the sample cannot be artificially cooled and any burning of the sample materials must be left to run its course, must comprise of:

(a) exposure of a sample for a period of 30 minutes to such heat environment, which at least corresponds to a heat flow equivalent to the flame from a mixture of hydrocarbon fuels and air under sufficiently stable surrounding conditions to achieve an average emission coefficient of at least 0.9 at an average temperature of flame at least 800°C, fully surrounding the sample, having a surface absorption coefficient of 0.8 or such where the value of the radioactive shipment will demonstrably have upon being exposed to fire,

(b) the ensuing exposure of the sample to surrounding temperature of 38°C due to the

influence of sun irradiation according to table 1.(11.) and at the same time with maximum generation of inner heat provided by the radioactive content of the radioactive shipment for a sufficient time period, which will ensure that the temperatures anywhere in the sample were lowered and nearing with initial balanced conditions. Alternately, following a disruption of external intake of heat any of the stated parameters may have a different value, under the presumption that they are being taken into consideration during the ensuing evaluation of the response of radioactive shipment.

29. (729.) During the water submersion test the sample must be submersed at least 15 m under the surface for a period of at least 8 hours in order for it to become as damaged as possible. Conditions of the test correspond to the value of the external pressure of at least 150 kPa.

Expanded water submersion test for radioactive shipment type B(U), type B(M) containing more than 10E5 A2 and for radioactive shipment type C

30. (730.) During a water submersion test the sample must be submersed under the surface of at least 200 m for a period of at least 1 hour. Test conditions correspond to the value of external overpressure of at least 2 MPa.

Test by water submersion for radioactive shipments containing fissile materials

31. (731.) Radioactive shipments, for which the evaluation for penetration and leakage of water was performed in the extent, which leads to a higher reactivity for purposes of evaluation according to points 77. - 82. of part I of Annex No. 1, are excluded from this test.

32. (732.) Before the sample is tested by water submersion, it must be tested in accordance

with point 27. (b) or 27. (a) or 27. (c) of part II of Annex No. 1, as required in point 82. of part I of Annex No. 1 and specified in point 28. of part II of Annex No. 1.

33. (733.) The sample must be submersed under the water surface at least 0.9 m for a period of at least 8 hours in a position in which the maximum seepage is expected.

Tests for radioactive shipment type C

34. (734.) Samples must be subjected to the effects of each of the following tests in the stated order:

(a) tests specified in points 27. (a), 27. (c), 35. and 36. of part II of Annex No. 1 and

(b) test specified in points 37 of part II of Annex No. 1.

NoteFor the order of tests according to (a) and (b) it is permitted to use special samples.

35. (735.) During a test by penetration the sample must be exposed to the destructive effects

of a probe from medium hard steel. The location of the probe against the sample surface must be such that following the test procedure specified in point 34. (a) of part II of Annex No. 1 causes maximum damage to the sample.

(a) A sample representing a radioactive shipment with mass less than 250kg, must be placed on the target and exposed to a fall by the probe with a mass of 250kg, falling from height of 3 m above the intended point of impact. The probe for this test must be a cylindrical rod with a diameter of 20cm and with an end (that will be hitting the sample) in the shape of a blunt cone with the following dimensions: 30cm height and 2.5cm average of the end part. The target the sample is attached to must correspond to the definition stated in point 17. of part II of Annex No. 1.

(b) for radioactive shipments with a mass greater than 250kg the probe must be placed

on the target and the sample falls on the probe. The height of the fall, measured from the point of impact to the external surface of the probe, must be 3 m. For this test the probe must have the same shape and dimensions as specified above in (a), with the exception of when the greater length and mass of the probe could bring on greater damage to the sample. The target, which must have the rod attached, must correspond to the definition stated in point 17. of part II of Annex No. 1.

36. (736.) The conditions of the extended heat test must be same as the conditions specified

in point 28. of part II of Annex No. 1, with the exception that exposure to heat must last for 60 minutes.

37. (737.) During the impact test the sample must be subjected to target impact at a speed of

less than 90 m/s, and positioned to suffer maximum damage. The target must correspond to the definition stated in 17. of part II of Annex No. 1.


1. Packaging set type D and S

(a) must be demonstrably sufficiently mechanically durable with regards to the designed method of handling,

(b) must be produced from materials whose life expectancy demonstrably corresponds with the designed life expectancy of packaging material. Materials with a shorter life expectancy can be used for components of the packaging set, which can be easily replaced during warehouse or storage operations,

(c) must satisfy requirements derived from the permit to handle sources of ionising

irradiation according to Section 9 paragraph 1 letter i) of the Act.

2. The approved packaging set type S must be constructed in such a way that:

(a) it complies with requirements in points 6. – 16. of part I of Annex No. 1 and further requirements, which are set by the Office in type approval based on applicant’s proposal.

While the requirements1. on packaging sets type S for storing radioactive substances must be in

accordance with the requirements on permission to handle sources of ionising radiation according to Section 9 paragraph 1 letter i) of the Act,

2. on packaging sets type S for storing radioactive wastes must be in accordance with the requirements on permission to handle radioactive wastes according to Section 9 paragraph 1 letter i) of the Act,

3. on packaging sets type S for storing spent nuclear fuel must be in accordance with the limits and conditions of the relevant storage of spent nuclear fuel approved by the Office;

(b) it enables sufficient content drying and its surrounding by the defined medium. The Office, based on the applicant’s proposal, shall decide on the criteria of drying content of packaging set and parameters of used medium;

(c) it provides the option to check packaging set seal tightness during the course of warehouse operations;

(d) it has preserved sufficient shielding under normal operation and project accidents. Shielding of the packaging set must guarantee that the input of batch equivalent on the surface of the packaging set is lower than 10 mSv/h at maximum permitted activity of the designed radionuclide content;

(e) heat created inside of the packaging set by effect of its radionuclide content, under normal conditions and exterior temperature of 38ºC, did not influence the packaging set so adversely that it would not comply with the requirement on tightness and shielding in case the packaging set and its content will not be monitored for a period of one week;

(f) eliminates influence of created heat, heat cannot:

1. change arrangement, geometrical form or physical state of radionuclide

content or, if the radionuclides are closed in a special casing, cause deformation or melting of this casing or radionuclides,

2. lower shielding effectiveness of the packaging set as a result of its irregular thermal expansion or rupturing or melting of the shielding material,

3. speed up corrosion in combination with humidity,4. be a cause of disruption in removal of residual heat and the removal of

residual heat must be guaranteed even under conditions of project accidents.

3. Approved packaging set type D must be constructed in such a way that it complies with all requirements specified in points 6. – 16. of part I of Attachment No. 1 and other requirements, which are determined by the Office in type approval based on the applicant’s proposal. While the requirements on packaging sets type D for storing radioactive wastes must be in accordance with the requirements on permission to handle radioactive wastes according to Section 9 paragraph 1 letter i) of the Act in the extent of disposal.

Annex no. 3 to Decree no. ………. Coll.

Activity limits and material restrictions

Basic radionuclide values

1. (401.)*) Table 1. (1.) states the following values for individual radionuclides:

(a) A1 and A2 in TBq; (b) limits of mass activity for excluding a substance from requirements of this Decree

in Bq/g; and

(c) activity limits for excluding a shipment from the requirements of this Decree in Bq/g.

Determining basic radionuclide values

2. (402.) for individual radionuclides, which are not stated in table 1. (1.) of Annex No. 3 the determination of the basic values stated in point 1 of Annex No. 3 requires an approval by the Office and approval by the relevant authorities of the countries that the transport is concerning. It is permitted to use value A2 calculated by using the batch coefficient for relevant type of lung absorption, as recommended by the International Commission on Radiological Protection, if under normal transportation conditions or during accident conditions the chemical form of each radionuclide is considered. Alternately the values of radionuclides stated in table 2 (2.) of Annex No. 3 may be applied without the approval of the Office.

3. (403.) In determining value A1 or A2 for radionuclide, which is not stated in table 1. (1.) of Annex No. 3, the decay series, if the radionuclides contained therein are in the proportions in which they occur in nature and if no product of the radioactive transformation has a half-life longer than 10 days or longer than the half-life of the initial radionuclide in the series, considered as an individual radionuclide and the values of activity A1 or A2, which are to be used, must be values corresponding with initial radionuclides of the given series. In the event of a decay series, where any product of radioactive transformation has a half-life longer than 10 days or longer half-life than the initial radionuclide the initial radionuclide along with products of radioactive transformation must be considered a mixture of various radionuclides.

4. (404.) To determine basic values for radionuclide mixtures, where the basic values of individual radionuclides are stated in table 1. of Annex No. 3 herein, the following relationship applies:Xm = 1 / Σ[f(i)/X(i)], i

) Note:Position numbers printed in parentheses next to point numbers, possibly tables and images correspond with numbering in the recommendation of the International Atomic Energy Agency “IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, Safety Requirements, International Atomic Energy Agency, Vienna, 2005”.

where:

f(i) is the share of activity or mass activity of the relevant radionuclide even in a mixture,X(i) the relevant value A1 or A2 or limit of mass activity for a substance excluded from the

requirements of this Decree or limit of activity for shipment excluded from the requirements of this Decree for relevant radionuclide i;and Xm is the basic value derived for a mixture from values A1 or A2 or from limit mass activity for a substance excluded from the requirements of this Decree or limit activity for a shipment excluded from the requirements of this Decree.

5. (405.) If the identity of each radionuclide is known, but the values of activity of some of these are not known, the radionuclides can be sorted into groups and the lowest value of activity in each group can be used in calculations according to the formulas stated in points 4 and 14 of Annex No. 3. Groups can be based on overall alpha activity and overall beta/gamma activity, if these are known; to calculate according to formulas stated in points 4 and 14 of Annex No. 3 the lowest values are used for alpha emitters and well as beta/gamma emitters.

Table 1. (1.) Basic radionuclide values

radionuclide (atomic number) A1 A2 Limit of mass activity for substance

exclusion

Limit of mass activity for shipment

exclusion[TBq] [TBq] [Bq/g] [Bq]

Actinium (89) Ac-225 (a) 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

Aluminum (13) Al-26 1x10-1 1x10-1 1x101 1x105

Americium (95) 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 (83) 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) 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 5x10-2 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

Cesium (55) Cs-129 4x100 4x100 1x102 1x105

Cs-131 3x101 3x101 1x103 1x106

Cs-132 1x100 1x100 1x101 1x105

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) 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 Unlimited 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-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

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

P-33 4x101 1x100 1x105 1x108

Protactinium (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) 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) 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) Te-121 2x100 2x100 1x101 1x106

Te-121m 5x100 3x100 1x102 1x105

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 Unlimited 1x100(b) 1x103(b) Titan (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 (fast retention) (a) (d) 4x101 1x10-1 1x101(b) 1x105(b) U-230 (medium fast retention)

(a), (e) 4x101 4x10-3 1x101 1x104

U-230 (slow retention) (a) (f) 3x101 3x10-3 1x101 1x104

U-232 (fast retention)(d) 4x101 1x10-2 1x100(b) 1x103(b) U-232 (medium fast retention)(e) 4x101 7x10-3 1x101 1x104

U-232 (slow retention) (f) 1x101 1x10-3 1x101 1x104

U-233 (fast retention) (d) 4x101 9x10-2 1x101 1x104

U-233 (medium fast retention)(e) 4x101 2x10-2 1x102 1x105


U-234 (fast retention) (d) 4x101 9x10-2 1x101 1x104



U-235 (all types of retention) (a), (d), (e), (f)

Unlimited Unlimited 1x101(b) 1x104(b)

U-236 (fast retention) (d) Unlimited Unlimited 1x101 1x104



U-238 (all types of retention) (d), (e), (f)

Unlimited Unlimited 1x101(b) 1x104(b)

U (natural) Unlimited Unlimited 1x100(b) 1x103(b) U (enriched to 20% or less) (g) Unlimited 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) (a) values of activities A1 or A2 for these parent radionuclides include contributions of products from radioactive

transformation with a half-life shorter than 10 days as stated below:Mg-28 Al-28Ar-42 K-42Ca-47 Sc-47Ti-44 Sc-44Fe-52 Mn-52mFe-60 Co-60mZn-69m Zn-69Ge-68 Ga-68Rb-83 Kr-83mSr-82 Rb-82Sr-90 Y-90Sr-91 Y-91mSr-92 Y-92Y-87 Sr-87mZr-95 Nb-95mZr-97 Nb-97m, Nb-97Mo-99 Tc-99mTc-95m Tc-95Tc-96m Tc-96Ru-103 Rh-103mRu-106 Rh-106Pd-103 Rh-103mAg-108m Ag-108Ag-110m Ag-110Cd-115 In-115mIn-114m In-114Sn-113 In-113mSn-121m Sn-121Sn-126 Sb-126mTe-118 Sb-118Te-127m Te-127Te-129m Te-129Te-131m Te-131Te-132 I-132I-135 Xe-135mXe-122 I-122Cs-137 Ba-137mBa-131 Cs-131Ba-140 La-140Ce-144 Pr-144m, Pr-144Pm-148m Pm-148Gd-146 Eu-146Dy-166 Ho-166Hf-172 Lu-172W-178 Ta-178W-188 Re-188Re-189 Os-189mOs-194 Ir-194Ir-189 Os-189mPt-188 Ir-188Hg-194 Au-194Hg-195m Hg-195Pb-210 Bi-210Pb-212 Bi-212, Tl-208, Po-212Bi-210m Tl-206Bi-212 Tl-208, Po-212At-211 Po-211Rn-222 Po-218, Pb-214, At-218, Bi-214, Po-214Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212Ra-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-214Ra-228 Ac-228Ac-225 Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209Ac-227 Fr-223Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212Th-234 Pa-234m, Pa-234Pa-230 Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214U-230 Th-226, Ra-222, Rn-218, Po-214U-235 Th-231Pu-241 U-237Pu-244 U-240, Np-240mAm-242m Am-242, Np-238Am-243 Np-239Cm-247 Pu-243Bk-249 Am-245Cf-253 Cm-249

(b) radionuclides and products of their radioactive transformation corresponding with permanent balance are stated below:Sr-90 Y-90Zr93 Nb-93mZr-97 Nb-97Ru-106 Rh-106Ag-108m Ag-108Cs-137 Ba-137mCe-144 Pr-144Ba-140 La-140Bi-212 Bi-210, Po-210Pb-212 Bi-212, Tl-208 (0.36), Po-212 (0.64)Rn-220 Po-216Rn-222 Po-218, Pb-214, Bi-214, Po-214Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Tl-207Ra-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-228Th-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-209Th 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-234mU-230 Th-226, Ra-222, Rn-218, Po-214U-232 Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64) U-235 Th-231U-238 Th-234, Pa-234mU 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-210Np-237 Pa-233Am-242m Am-242Am-243 Np-239 (c) Quantity can be determined by a measurement of transformation speed or measurement of batch equivalent input at a defined distance from the radionuclide emitter. (d) These values are only applicable for the following compounds of uranium: UF 6 , U 2 F 2 , UO 2 (NO 3 ) 2 . (e) These values are only applicable for the following compounds of uranium: UO 3 , UF 4 , UCl 4 and hexavalent uranium compounds. (f) These values are only applicable for the following compounds of uranium not stated in points d) and e). (g) These values are only applicable for non-irradiated uranium.

6. (406.) For individual radionuclides or their mixtures, for which the necessary data are

not known, values stated in table 2 (2.) of Annex No. 3 must be used. Table 2. (2.) Basic radionuclide values for unknown radionuclides and mixtures

Radioactive content A1 A2 Limits of Mass

activity for exclusion of

substance

Limits of activity to exclude a shipment

[TBq] [TBq] [Bq/g] [Bq]Only presence of radionuclides emitting beta or gamma radiation is known

0.1 0.02 1x101 1x104

Only presence of radionuclides emitting alpha radiation is known, but no presence of neutron emitters is known

0.2 9x10-5 1x10-1 1x103

Only presence of neutron emitters is known or no information is available

0.001 9x10-5 1x10-1 1x103

Limits of radioactive content for radioactive shipment

7. (407.) The quantity of fissile material or radioactive substance in a radioactive shipment may not exceed the relevant limits in points 8. – 20. of Annex No. 3.

Excluded shipments

8. (408.) Excluded shipments for fissile material or a radioactive substance other than items manufactured from natural uranium, depleted uranium, or natural thorium, may not contain higher than the following activities:

(a) in a case where the fissile material or a radioactive substance is categorized or included as part of a device or another product, such as clocks or electronic devices, limits for each individual item and each radioactive shipment (in this Decree) specified in columns 2. and 3. of table 3. (3.) of Annex No. 3 apply;

(b) in a case where the fissile material or a radioactive substance is not categorized or included as part of a device or another product, such as clocks or electronic devices, limits for radioactive shipment specified in column 4. of table 3. (3.) of Annex No. 3 apply.

9. (409.) Excluded shipment for manufactured from natural uranium, depleted uranium, or natural thorium can contain any amount of such substance under the presumption that the external surface of the uranium or thorium is enclosed in an inactive casing made of metal or another solid material.

10. (410.) For transport via postal service the total activity of each excluded shipment may

not exceed a tenth of the relevant limit specified in table 3. (3.) of Annex No. 3.

Type IP-1, type IP-2 and type IP-3

11. (411.) Radioactive content in a single radioactive shipment of LSA substance according to Section 2 of letter o) or SCO according to Section 2 letter x) must be restricted in

such a way that the input of radioactive equivalent batch specified in point 21. of Annex No. 4 may not be exceeded and activity in one radioactive shipment must be restricted to not exceed the activity limit for transportation vehicle specified in point 25. of Annex No. 4.

Table 3. (3.) Limits of activity for excluded shipments

PHYSICAL STATE OF CONTENT

(PHASE)

Device or product Substances –limits for radioactive

shipmentsaLimits for itema Limits for radioactive

shipmentsa

Solid:Special form 10-2A1 A1 10-3A1

other 10-2A2 A2 10-3A2

Liquid 10-3A2 10-1A2 10-4A2

Gaseous:tritium 2x10-2A2 2x10-1A2 2x10-2A2

Special form 10-3A1 10-2A1 10-3A1

other 10-3A2 10-3A2 10-3A2

a) for radionuclide mixtures, see points 4. - 6. of Annex No. 3. 12. (412.) One radioactive shipment of a non-flammable solid substance LSA II or LSA III,

if air transported, may not contain activity higher than 3000 A2 . Radioactive shipments type A

13. (413.) Shipments type A may not contain activity higher than:

(a) value A1; for radioactive substance of special form or

(b) value A2; for all other radioactive substances. 14. (414.) For radionuclide mixtures the identity and relevant activity of which are known,

the following condition for content of radioactive shipments type A applies:

Σ [B(i)/A1(i)] + Σ [C(j)/A2(j)] 1, i jwhere:

B(i) is the activity of radionuclide i as the radioactive substance of special formA1(i) is value A1 for radionuclide i, C(j) is the activity of radionuclide j as the radioactive substance other than radioactive

substance of special form and A2 (j) is the value of A2 for radionuclide j.

Radioactive shipments type B(U) and B(M)

15. (415.) Shipments type B(U) and B(M) may not contain:

(a) higher activities than those permitted for the given construction type, (b) other radionuclides than those permitted for the given construction type, or

(c) radioactive content in a form or chemical or physical state other than which was permitted for the given construction type

as is described in the decision on type approval. 16. (416.) Air transported shipments type B(U) and B(M) must comply with the

requirements of point 16. of Annex No. 3 and may not contain higher than the following activity:

(a) for radioactive substance with low dispersibility – as were permitted for the given construction type, as is described in the decision on type approval,

(b) for radioactive substance of special form - 3000 A1 or 100 000 A2, whichever is lower,

(c) for all other types of fissile materials and radioactive substances - 3000 A2.

Radioactive shipments type C

17. (417.) Shipments type C may not contain:

(a) higher activities than those permitted for the given construction type, (b) other radionuclides than those permitted for the given construction type, or

(c) radioactive content in a form or chemical or physical state other than that permitted for the given construction type and are included in the decision on their type approval.

as is described in the decision on type approval.

Radioactive shipments containing fissile materials

18. (418.) Radioactive shipments containing fissile materials may not contain:

(a) mass of the fissile material different from that specified for the given construction type,

(b) any radionuclides or fissile materials different from those specified for the given construction type,

(c) radioactive content in a form or chemical or physical state or in a special arrangement other than that specified for the given construction type

as is described in the decision on type approval. Radioactive shipments containing uranium hexafluoride

19. (419.) Radioactive shipments containing uranium hexafluoride may not contain:

(a) uranium hexafluoride with a mass different from the mass determined in the decision on type approval,

(b) uranium hexafluoride with a mass greater than the one, which permits 5% of free volume in a packaging set at the maximum temperature of the radioactive shipment, as is described for systems of the facilities where the radioactive shipment will be handled,

(c) uranium hexafluoride in other than solid state or under an internal pressure higher than the atmospheric pressure during handover for transport.


Transport Requirements

Requirements prior to first transport

1. (501.)*) Prior to the first transport of radioactive consignments the following requirements must be met:

(a) if the projected overpressure on the retaining system exceeds 35 kPa, it must be ensured that the retaining system of each radioactive consignment conforms to the approved project requirements with regard to the ability of the system to preserve its integrity under such pressures,

(b) the effectiveness of the shielding and retaining system must be ensured for each

type B(U), B(M) and C radioactive consignment and for each radioactive consignment containing fissile material, and if necessary, the characteristics of heat transfer and the efficiency of the curbing system, were in the framework of evaluations usable for approving the construction type or described in it,

(c) each radioactive consignment which contains fissile material and to which were

purposely added neutron toxins as a component must be subjected to testing to determine the presence and location of these neutron toxins in order to meet the stipulations of item 71. part I. Annex No. 1.

Requirements prior to every transport

2. (502.) Before each transport of radioactive consignments the following requirements must be met:

(a) for all radioactive consignments all requirements must be met corresponding to the relevant type of radioactive consignment,

(b) hoisting handles that do not meet the conditions specified in item 7. part I. Annex

No. 1 must be removed or in some other way made unusable for hoisting radioactive consignments in accordance with item 8. part I. Annex No. 1,

(c) for each radioactive consignment for which approval from the Authority is

required all conditions stipulated in the decision on approval must be met, (d) each type B(U), B(M) and C radioactive consignment and each radioactive

consignment containing fissile material must not be transported before meeting the conditions balance close enough conditions corresponding to the requirements for heat and pressure during transport, as long as there is no exception to these requirements contained in the approval.

) Note:The position number printed in brackets next to the item number in tables and pictures corresponds to the numbering in the recommendation of the International Atomic Energy Agency “IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, Safety Requirements, International Atomic Energy Agency, Vienna, 2005”.

(e) for each type B(U), B(M) and C radioactive consignment and for each radioactive consignment containing fissile material all seals, vents or other openings which could leak radioactive contents in the retaining system must be verified by checks or suitable tests that they are closed in an appropriate way and if necessary sealed

as in proof tests in accordance with the requirements of item 57. and 69. part I. Annex No. 1,

(f) each radioactive substance must meet all the conditions stipulated in the decision

on approval and all corresponding requirements, (g) for radioactive consignments containing fissile material the carrying out of

measurements described in item 74. (b) part I. Annex No. 1 and tests to establish that each radioactive consignment is sealed according to item 77. part I. Annex No. 1, if applicable must be ensured,

(h) each radioactive substance with low diffusion must meet all the conditions stipulated in the decision on approval and all corresponding requirements.

Transport of other items

3. (503.) Radioactive consignments cannot, outside instruments required for handling fissile material or radioactive substances, contain anything else. Mutual operation between these instruments and the radioactive consignment must not decrease their safety, for all conditions anticipated in the project construction type of radioactive consignments.

4. (504.) The containers for bulk substances which are used to transport radioactive substances must not be used for transit storage or transporting other items if they have not been decontaminated in such a way that the non-fixed surface contamination for gamma radiation, beta radiation and alpha radiation with low toxicity is not greater than 0.4 Bq/cm2 and for other alpha radiation not greater than 0.04 Bq/cm2.

5. (505.) Transport of other items with cargo transported upon condition of exclusive use is permitted if the mutual transport is entirely organized by one shipper and is not forbidden on the basis of other stipulations of this Decree.

6. (506.) During transport and transit storage the cargo must be separated from other dangerous items in accordance with the relevant regulations for transporting dangerous items in each country through which or to which the fissile material or radioactive substance is transported, as the case may be, regulations of the shipper as well as the requirements of this Decree.

Transporting radioactive consignments containing other dangerous characteristics

7. (507.) During packing, marking, placing labels, storing and transport, besides radioactive and fissile characteristics, other dangerous characteristics of radioactive consignments such as explosiveness, flammability, combustibility, chemical toxicity and corrosiveness must be taken into account with the goal of ensuring conformity with the relevant regulations for transporting dangerous items in each country through which or to which the fissile material or radioactive substance is transported, as the case may be, regulations of the shipper, as well as the requirements of this Decree.

Inspections and requirements in terms of contamination and leaks of radioactive

consignments

8. (508.) Non-fixed contamination to the exterior surface of radioactive consignments must be held to the lowest attainable level in practice and in ordinary transport conditions must not exceed the following limits:

(a) 4.0 Bq/cm2 for gamma and beta radiation and for alpha radiation with low toxicity; and

(b) 0.4 Bq/cm2 for other alpha radiation. NoteThe above limit levels are considered average results from abrasion of areas of 300cm2 on random parts of the surface.

9. (509.) With the exception specified in item 14. Annex No. 4 the level of non-fixed

contamination in external and internal surfaces of exterior packaging, transport containers, cisterns and mid-size containers for freely placed items cannot exceed the limits stipulated in item 8. Annex No. 4.

10. (510.) If it is obvious that the radioactive consignment is damaged or leaking or if it is

suspected that the radioactive consignment was damaged or leaking, access to it must be limited and a qualified person must evaluate the power input of the dose equivalent and the scope of contamination of these consignments as soon as possible. The evaluation must be carried out with regard to the radioactive consignment, vehicle, loading and unloading place and including neighbouring places and in case of need to all other materials which are found in the vehicle. In case of need other measures to protect health, property and the environment according to the conditions stipulated in the valid legal regulations must be carried out with the goal of removing or as much as possible decreasing the consequences of the leak or damage.

11. (511.) Radioactive consignments from which area leaking radioactive contents exceed

the limit permitted for normal transport conditions must be placed under supervision in a suitable place, but must not be further transported unless they have been repaired or otherwise put into proper condition and decontaminated.

12. (512.) The vehicle and equipment usually used to transport radioactive substances must

be regularly checked to determine the level of contamination. The frequency of these checks must correspond to the likelihood of contamination and the amount of transported radioactive substances.

13. (513.) With the exception specified in item 14. Annex No. 4 all vehicles and their

equipment and parts that were contaminated during transport of radioactive substances or are over the limit stipulated in item 8. Annex No. 4 or show a power input of a dose equivalent to or greater than 5 Sv/h must be decontaminated as soon as possible by a qualified person; they cannot be reused as long as the non-fixed contamination exceeds the limits stipulated in item 8. Annex No. 4 and as long as there is no power input of the dose equivalent, ensuing from the fixed contamination on the surface, after decontamination less than 5 Sv/h.

14. (514.) Exterior packaging, transport containers, cisterns, large bins for freely placed

substances or vehicles designated for transporting radioactive substances transported upon condition of exclusive use are excluded from the conditions of items 9. and 13.

Annex No. 4; however, only in relation to their interior surfaces and only for the period during which this exclusive use remains.

Requirements for transporting exclusive consignments

15. (515.) Exclusive consignments are liable only to the following requirements:

(a) in items 7., 8., 11., 16., 34. - 37., 50. (c), 55. and corresponding requirements from items 17. - 20. Annex No. 4,

(b) in item 20. part I. Annex No. 1 on exclusive consignments, (c) in item 34. part I. Annex No. 1, on exclusive consignments containing fissile

material and also meeting one of the requirements of item 72. part I. Annex No. 1, (d) in items 80. and 81. Annex No. 4 on transport by post.

16. (516.) The power input of the dose equivalent on a random place on the exterior surface of exclusive consignments must not exceed 5 Sv/h.

17. (517.) Fissile materials or radioactive substances which are enclosed in equipment or

engaged in production or create a part of this subject and its activities also do not exceed the limits stipulated for the item and for radioactive consignments in columns 2. and 3. Table 3 (3.) Annex No. 3 can be transported as an exclusive consignment as long as the following prerequisites are met:

(a) the power input of the dose equivalent at a distance of 10cm from the random place on the external surface of a packaged device or product is not greater than 0.1 mSv/h,

(b) every device or product is marked “Radioactive” with the exception of:

(i) clocks or devices powered by marked colours lit on the basis of radio-luminescence,

(ii) consumer goods having permission from a competent authority or not exceeding the activity limit for exclusive consignments specified in Annex No. 3 of this Decree in Table 1. (1.) column 5, upon the condition that these kinds of products are transported in a package which is marked with the words “Radioactive” on the interior surface in such a way that the marking of radioactive substance is visible after opening the exterior packaging; and

(c) the fissile material or radioactive substance is completely enclosed with a non-active reactant (devices whose only purpose is to contain radioactive substances cannot be considered as devices or products in the above sense).

18. (518.) Fissile materials or radioactive substances of a form other than described in item

17. Annex No. 4 can be transported as an exclusive consignment if they do not exceed the activity limits stipulated in column 4. of Table 3 (3.) Annex No. 3 and if they meet the following prerequisites:

(a) the radioactive consignment maintains its radioactive contents under the

conditions of normal transport, (b) the radioactive consignment is marked with the words “Radioactive” on the

interior surface of the package in such a way that the warning about the presence of fissile material or radioactive substances is visible when the package is opened.

19. (519.) Products that contain fissile materials or radioactive substances, non-irradiated

natural uranium, non-irradiated depleted uranium or non-irradiated natural thorium can be transported as an exclusive consignment if the exterior surface of the uranium or thorium has non-active plastic metal or another solid material.

Further requirements for transporting empty packages

20. (520.) Empty packages containing fissile material or radioactive substances can be transported as an exclusive consignment if the following prerequisites are met:

(a) the package is in excellent condition and is safely sealed, (b) the exterior surface of each of its uranium or thorium parts is sealed with a non-

active casing made of metal or another solid material, (c) the level of non-fixed contamination on its interior surface does not exceed the

centuple limit stipulated in item 8. Annex No. 4, (d) all safety labels which could be placed on it in accordance with item 42. Annex

No. 4 are enclosed, devalued or removed. Checking and requirements for transporting radioactive substances of low specific activity (LSA) and surface contaminated objects (SCO) in industrial consignments or unpacked.

21. (521.) The number of LSA or SCO substances in one IP-1, IP-2, IP-3 package or object, or package object must be limited in such a way that the external power input of the dose equivalent is at a distance of 3 m from the unshielded substances or objects or package object does not exceed 10 mSv/h.

22. (522.) LSA and SCO substances which are fissile materials or contain fissile materials

must correspond to the relevant conditions of items 69. and 70. Annex No. 4 and item 71. part I. Annex No. 1.

23. (523.) LSA and SCO substances in the LSA-I and SCO-I groups can be transported

unpacked under these conditions:

(a) all unpacked substances, with the exception of ores containing radionuclides occurring exclusively in nature, must be transported in such a way that under normal transport conditions the radioactive contents cannot leak into the vehicle and cannot lead to a loss of shielding,

(b) every vehicle must be used only to transport upon the condition of exclusive use, unless they transported only SCO-I objects, whose level of contamination on accessible and inaccessible surfaces is greater than 10 multiples of the limit specified in item 4. Annex No. 4,

(c) inaccessible surfaces and substances in the SCO-I group cannot demonstrate a

greater level of non-fixed contamination than the values stipulated in directive 2 letter x) item 1. aa); on the other hand, measures can be carried out which ensure that the fissile materials or radioactive substances cannot leak into the vehicle.

24. (524.) LSA and SCO substances must be packed in accordance with the requirements in Table 1. (4.) Annex No. 4, unless otherwise specified in item 23. Annex No. 4.

25. (525.) The total activity of LSA and SCO substances in stowage space or the watertight

section of a craft for floatage or in another vehicle in type IP-1, IP-2, IP-3 radioactive consignments or unpacked consignments cannot exceed the limits stipulated in Table 2. (5.) Annex No. 4.

Table 1. (4.) Requirements for industrial consignments for LSA and SCO substances

Radioactive contents Type of industrial consignmentTransport upon condition of exclusive use

Other transports

LSA-I Solid a

LiquidType IP-1Type P-1

Type IP-1Type IP-2

LSA-II SolidLiquid and gas

Type IP-2Type IP-2

Type IP-2Type IP-3

LSA-III Type IP-2 Type IP-3SCO-I a Type IP-1 Type IP-1SCO-II Type IP-2 Type IP-2a) Upon the conditions described in item 23. Annex No. 4 LSA-I and SCO-I substances can be transported non-packaged. Table 2. (5.) Limits on activities for LSA or SCO substances in industrial consignments or non-packaged

Type of substance Limits on activities for vehicles other than domestic crafts

Limits on activities for the craft space or watertight section of domestic crafts

LSA-I Unlimited UnlimitedLSA-II a LSA-III

Solid flame proof substancesUnlimited 100 A2

LSA-II a LSA-IIISolid flame proof substances

and all liquid substance and gasses

100 A2 10 A2

SCO 100 A2 10 A2

Table 3. (6.) Multiplication factors for large-size cargo

Dimension of cargo a Multiplication factor

Up to 1 m2 1

From more than 1 m2 to 5 m2 2

From more than 5 m2 to 20 m2 3

From more than 20 m2 10

a) Stipulated as the largest surface of possible opening of cargo Stipulated transport index

26. (526.) The transport index (TI) for radioactive consignments, exterior packaging, transport containers, unpacked LSA-I substances or unpacked SCO-I is the number derived on the basis of the following procedure:

(a) determination of the largest power input of the dose equivalent in mSv/h at a distance of 1 m from the exterior surface of the radioactive consignments, exterior packaging, or transport container or unpacked LSA-I substances or unpacked SCO-I must be multiplied by 100 and the resulting number is the transport index,

(b) for uranium and thorium ores and their concentrates are on the largest power input

of the dose equivalent at a distance of 1 m from the exterior surface stipulated these values:

(i) 0.4 mSv/h for uranium and thorium ore and their physical concentrates,

(ii) 0.3 mSv/h for chemical concentrations of thorium,

(iii) 0.02 mSv/h for chemical concentrations of uranium, except uranium hexafluoride,

(c) for cisterns, transport containers and unpacked LSA-I and SCO-I substances with a

value determined according to item (a) multiplied by the corresponding factor from Table 3. (6.) Annex No. 4,

(d) values determined according to point (a) and (b) are rounded up to one tenth (e.g.

from 1.13 to 1.2), with the exception of values of 0.05 or lower, which must be considered as zero.

27. (527.) The transport index for exterior packaging, transport containers or vehicles must

be stipulated either as the sum of transport indexes of radioactive consignments or by measuring the power input of the dose equivalent. An exception is soft exterior packaging, for which the transport index must be stipulated only as the sum of the transport indexes of all radioactive consignments contained within them.

Stipulated critical safety index

28. (528.) The critical safety index (CSI) for radioactive consignments containing fissile materials is determined by dividing the number 50 by the smaller of two “N” values, derived in items 81. and 82. part I. Annex No. 1 (i.e. CSI = 50/N). The value of the critical safety index can be zero if the number of unlimited radioactive consignments is sub-critical (i.e. that “N” is practically equal to infinity in both cases).

29. (529.) The critical safety index for each shipment must be stipulated as the sum of

individual CSIs of all radioactive consignments contained in the shipment.

Limits for transport index, the critical safety index and power input of the dose equivalent for radioactive consignments and exterior packaging

30. (530.) The transport index of individual radioactive consignments or exterior packaging cannot exceed the value of 10 and the critical safety index of individual radioactive consignments or exterior packaging cannot exceed 50 with the exception of shipments transported upon condition of exclusive use.

31. (531.) The power input of the dose equivalent cannot exceed 2 mSv/h on a random place

on the exterior surface of the radioactive consignment or exterior packaging, with the exception of radioactive consignments and exterior packaging transported upon condition of exclusive use by rail or road in accordance with the conditions stipulated in item 72 (a) Annex No. 4, or radioactive consignments and exterior packaging transported upon condition of exclusive use and upon special conditions by vessel or plane in accordance with the conditions stipulated in items 74. and 78. Annex No. 4.

32. (532.) The maximum power input of the dose equivalent on a random place on the

exterior surface of radioactive consignments transported upon condition of exclusive use cannot exceed 10 mSv/h.

Table 4. (7.) Categories of radioactive consignments and exterior packaging

ConditionsCategory

Transport index (TI) Maximum power input of the dose equivalent on random place on exterior surface

0 a greatest 0.005 mSv/h I-WHITEgreater than 0,but not greater than 1 a

greater than 0.005 mSv/h, but not greater than 0,5 mSv/h

II-YELLOW

greater than 1,but not greater than 10

greater than 0.5 mSv/h, but not greater than 2 mSv/h III-YELLOW

greater than 10 greater than 2 mSv/h, but not greater than 10 mSv/h III-YELLOW b

a) If the transport index is not greater than 0.05, the transport index according to 26.(c) Annex No. 4 can be considered equivalent to 0. b) Must be transported upon condition of exclusive use.

Categories of radioactive consignments and exterior packaging

33. (533.) Radioactive consignments and exterior packaging must be ranked in one of the I-WHITE, II-YELLOW or III-YELLOW categories according to the conditions stipulated in Table 4. (7.) Annex No. 4 and according to the following conditions:

(a) when determining the appropriate category for the radioactive consignment and

exterior packaging the transport index and the power input of the dose equivalent on the surface must also be taken into account. If the transport index meets the conditions for one category, but the power input of the dose equivalent on the surface value corresponds to another category, the radioactive consignment or exterior packaging will be assigned to the higher of the two categories. In this respect, the I-WHITE category is considered the lower category,

(b) the transport index is determined according to the procedures stipulated in items

26. and 27. Annex No. 4,

(c) if the power input of the dose equivalent on the surface is greater than 2 mSv/h, the radioactive consignment or exterior packaging must be transported upon condition of exclusive use and according to the corresponding conditions of items 73. (a), 75. or 79. Annex No. 4,

(d) radioactive consignments transported under special conditions are ranked in the III-YELLOW category, with the exception according to the stipulations of the following item 34,

(e) exterior packaging containing radioactive consignment, transported upon special conditions, is ranked in the III-YELLOW category, with the exception according to the stipulations of the following item 34.

34. (534.) For every radioactive consignment or exterior packaging a UN number and

official name for the transport must be designated (see Table 5. (8.) Annex No. 4 of this Decree). The UN number, official name for the transport, category ranking, marking and furnishing with safety labels must be in accordance with the decision of the competent authority of the country of origin of a construction type in all cases of international transport of radioactive consignments requiring type approval for packages or transport permits which are in different countries than the one in which the transport takes place issued different permits.

Table 5. (8.) Selection from the list of UN numbers, official names for transport and extra risk.

UN number

OFFICIAL NAME FOR TRANSPORTa and description Extra risk

2910 RADIOACTIVE SUBSTANCE, EXCLUSIVE UNIT – LIMITED NUMBER

2911 RADIOACTIVE SUBSTANCE, EXCLUSIVE UNIT – DEVICE or PRODUCT

2909 RADIOACTIVE SUBSTANCE, EXCLUSIVE UNIT – PRODUCT FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUMb

2908 RADIOACTIVE SUBSTANCE, EXCLUSIVE UNIT – EMPTY PACKAGE

2912 RADIOACTIVE SUBSTANCE WITH LOW SPECIFIC ACTIVITY (LSA-I) other than fissile or exclusive fissile

3321 RADIOACTIVE SUBSTANCE WITH LOW SPECIFIC ACTIVITY (LSA-II), other than fissile or exclusive fissileb

3322 RADIOACTIVE SUBSTANCE WITH LOW SPECIFIC ACTIVITY (LSA-III), other than fissile or exclusive fissile b

2913 RADIOACTIVE SUBSTANCE – SURFACE CONTAMINATED OBJECT (SCO-I or SCO-II), other than fissile or exclusive fissile b

2915 RADIOACTIVE SUBSTANCE, KUS TYPU A, other than special form, other than fissile or exclusive fissile b

3332 RADIOACTIVE SUBSTANCE, UNIT TYPE A, SPECIAL FORM, other than fissile or exclusive fissileb

2916 RADIOACTIVE SUBSTANCE, UNIT TYPE B (U), other than fissile or exclusive fissile b

2917 RADIOACTIVE SUBSTANCE, UNIT TYPE B (M), other than fissile or exclusive fissile b

3323 RADIOACTIVE SUBSTANCE, UNIT TYPE C, other than fissile or exclusive fissile b

2919 RADIOACTIVE SUBSTANCE, TRANSPORTED UPON SPECIAL CONDITIONS, other than fissile or exclusive fissile b

2978 RADIOACTIVE SUBSTANCE, HEXAFLUORIDE URANIUM, other than fissile or exclusive fissileb,c

Corrosive substance class 8

3324 RADIOACTIVE SUBSTANCE WITH LOW SPECIFIC ACTIVITY (LSA-II), FISSILE

3325 RADIOACTIVE SUBSTANCE WITH LOW SPECIFIC ACTIVITY (LSA-III), FISSILE

3326 RADIOACTIVE SUBSTANCE, SURFACE CONTAMINATED OBJECT (SCO-I or SCO-II), FISSILE

3327 RADIOACTIVE SUBSTANCE, UNIT TYPE A, FISSILE, other than special form

3333 RADIOACTIVE SUBSTANCE, UNIT TYPE A, SPECIAL FORM FISSILE

3328 RADIOACTIVE SUBSTANCE, UNIT TYPE B (U), FISSILE3329 RADIOACTIVE SUBSTANCE, UNIT TYPE B (M), FISSILE3330 RADIOACTIVE SUBSTANCE, UNIT TYPE C, FISSILE3331 RADIOACTIVE SUBSTANCE, TRANSPORTED UPON

SPECIAL CONDITIONS, FISSILE2977 RADIOACTIVE SUBSTANCE, HEXAFLUORIDE

URANIUM, FISSILEcCorrosive substance class 8

a) Official names for transports can be found in the column “OFFICIAL NAMES FOR TRANSPORT and description” and is limited to the parts written in CAPITAL LETTERS. In case of UN 2909 and UN 2911 and further UN 2913 and UN 3326 only corresponding official names for transport with alternative OFFICIAL NAMES FOR TRANSPORT which are separated by the word “or” can be used. b) Exclusive fissile materials are those fissile materials which meet the stipulations of item 72. part I. Annex No. 1. c) For uranium hexafluoride (other than fissile material or excluded fissile material), UN number 2978 has an official name for transport “RADIOACTIVE SUBSTANCE, URANIUM HEXAFLUORIDE, other than fissile or excluded fissile” priority over other UN numbers suitable for types other than fissile material or excluded fissile material. For uranium hexafluoride which is fissile material, UN number 2977 has an official name for transport “RADIOACTIVE SUBSTANCE, URANIUM HEXAFLUORIDE, FISSILE” priority over other UN numbers suitable for other types of fissile material. Marking and affixing safety labels

Marking 35. (535.) Each radioactive consignment must be visible, legible and permanently marked

on the exterior surface with the symbol of the shipper, receiver or both. 36. (536.) Each radioactive consignment, with the exception of excluded consignments,

must be visibly, legibly and permanently marked on the exterior surface with the number of the United Nations (hereinafter only the UN number) (see Table 5. (8.) Annex No. 4 of this Decree), before which the letters “UN” are prefixed and the official name for transport. Excluded consignments, if they were not received by international post transport, must be marked only with the UN number, before which the letters “UN” are prefixed. For radioactive consignments received by international post transport the stipulations of item 81. Annex No. 4 apply.

37. (537.) Each radioactive consignment with a gross weight greater than 50kg must be

visibly, legibly and permanently marked on the exterior surface with information about the real gross weight.

38. (538.) Each radioactive consignment which corresponds to structural type:

(a) industrial consignments types 1, 2 or 3 must be visibly, legibly and permanently marked on the exterior surface with the appropriate designation "TYPE IP-1", "TYPE IP-2" or "TYPE IP-3",

(b) consignment type A must be visibly, legibly and permanently marked on the

exterior surface with the letters "TYPE A", (c) industrial consignments type IP-2, IP-3 or radioactive consignments type A must

be visibly, legibly and permanently marked on the exterior surface with a distinctive label for the vehicle in international operation (VRI code), the country of origin construction type and either the mark of the producer or the identification marker of the package stipulated by the competent authority of the country of origin of a construction type.

39. (539.) Each radioactive consignment which corresponds to the type approval of a construction type must be visibly, legibly and permanently marked on the exterior surface: (a) identification marker attached by the authority, (b) production number uniquely identifying each package of a given type approved

construction type, (c) the letters "TYPE B(U)" or "TYPE B(M)" for radioactive consignments type

B(U), or type B(M), (d) the letters "TYPE C" for radioactive consignments type C.

Pic. 1. (1.) Basic three-leaf symbol of dimensions derived from the central circle of radius X. Minimum permitted size of X is 4 mm.

40. (540.) Radioactive consignments type B(U), type B(M) or type C must be marked with a three-leaf symbol a sample of which is in Pic. l (1.) on an external part of the surface which is resistant to fire and water and this by driving out, extracting or in another way which is resistant to fire and water.

41. (541.) If LSA-I or SCO-I substances contained in vessels or packed in packaging

materials are transported upon condition of exclusive use according to item 23. Annex No. 4; on the external surface this vessel or package must be marked either “RADIOACTIVE SUBSTANCE LSA-I” or “RADIOACTIVE SUBSTANCE SCO-I”.

Affixing safety labels

42. (542.) All radioactive consignments, exterior packaging and transport containers must be affixed with safety labels according to the corresponding category according to the sample in Pic. 2. (2.), Pic. 3. (3.), or Pic. 4. (4.) with the exception of large transport containers and cisterns for which the use of alternative safety labels according to the requirements of item 46. Annex No. 4 is permitted. In addition, each radioactive consignment, exterior packaging and transport container containing fissile material, with the exception of fissile materials excluded on the basis of the stipulations of item 72 part I. Annex No. 1, must be affixed with safety labels according to the sample in Pic. 5. (5.). Safety labels not related to the contents must be removed or covered up. For fissile materials or radioactive substances with other dangerous characteristics, the stipulations of item 7. Annex No. 4 apply.

43. (543.) Safety labels according to the samples in Pic. 2. (2.), Pic. 3. (3.), or Pic. 4. (4.)

must be placed on the exterior surface of two opposite sides of radioactive consignments, exterior packaging or on the exterior surface of all four sides of the transport container or cistern. If there is an obligation to affix safety labels according to the sample in Pic. 5. (5.), these safety labels must be placed in the immediate vicinity of the safety labels according to the sample in Pic. 2. (2.), Pic. 3. (3.), or Pic. 4. (4.). Safety labels cannot cover up markings stipulated in items 35. to 40. Annex No. 4.

Pic. 2. (2.) Safety label category I-WHITE. The back of the safety labels must be white; the colour of the three-leaf symbol and text must be black and the colour of the stripes indicating the category must be red.

Filling in safety labels according to the radioactive contents

44. (544.) Each safety label according to the sample in Pic. 2. (2.), Pic. 3. (3.), or Pic. 4. (4.). must be filled in with the following information:

(a) contents of the consignment

(i) in addition to LSA-I substances the safety labels must include the name of the radionuclide according to Table 1. (1.) Annex No. 3 using the symbol specified therein. For mixed radionuclides the most limiting nuclide is filled in as long as there is enough space in the row. The corresponding LSA group or SCO must be recorded after the name of the radionuclide. For this the expressions “LSA-II”, “LSA-III”, “SCO-I” and “SCO-II” are used;

(ii) for LSA-I substances the information “LSA-I” is sufficient; the name of the

radionuclide is not necessary. (b) the activity of radioactive contents during transport is expressed in Becquerel (Bq)

with attached relevant prefixes SI units. For fissile materials, instead of the activity, the total weight in grams (g) or in its multiples can be provided,

(c) for exterior packaging and transport containers, the markers for “contents” and

“activity” on safety labels must correspond to the relevant information required by points 44. (a) and 44. (b) Annex No. 4, with the total contents of exterior packaging and transport containers being counted. This does not apply for safety labels on exterior packaging and transport containers when the container’s contents are a mix of radioactive consignments with different radionuclides; for these, the marker must read: “See transport documents”;

(d) for I-WHITE category a record of the transport index is not required.

Pic. 3. (3.) Safety label category II-YELLOW. Back top half of the safety labels must be yellow and the bottom half white; the colour of the three-leaf symbol and text must be black and the colour of the stripes indicating the category must be red. Filling in safety label critical safety index value

45. (545.) Each safety label according to the sample in Pic. 5 must be filled in with a critical safety index value as is regulated in the decision on transport permits under special conditions or in the decision on type approval issued by the Authority.

46. (546.) For exterior packaging and transport containers the record of the critical safety index value on the safety label must correspond to the sum of the critical safety index required by item 45. Annex No. 4 all radioactive consignments contained in the exterior packaging or in the transport container.

Affixing large safety labels

47. (547.) Large transport containers which contain radioactive consignments with the

exception of excluded cargo and cisterns must be affixed with large safety labels according to the sample in pic. 6. (6.). The labels must be vertically fixed to the front, side and back walls of large transport containers or cisterns. Labels which do not refer to the contents must be removed or covered. Instead of this use of safety labels and large safety labels it is also permitted to use only the safety labels according to the sample in pic. 2. (2.), pic. 3. (3.), pic. 4. (4.) and pic. 5. (5.), but enlarged in such a way that they have the minimum dimensions shown in the sample in pic. 6. (6.).

Pic. 4. (4.) Safety label category III-YELLOW. The back upper half of the safety labels must be yellow and the lower half white. The color of the three-leaf label and text must be black and the color of the stripes marking the category must be red.

48. (548.) Deliveries of unpackaged LSA-I or SCO-I substances in the transport container or

cistern or deliveries of packaged fissile material or radioactive substances transported under the condition of exclusive use can be marked with one UN number on the transport container corresponding to the UN number of the delivery, and must be marked with black numbers at least 65 mm high, in the lower half of the large safety labels according to the sample in pic. 6. (6.), before which the letters “UN” are prefixed on a white background.

Pic. 5. (5.) Safety label critical safety index. Safety labels must be white on the back; the color of the text must be black.

Responsibilities of the shipper

49. (549.) The shipper is responsible for fulfilling the requirements of Items 20. (d) and 34. to 48. Annex No. 4 regarding markings and safety labels.

Pic. 6. (6.) Large safety label. With the exception permitted according to the stipulations of Item 71. Annex No. 4 the minimum dimension of the labels must be according to the pictured sample; if other dimensions are selected, similar proportions must be maintained. The numeral “7” must not be less than 25 mm high. The back upper half of the label must be yellow and the bottom half white; the color of the three-leaf label and of the text must be black. In the bottom half of the label the expression “Radioactive” can be used or record the corresponding UN number for the consignment instead.

Accompanying documents of the consignment

50. (550.) The shipper must provide documents accompanying each consignment with relevant information and maintain the specified order:

(a) The UN number of the associated substance according to Table 5. (8.) Annex No.

4 with prefixed letters “UN”, (b) official name for the shipment according to table 5. (8.) Annex No. 4; (c) class number “7”, (d) name or label of each radionuclide or for compounds of radionuclides a universal

label is sufficient or a list of restricted nuclides, (e) a description of the physical and chemical condition of the substance or

information regarding the radioactive substance in a special form or radioactive material with low diffusion. For the description of the chemical form a chemical sample can be used,

(f) maximum activity of radioactive contents during transport expressed in Becquerel (Bq) with attached corresponding prefix SI unit, for fissile material can be stated instead of the activity the total weight in grams (g) or in its multiples,

(g) category of radioactive cargo, i.e. I-white, II-yellow, III-yellow, (h) transport index (only for category II-yellow and III-yellow), (i) for deliveries containing fissile materials other than specified according to Item 72

part I. Annex No. 1, critical safety index,

(j) identification label for each decision about design approval or permit from the Authority responsible for the given consignment,

(k) for mass delivery of radioactive cargo in exterior packaging or transport container

a detailed manifest of the contents of each radioactive consignment inside each package or transport container, or as the case may be, each exterior package or transport container in the delivery. If there should be included individual radioactive cargo from the exterior packaging or transport container at certain places in the course of the transport, the corresponding transport documents must be available;

(l) if the delivery is being shipped upon condition of exclusive use, add the words

“Shipped upon condition of exclusive use”, (m) for mass delivery of substances LSA-II, LSA-III and SCO-I and SCO-II the total

activity of the delivery as a multiple of A2.

Declaration of the shipper

51. (551.) The shipper is obliged to include a document in the transport that declares the following text or a similar meaning: “I declare that the contents of this consignment fully includes the above-mentioned transport name, is categorized into groups, packed, marked and equipped with safety labels and is in all regards in a condition suitable for transport (fill in the type of transport) according to the requirements of the relevant international agreements and national legal regulations.”

52. (552.) If this declaration on transport conditions is issued in the framework of a specific

international agreement, the shipper cannot issue such a declaration for a part of the shipment that this international agreement does not apply to.

53. (553.) The declaration must be dated and signed by the shipper. A hand-written signature can be replaced by a fax only when the relevant laws and ordinances lawfully permit the legal validity of this kind of signature.

54. (554.) The declaration must be part of the document which describes the consignment

according to Item 50. Annex No. 4.

…

Removing or covering safety labels

55. (555.) If an empty package list is sent as an exclusive consignment according to the stipulations of Item 20. Annex No. 4, the original safety labels cannot be legible or visible.

Information for the shipper

56. (556.) The shipper must include a document in the transport with instructions and measures, if any are stipulated, which must be carried out by the shipper. The instructions must be in the language or languages requested by the shipper, Authority, or relevant authority of the country to which the transport is involved and must contain at least this information:

(a) additional measure during loading, placement for transport, transport, handling and

unloading radioactive cargo, exterior packaging or transport containers, including special conditions for heat removal (see Item 66. Annex No. 4) or instructions that these kinds of measures are not necessary,

(b) limitations from the Item of view of the type of transport or shipping means and all

required instructions about the route, (c) written instructions on emergency measures with regard to the relevant shipment.

57. (557.) Decision on the approval type or transport permit must accompany the consignment. The shipper, however, must ensure their availability for shipment before loading and unloading.

Notification of relevant authorities

58. (558.) Before the first transport of any radioactive cargo requiring approval or a permit from relevant competent authorities, the shipper must ensure that copies of the approval have been submitted to the relevant competent authorities of each state involved in the transport. The relevant competent authorities are not obliged to react to obtained notifications and the shipper is not obliged to wait for their reaction.

59. (559.) For every transport specified under letters a), b), c) or d) of this Item the shipper

must notify the relevant competent authorities of all the states involved in the transports. Every relevant competent authority must obtain this notification before the start of transport, if possible at least 7 days before.

(a) type C radioactive cargo with fissile materials or radioactive substances, whose

activity is greater than 3.103 A1 or 3.103 A2 or 1000 TBq, according to the value that is lower,

(b) type B(U) radioactive cargo with fissile materials or radioactive substances, whose

activity is greater than 3.103 A1 or 3.103 A2 or 1000 TBq, according to the value that is lower,

(c) type B(M) radioactive cargo, (d) transport with special conditions.

60. (560.) The notification of the shipper must contain:

(a) sufficient information to permit identification of the radioactive cargo or radioactive cargo, including all required numbers of decisions and identification markers,

(b) information about the date of transport, the expected arrival date and the expected

route, (c) name of fissile material or radioactive substance or nuclide, (d) description of the physical condition and chemical form of the radioactive

substance or information that it involves radioactive substances of a special form or radioactive substance with low diffusion,

(e) maximum activity of radioactive contents during transport expressed in Becquerel (Bq) with attached corresponding prefix of the SI unit; for fissile material instead of the activity the total weight in grams (g) or in its multiples can be stated.

61. (561.) The shipper must not send a separate notification if the required information was

contained in the application for a transport permit.

Documentation and operating instructions which the shipper must possess

62. (562.) The shipper must have copies of every decision by the Authorities and copies of instructions for correct enclosure of radioactive cargo and all measures for transporting the shipment before the transport is carried out according to the conditions of this decision.

Transport and transit storage during transport

Separation during transport and during transit storage during transport

63. (563.) Radioactive cargo, exterior packaging or transport containers containing fissile materials or radioactive substances must during transport and during transit storage during transport be separated from:

(a) places used by personnel and from undeveloped photographic film in order to limit exposure to ionising radiation,

(b) other dangerous objects in accordance with Item 6 Annex No. 4.

64. (564.) Radioactive cargo or exterior packaging of category II-YELLOW or III-YELLOW c transported separately with the exception of places designated for personnel entrusted with the safe conduct of these radioactive cargo or exterior packaging.

Placement of the consignment on the vehicle and transit storage during transport

65. (565.) The cargo must be safely stored during transport, i.e. in such a way to avoid shifting, turning over or falling.

66. (566.) If the average surface heat flow of radioactive cargo or exterior packaging does not exceed 15 W/m2 and if objects in the immediate vicinity are not packed in bags or sacks, the radioactive consignment or exterior packaging transported without special requirements with regard to placement for transport together with other packed cargo, however, as long as the relevant permits or approval from the Authority, or for international transport from relevant competent authorities of the countries involved in the transport is not specified explicitly or otherwise.

67. (567.) The loading of transport containers and distribution of radioactive cargo, exterior

packaging or transport containers takes place in the following way:

(a) with the exception of transports on the conditions of exclusive use and shipments of LSA-I substances, the total number of radioactive cargo, exterior packaging or transport containers on one shipment is limited in such a way so that the total sum of the transport index does not exceed the value shown in Table 6. (9.) Annex No. 4 of this notice,

(b) for common transport conditions the power input of the dose equivalent cannot be

on any part of the exterior surface of the vehicle greater than 2 mSv/h and at a distance of 2 m from the exterior surface of the vehicle 0.1 mSv/h, with the exception of shipments transported upon the condition of exclusive use by road or rail, for which the power input of the dose equivalent is stipulated in Item 73. letters b) and c),

(c) the total number of critical safety indexes in the transport container and the vehicle cannot exceed the value shown in Table 7. (10.) Annex No. 4 of this notice.

Table 6. (9.) Transport index (TI) for transport containers and for vehicles not transported upon the condition of exclusive use

Type of transport container or shipping means Total number of transport index (TI) in transport container or vehicle

Transport container – small 50Transport container – large 50Vehicle 50Plane for transporting people

for transporting cargo50200

Domestic craft 50Sea-going vessel a

(1) Stowage space, separated or demarcated deck space forradioactive consignment, exterior packaging or small transport

containerlarge transport container

(2) Total sea-going vesselradioactive consignment, exterior packaging or small transport

containerlarge transport container

50200

200unlimited

a) Radioactive cargo or exterior packaging on vehicles which fulfill the requirements of Item 73. Annex No. 4, can be transported on crafts if they are not unloaded from the vehicle for the whole course of the transport on the deck of the craft.

68. (568.) Each radioactive consignment or exterior packaging with a transport index

greater than 10 and every shipment with a critical safety index greater than 50 must be transported only upon condition of exclusive use.

Separating radioactive cargo containing fissile materials during transport and transit storage

69. (569.) In transit storage during transport with any storage space the number of radioactive cargo, exterior packaging and transport containers containing fissile materials must be confined in such a way that the total number of the critical safety index does not exceed 50 in one group of this kind of radioactive cargo, exterior packaging and transport containers. Groups of radioactive cargo, exterior packaging and transport containers confined in this way must be stored in such a way as to keep a distance of at least 6 m between them.

Table 7. (10.) Critical safety index (CSI) for transport containers and vehicles containing fissile materials

Type of transport container or vehicle

Total number of critical safety index (CSI) in transport container or on vehicle

Other transport

Transport upon condition of exclusive use

Transport container – small 50 –Transport container – large 50 100Vehicle 50 100Plane:

for transporting peoplefor transporting cargo

5050

–100

Domestic craft 50 –Sea-going vessel a:

(1) Stowage space, separated or demarcated deck space forradioactive consignment, exterior packaging or small

transport container-large transport container

(2) Total sea-going vessel-radioactive consignment, exterior packaging or small transport

container-large transport container

5050

200 b

unlimited b

100100

200 c

unlimited c

a) Radioactive cargo or exterior packaging on vehicles which fulfill the requirements of Item 73. Annex No. 4, can be transported on crafts if they are not unloaded from the vehicle for the whole course of the transport on the deck of the craft. In this case information is used from the column with the header “Transport upon condition of exclusive use”.

b) Handling the shipment and its storage for transport must be carried out in such a manner that the total critical safety index (CSI) does not exceed 50 in any group and handling of all of these kinds of groups and its storage for transport must be carried out in such a manner that the groups are separated by a distance of at least 6 m. c) Handling the shipment and its storage for transport must be carried out in such a manner that the total critical safety index (CSI) does not exceed 100 in any group and handling of all of these kinds of groups and its storage for transport must be carried out in such a manner that the groups are separated by a distance of at least 6 m. The space between the groups can be occupied by other cargo in accordance with Item 5. Annex No. 4. 70. (570.) If the total critical safety index on the vehicle or transport container exceeds 50,

as table 7. (10.) Annex No. 4 allows, it must be stored in such a manner as to keep a distance of at least 6 m between these vehicles or transport containers and other groups of radioactive cargo, exterior packaging or transport containers containing fissile materials or other vehicles transporting fissile materials or radioactive substances.

Additional requirements for transport by rail and road

71. (571.) Rail and road vehicles transporting radioactive cargo, exterior packaging or transport containers furnished with safety labels according to the sample in pic. 2. (2.), pic. 3. (3.), pic. 4. (4.) or pic. 5. (5.) or transport of cargo upon the condition of exclusive use must be furnished with large safety labels according to the sample in pic. 6. (6.):

(a) from the exterior on both sides for rail vehicles, (b) from the exterior on both sides and on the back for road vehicles.

NoteFor vehicles that do not have sides, the large safety labels can be placed directly on the carriage carrying the cargo if they are easily visible there; for large-volume cisterns or transport containers the labels can be placed directly on them. For vehicles which do not have enough space for larger labels, the dimensions of the labels can be reduced according to the sample in pic. 6. (6.) to a size of 100 mm on each side. All labels on the vehicle not related to the cargo must be removed.

72. (572.) If the consignment on the vehicle is an unpackaged LSA-I or SCO-I substance or

the consignment is transported upon the condition of exclusive use of packaged fissile material or radioactive substance with one UN number, the corresponding UN number, see table 5. (8.) Annex No. 4, must be marked in black numerals at least 65 mm high in the bottom part of the large safety labels according to the sample in pic. 6 (6.), before which the letters “UN” are prefixed on a white background.

73. (573.) In case of cargo transported upon condition of exclusive use the power input of

the dose equivalent cannot exceed:

(a) 10 mSv/h in any exterior surface of radioactive cargo or exterior packaging; however, it can exceed 2 mSv/h if:

(i) the vehicle is equipped with an extension which prevents unauthorized

persons from entering the interior of the structure during regular transport conditions;

(ii) such measures are carried out to fortify radioactive cargo or exterior

packaging that its position inside the vehicle during regular transport conditions does not change; and

(iii) no loading or unloading will take place during transport;

(b) 2 mSv/h in any place exterior surface of vehicle including roofs and floors or for open vehicles in any place found on a vertical plane extending outside the vehicle, on top of the cargo and lower external surface of the vehicle; and

(c) 0.1 mSv/h at a distance of 2 m from the vertical plane, whose parts are an external surface of the vehicle or if the cargo is transported in an open vehicle, at a distance of 2 m from the vertical plane, which extends outside the vehicle.

74. (574.) For road vehicles, no one besides the driver and his assistant are permitted to

handle the vehicle transporting radioactive cargo, exterior packaging or transport containers marked with safety labels category II-YELLOW or III-YELLOW.

Additional requirements for transport by ship

75. (575.) Radioactive cargo or exterior packaging with power input of a dose equivalent on the surface greater than 2 mSv/h, besides those that are transported on vehicles upon condition of exclusive use in accordance with table 6. (9.) Annex No. 4, Note (a), cannot be transported by ship, with the exception of those that are transported under special conditions.

76. (576.) Transportation of cargo realized by ship for special purposes, on the basis of a

project solution or rental conditions designated for the transport of radioactive substances is excluded from the requirements shown in Item 66. Annex No. 4 if the following conditions are also fulfilled:

(a) for transport a program of radiation protection is developed which is approved by the competent authority of the state in which the craft is registered and if it is requested and the competent authority of each port in which the craft anchors,

(b) conditions for placement in the vehicle are firmly stipulated for the whole route

and also apply to the consignment which can be loaded during the trip during stopovers,

(c) cargo handled with the consignment and unloading taking place under the

supervision of a person qualified in the area of transporting radioactive substances.

Additional requirements for air transport

77. (577.) Radioactive cargo type B(M) and cargo transported upon condition of exclusive use cannot be transported by planes used to transport people.

78. (578.) Radioactive cargo type B(M) cooled by air, radioactive cargo requiring external

cooling by a cooling system, radioactive cargo subject to transport checks during transport and radioactive cargo containing liquid pyrophosphate materials cannot be transported by plane.

79. (579.) Radioactive cargo or exterior packaging with power input of the dose equivalent

on the surface greater than 2 mSv/h, cannot be transported by plane with the exception of cargo that is transported under special conditions.

Additional requirements for international transport by post

80. (580.) Cargo which fulfills the requirements of Item 15. Annex No. 4 and whose radioactive activity does not exceed the limit of one tenth prescribed in table 3. (3.) Annex No. 3, can be received for transport by post in states where this kind of transport is permitted; however they must fulfill additional requirements which can be stipulated by the competent postal service. In the Czech Republic, domestic transport of radioactive substances by post is not permitted.

81. (581.) Cargo which fulfills the requirements of Item 15. Annex No. 4 and whose

radioactive activity does not exceed the limit of one tenth prescribed in table 3. (3.) Annex No. 3, can be received by international postal transport delivered outside the territory of the Czech Republic; however, they must fulfill the following additional requirements of prescribed individual regulations of the World postal union:

(a) delivered by post only by shippers authorized by competent authorities; (b) delivered in the fastest way, usually by air; (c) clearly and permanently marked on the surface with the words “RADIOACTIVE

SUBSTANCE – AMOUNT PERMITTED FOR POSTAL TRANSPORT”; these words must be crossed out if the package is returned empty;

(d) on the surface marked with the name and address of the shipper with request to

return to sender if not delivered; (e) name and address of the shipper and description of the contents of the shipment

provided also inside the package.


STANDARD DOCUMENT FOR SUPERVISING THE TRANSPORT OF RADIOACTIVE WASTE AND SPENT FUEL AND ITS MONITORING (DIRECTIVE OF COUNCIL

2006/117/Euratom)General remarks:

Parts A1–A6 are filled in for transport of radioactive waste and parts B-1 to B-6 are filled in for transport of spent fuel (including spent fuel intended for final storage, which is therefore classified as waste).Part A-1 or B-1 (application for transport permit): filled in by the applicant, who according to the type of transport is a:

holder in case of transport between Member States (MM) or export from the Community to a third country (ME);

recipient in case of import to the Community from a third country (IM);

person responsible for transport in a Member State, which radioactive waste or spent fuel enters the Community in case of transport to the Community (TT).

Part A-2 or B-2 (confirmation of application receipt): filled in by the competent affected authorities, which according to the type of transport are the competent authorities of the

country of origin for MM or ME transport;

country of destination for IM transport;

country where the consignment first enters the Community for TT transport;

and all competent authorities of the transit Member State.Part A-3 or B-3 (refusal or acceptance): filled in by all competent affected authorities.Part A-4a/A-4b or B-4a/B-4b (permission or refusal to transport): filled in by the competent authority responsible for issuing permits, which according to the type of transport are the competent authorities of the

country of origin for MM or ME transport;

country of destination for IM transport;

country where the consignment first enters the Community for TT transport.Part A-5 or B-5 (description of consignment / list of packaging): filled in by the applicant mentioned in part A-1 or B-1.Part A-6 or B-6 (Confirmation of consignment acceptance): filled in by the recipient (for MM and IM transport) or the holder (ME transport) or the person responsible for the transport (TT transport).

Registration No.: _______________________________________________ (filled in by the authority responsible for issuing transport permits)

PART A-1APPLICATION FOR PERMIT TO TRANSPORT

RADIOACTIVE WASTE (1) Type of transport (check the applicable box):

□ MM: Transport between Member States (through one or more Member States or third countries)□ IM: import to the Community□ ME: export from the Community□ TT: transit through the territory of the Community

(2) Application for permit for (check the applicable box):□ one-time transport ____________________ Planned implementation period: __________________□ repeated transport : number (planned):___________ Planned implementation period:____________

(3) □ not used. □ MM transport through one or more third countries:Exit border crossing of the Community*:______________________________________________Entrance border crossing of a third country* (first transit country):________________________________Exit border crossing of a third country* (last transit country):______________________________Border crossing during re-import to the Community*: _____________________________________(*)These crossing must be the same for all transports mentioned in the application unless the competent authority permits otherwise.

(4) Applicant (commercial name):_________________________________________________________□ Holder (for MM, ME),____ □ Recipient (for IM), ___□ Other (for TT), provide details: __________________________________________________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country:_______________________Tel.:_________________ Fax:_____________________ E-mail:______________________________Contact person: Mr./Ms._____________________________________________________________

(5) Storage of radioactive waste before transport (commercial name): ___________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:______________________________Contact person: Mr./Ms._____________________________________________________________

(6) Recipient (commercial name): __________________________________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:__________________________Contact person: Mr./Ms._____________________________________________________________

(7) Storage of radioactive waste after transport: _________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:__________________________Contact person:

Mr./Ms.:_____________________________________________________________(8) Characteristics of radioactive waste:_______________________________________________

Physical-chemical characteristics (check the applicable box): □ solid, □ liquid, □ gas, □ other (e.g. fissile, with low diffusion,…), provide details:_________________________________________Main radionuclids:_________________________________________________________________Maximum alpha radiation activity on the consignment (GBq):_______________ on packaging (GBq):______________Maximum beta/gamma radiation activity on the consignment (GBq):__________ on packaging (GBq):_____________Total alpha radiation activity (GBq):____________ Total beta/gamma radiation activity (GBq):_________ (These values are only estimates if the application involves repeated transport)

(9) Total amount of packaging:___________________________________________________________Total net weight of consignment (kg):_____________Total gross weight of consignment (kg):__________(These values are only estimates if the application involves repeated transport)Description of consignment :□ plastic bag, □ metal drum (m3):_________, □ transport container ISO (m3):_________, □ other, provide details:_________________________________________________Type of packaging 14 (if known):_________________________________________________________Method of marking individual packaging (when marking labels provide an example):____________________

(10) Type of activity that created the radioactive waste (check the applicable box): □ medical, □ research, □ (non-nuclear) industrial, □ nuclear industrial, □ other activity (provide details):___________________

(11) Purpose of transport:□ Return radioactive waste after processing or reprocessing of spent fuel□ Return of radioactive waste after processing radioactive waste□ Processing, e.g. packaging, new packaging, adjustment, reduction of volume□ Temporary storage□ Return after temporary storage□ Final disposal□ Other purpose (provide details):_______________________________________________________

(12) Proposed type of shipping (road, rail, sea,

air, domestic water)

Place of dispatch: Destination: Proposed shipper (if known):

1.

2.

3.

4.

5.

6.

7.

8.(13) Successive list of countries affected by the transport (first is the country of origin of the radioactive

waste and the last is the country of destination)

1. 3. 5. 7.

14 According to the Rules for safe transport of radioactive materials serving for protection of people and the environment, safety requirements No. TS-R-1, safety requirements, IAEA, Vienna, 2005

2. 4. 6. 8.(14) According to the regulations of directive 2006/117/Euratom, I, as the applicant:

1. Apply for permission to realize (repeated) transport of the above-mentioned radioactive waste and2. I confirm that the above information is true according to my best knowledge and conscience and that (repeated) transport will take place in accordance with all applicable legal regulations, and3.*(for MM or ME transports) I undertake to transport waste back if it will not be possible to realize (repeated) transport or if it will not be possible to fulfill the conditions of transport; or*(for IM or TT transports) I will attach a document on arrangements between the recipient and the holder of radioactive waste settled in third countries, which was accepted by the competent authority in the third country and which states that the holder in the third party will transport radioactive waste back if it will not be possible to realize (repeated) transport or if it will not be possible to fulfill the conditions of transport, if no other alternative safety measures are accepted.(*) Only one of the options marked with a star can be used: cross out those that are not applicable.

__________________________________________________________________________________

(date and place)…………………………(stamp)………………………..(signature)


PART A-2CONFIRMATION OF RECEIPT OF APPLICATION TO TRANSPORT RADIOACTIVE

WASTE – REQUEST FOR MISSING INFORMATION

(15) Name of competent authority responsible for issuing permits ________________________________________________________________________________________________________Member State:________________________________________________________________________□ origin 15, □ destination 16, □ where the consignment will first enter the Community17

Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax.:_____________________ E-mail:_____________________________Contact person: Mr./Ms._______________________________________________________________

Date of receipt /registration:________________________________________________(dd/mm/yyyy)

(16) Name of competent authority:______________________________________________Member State or country (check the applicable box) □ destination, □ transit, □ where the consignment will first enter the Community or □ origin 18:________________________________________________ Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:___________________________________Contact person: Mr./Ms._______________________________________________________________

(17) According to the stipulations of directive 2006/117/Euratom considers the application from ____________________(dd/mm/yyyy), which was received on ____________________dd/mm/yyyy)a) * incomplete and request this missing information to be filled in: (If there is not enough space, provide the whole list of missing information (items) in a separate attachment) ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________...............................(date and place)……………… (stamp)………………………..(signature).....................b) *duly filled in and confirm its receipt.

15 For MM or ME cargo.16 For IM cargo. 17 For TT cargo.18 E.g. in third countries with which transport must be consulted.

__________________________________________________________________________________.......................(date and place).......................(stamp)……………………..(signature).......................(*) Only one of the options marked with a star can be used: cross out those that are not applicable.


PART A-3REFUSAL OR ACCEPTANCE OF CARGO OF RADIOACTIVE WASTE BY AFFECTED

COMPETENT AUTHORITIES

(18) Name of affected competent authority:______________________________________________Member State or country (check the applicable box and fill in) □ origin 19 , □ destination 20, □ transit21:________________________________________________________ Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:__________________________________Contact person: Mr./Ms.______________________________________________________________

(19) *) General term for automatic acceptance ______________________________(dd/mm/yyyy)

*) Application for further period not more than one month, prolongation of term for automatic acceptance: _______________________________________________________________(dd/mm/yyyy)

__________________________________________________________________________________(date and place)…………………………

__________________________________________________________________________________(stamp)………………………..(signature)………………..

(*) Only one of the options marked with a star can be used: cross out those that are not applicable. (20) According to the stipulations of directive 2006/117/Euratom

**I refuse for these reasons (if there is not enough space, provide the full list of reasons in a separate attachment):__________________________________________________________________________ ____________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

__________________________________________________________________________________(date and place)…………………………

__________________________________________________________________________________(stamp)………………………..(signature)………………..

**I accept under these conditions (if there is not enough space, provide the full list of reasons in a separate attachment):________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

__________________________________________________________________________________.......................(date and place).......................(stamp)……………………..(signature).......................

(**) Only one of the options marked with a star can be used: cross out those that are not applicable.

19 For TT and IM cargo the country of origin can be voluntarily consulted; however, the directive does not absolutely require this.20 For MM or ME cargo. 21 For MM, IM, ME or TT cargo if at least one Member State is affected by the transit.


PART A-4ATransport permit FOR radioactive WASTE

(21) Name of competent authority responsible for issuing transport permits: ___________________________________________________________________________________Member State (check the applicable box and fill in): ______________________________ □ origin , □ destination or □ where the waste will exit the CommunityAddress:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:__________________________________Contact person: Mr./Ms._______________________________________________________________

(22) Enumeration of cases approved and/or refused by countries affected by the transport:

Member State or country

Approved?

Enumeration of competent conditions for approval: Reference to supplements

1. YES/NO*

2. YES/NO*

3. YES/NO*

4. YES/NO*

5. YES/NO*

6. YES/NO*

7. YES/NO*

8. YES/NO*

(23) The approved decision in this part was made in accordance with the stipulations of directive 2006/117/Euratom.22

The competent authorities of the affected countries have been informed that theone-time transport*repeat transport*of radioactive waste described in part A-1 was

PERMITTED Expiry date of permit: ____________________________________________(dd/mm/yyyy)

__________________________________________________________________________________…… (date and place)…………….……………….. (stamp) …………………………… (signature)……………(*) Only one statement marked with a star is used; cross out those that are not applicable.

22 This permit in no way decreases the responsibility of the holder, shipper, owner, recipient or any other physical or legal entity affected by the consignment.


PART A-4BREFUSAL TO transport radioactive WASTE

(24) Name of competent authority responsible for refusal of transport:_____________________________________________________________________________________________________Member State (check the applicable box and fill in): ______________________________ □ origin, _____□ destination ___□ transit ___or □ where the waste exits the CommunityAddress:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:__________________________________Contact person: Mr./Ms._______________________________________________________________

(25) Enumeration of cases that were approved and/or refused by affected countries:

Member State / country

Approved ?

Enumeration of competent conditions of acceptance or reasons for refusal:

Reference to supplements

1. YES/NO*

2. YES/NO*

3. YES/NO*

4. YES/NO*

5. YES/NO*

6. YES/NO*

7. YES/NO*

8. YES/NO*

The approved decision in this part was made in accordance with the stipulations of directive 2006/117/Euratom. The competent authorities of the affected countries have been informed that theone-time transport*repeat transport*of radioactive waste described in part A-1 was

REFUSED

__________________________________________________________________________________(date and place)…………………………(stamp)………………………..(signature)

(*)Only one statement marked with a star is used; cross out those that are not applicable.


PART A-5DESCRIPTION OF CONSIGNMENT OF RADIOACTIVE MATERIAL AND LIST OF

PACKAGING

(26) Applicant (commercial name):_______________________________________________________________□ holder,____ □ recipient,____□ other, provide details:_____________________________________Address:____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:__________________________________Contact person: Mr./Ms.:_______________________________________________________________

(27) Expiry date of permit __________________________________(dd/mm/yyyy), for □ one-time transport or □ repeat transport, serial number of consignment: _______________________

(28) Characteristics of radioactive wastePhysical-chemical characteristics (check the applicable box): □ solid, □ liquid, □ gas, □ other (e.g. fissile, with low diffusion,…), provide details:________________________________________________Main radionuclids:____________________________________________________________________Maximum alpha radiation activity on the consignment / packaging (GBq):________________________________________Maximum beta/gamma radiation activity on the consignment / packaging (GBq): __________________________________Total alpha radiation activity (GBq):____________Total beta/gamma radiation activity (GBq):_________

(29) *ID No. *Type 23 *Gross weight (kg)

*Net weight(kg) *Activity (GBq)

Total amount: Total/type: Total: Total: Total:

(*) Filled in for each packaging; if there is not enough space, attach a separate list!

(30) Consignment dispatch date: ____________________________________________ (dd/mm/yyyy) I confirm that the information provided in this part (and in the attached lists or documents) is according to my best knowledge and conscience true.

__________________________________________________________________________________

23 According to the Rules for safe transport of radioactive material, safety requirements TS-R-1, IAEA, Vienna, 2005



PART A-6CONFIRMATION OF Receipt OF radioactive WASTE

(31) Recipient (commercial name): _____________________________________________________________ Address:_____________________________________________________________________________Post code:________ City:___________________ Country :________________________Tel.:_________________ Fax:_____________________ E-mail:_______________________________Contact person:

(32) Storage of radioactive waste for transport: ______________________________________ Address:_____________________________________________________________________________Post code:________ City:___________________ Country :________________________Tel.:_________________ Fax:_____________________ E-mail:_______________________________Contact person: Mr./Ms._______________________________________________________________

(33) Permit granted (check the applicable box):□ for one-time MM or IM transport,□ for one-time ME or TT transport,□ for repeat MM or IM transport, serial number of consignment: ____________________________Last transport to which the permit applies: □Yes □No□ for repeat ME or TT transport, serial number of consignment: ____________________________Last transport to which the permit applies: □Yes □No

(34) □ Not used . □ ME or TT transport (this item can be replaced with a separate permit; set in reference to supplement):

Entry border crossing to third country destination or transit:______________________Third country:____________________ Border crossing:______________________________________

(35) The recipient must send confirmation of receipt together with part A-5 according to the type of transport: (MM or IM): to the competent authority of the destination Member State, (ME or TT): to applicants (ME: holders, TT: to the person responsible for the transport in the

Member State where waste enters the Community), according to item 4 (part A-1).Date of receipt of radioactive waste:______________________________________(dd/mm/yyyy)Date of sending confirmation of receipt:_______________________________________(dd/mm/yyyy)I, as the recipient, confirm that the information in this part (and attached lists) is according to my best knowledge and conscience true.

__________________________________________________________________________________


(36) □ Not used . □ ME or TT transport: the applicant sends confirmation of receipt and if necessary the recipient permits to the authority which issued the permit.1. A recipient with registered seat outside the European Union can confirm the receipt of radioactive waste by means of a declaration or attestation that includes the information shown in items 31 to 36. 2. The competent authority which holds the original confirmation of receipt must send a copy of it to the other competent authorities. 3. The originals of parts A-5 and A-6 must be sent to the competent authority which issued the permit.

4. For transport between Member States the competent authority of the Member State of origin or the state where the consignment first enters the Community, send a copy of the confirmation of receipt to the holder.

Dispatch date of confirmation of receipt (together with part A-5): ____________(dd/mm/yyyy)

Exit border crossing from Community:

Country: Border crossing:

__________________________________________________________________________________

(date and place).......................(stamp)……………….(signature of applicant)


PART B-1APPLICATION FOR TRANSPORT PERMIT FOR

SPENT FUEL (1) Transport type (check the applicable box):

□ MM: Transport between Member States (through one or more Member States or third countries)□ IM: Import to Community□ ME: Export from Community□ TT: Transit through Community territory

(2) Application for permit for (check the applicable box):______________________________________□ one-time transport _________________ Planned implementation period:_______________________□ repeat transport : number (planned):___________ Planned implementation period:______________

(3) □ Not used. □ (Repeat) MM transport through one or more third countries:Community exit border crossing *:______________________________________________Third country entry border crossing * (first transit country):________________________________Third country exit border crossing * (last transit country):______________________________Border crossing for repeat import to Community*: _____________________________________(*)These border crossings must be the same for all transports specified in the application unless the competent authority permits otherwise.

(4) Applicant (commercial name):___________________________________________________________□ Holder (for MM, ME), □ Recipient (for IM), □ Other (for TT), provide details:__________________________________________________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:______________________________Contact person: Mr./Ms._______________________________________________________________

(5) Storage of spent fuel before transport (commercial name): ___________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:______________________________Contact person: Mr./Ms._______________________________________________________________

(6) Recipient (commercial name): ____________________________________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel.:_________________ Fax:_____________________ E-mail:__________________________Contact person: Mr./Ms._______________________________________________________________

(7) Storage of spent fuel after transport: _________________________________ Address:___________________________________________________________________________Post code:________ City:___________________ Country :_______________________Tel:_______________ Fax:________________ E-mail:________________________________________Contact person: Mr./Ms.:_______________________________________________________________

(8) Type of spent fuel: □ metallic uranium, □ uranium oxide, □ mixed fuel (MOX), □ other, provide details: ____________________________________________________________________________________

Original fission substance: □ uranium-235_____________________[maximum enrichment……………….%]□ MOX____________________________________________ [standard enriched uranium………….%]__________________________________________________ [maximum plutonium contents ……….%]□ other, provide details__________________________________________________________________

Spent fuel (average or normal range):______________________________MWdny/teHM (9) Total amount of packaging (e.g.

containers):_________________________________________________Total amount of files/packets/components/specimens (provide details):____________________________Total net weight(kg):_____________________Total gross weight (kg):_________________(These values are estimates if the application concerns repeat transport)

Description of consignment (e.g. containers):________________________________________________Type of packaging 24 (if known):__________________________________________________________Maximum volume of spent fuel in one packaging (kg):______________________________________Method of marking individual packaging (when marking labels provide an example):________________

(10) Type of activity that created the spent fuel (check the applicable box)_________________ □ research, □ commercial production of nuclear energy, □ other activity (provide details):______________________

(11) Purpose of transporting spent fuel:□ Processing or reprocessing □ Temporary storage□ Return after temporary storage□ Final disposal□ Other purpose (provide details):_____________________________________________________________

(12) Proposed type of shipping (road, rail, sea, air, domestic water)

Place of dispatch: Place of receipt: Proposed shipper (if known):

1.

2.

3.

4.

5.

6.

7.

8.(13) Enumeration of countries affected by the transport of spent fuel (first is the country in which the spent

fuel originates and the last is the country of destination)1. 3. 5. 7.

2. 4. 6. 8.

24 According to the Rules for safe transport of radioactive material, safety requirements TS-R-1, IAEA, Vienna, 2005

(14) According to the stipulations of directive 2006/117/Euratom, I, as the applicant:1. apply for a permit to perform (repeated) transport of the above-mentioned spent fuel and2. certify that the information provided is true according to my best knowledge and conscience and that (repeated) transport will take place in accordance with all the valid legal regulations, and 3. *(for MM or ME transport) undertake to take back spent fuel if it will not be possible to realize (repeated) transport or if it will not be possible to meet the conditions of transport; or *(for IM or TT transport) attach a document on the agreement between the recipient and the holder on spent fuel settled in a third country, which is accepted by the competent authority of this third country and which states that the holder in the third country will take back the spent fuel if it will not be possible to realize (repeated) transport or it will not be possible to meet the conditions of transport.(*) Only one of the options marked with a star can be used: cross out those that are not applicable.



PART B-2CONFIRMATION OF RECEIPT OF APPLICATION TO TRANSPORT SPENT FUEL –

REQUEST FOR MISSING INFORMATION

(15) Name of competent authority responsible for issuing permits ________________________________________________________________________________________________________Member State:________________________________________________________________________□ origin 25, □ destination 26, □ transit or □ where spent fuel enters the Community27

Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax.:_____________________ E-mail:_____________________________Contact person: Mr./Ms._______________________________________________________________

Date of receipt/registration:_________________________________________________(dd/mm/yyyy)

(16) Name of affected competent authority:______________________________________________Member State or country (check the appropriate box) □ origin, □ destination, □ transit:____________________________________________________________ Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:___________________________________Contact person: Mr./Ms._______________________________________________________________

(17) According to the stipulations of directive 2006/117/Euratom the application is considered from ____________________(dd/mm/yyyy), which was received on ____________________dd/mm/yyyy)a) *incomplete and I request to fill in the missing information: (if there is not enough space provide a complete list of missing information (items) in a separate attachment)______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

____________________________________________________________________________________..................(date and place)………………..…(stamp)………………………………..(signature)b) *duly filled in and confirm its receipt.

_________________________________________________________________________________

25 For MM or ME consignments.26 For IM consignments. 27 For IM or TT consignments.

_...................(date and place)…………………………(stamp)………………………..(signature)(*) Only one of the options marked with a star can be used: cross out those that are not applicable.


PART B-3REFUSAL OR APPROVAL TO TRANSPORT SPENT FUEL FROM AFFECTED

COMPETENT AUTHORITIES

(18) Name of affected competent authority:______________________________________________Member State or country (check the applicable box and fill in) □ origin 28, □ destination 29, □ transit30:_________________________________________ Address:_____________________________________________________________________________Post code:__________ City:_____________ Country:___________________________Tel.:___________________ Fax:________________ E-mail:__________________________________Contact person: Mr./Ms._______________________________________________________________

(19) *) Deadline for automatic conferment of acceptance: _________________________(day/month/year)

*) Request for further period not more than one month, extension of deadline for automatic approval: _______________________________________________________________(dd/mm/yyyy)

__________________________________________________________________________________(date and place)…………………………

__________________________________________________________________________________(stamp)………………………..(signature)………………..

(*) Only one of the options marked with a star can be used: cross out those that are not applicable.

(20) According to the stipulations of directive 2006/117/Euratom **I refuse for this reason (if there is not enough space provide a complete list of reasons in a separate attachment): ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

__________________________________________________________________________________(date and place)………………………… (stamp)………………………..(signature)………………..

**I approve under these conditions (if there is not enough space provide a complete list of conditions in a separate attachment):________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

__________________________________________________________________________________(date and place)………………………… (stamp)………………………..(signature)………………..

(**) Only one of the options marked with a star can be used: cross out those that are not applicable.

28 For TT and IM consignments the country of origin can be consulted, however, the directive does not require this.29 For MM consignments. 30 For MM, IM, ME or TT consignments, if at least one transit state is affected.


PART B-4ATransport permit FOR spent fuel

(21) Name of competent authority responsible for issuing transport permits:_______________________ ___________________________________________________________________________________Member State (check the applicable box and fill in): ___________________________ □ origin, □ destination, □ transit or □ where the spent fuel enters the CommunityAddress:_______________________________________________________________Post code:__________ City:_____________ Country:______________Tel.:___________________ Fax:________________ E-mail:____________________Contact person: Mr./Ms._______________________________________________________________

(22) Enumeration in case of approval and/or refusal from the country affected by the transport:

Member State or country

Approved ? List of conditions for acceptance or reasons for refusal, as the case may be:


1. YES/NO*

2. YES/NO*

3. YES/NO*

4. YES/NO*

5. YES/NO*

6. YES/NO*

7. YES/NO*

8. YES/NO*

(23) The decision stated in this part was made in accordance with the stipulations of directive 2006/117/Euratom.31 The competent authorities of the affected countries have been informed that theone-time transport*repeated transport*of spent fuel described in part B1 was

APPROVED Expiry day of permit: ____________________________________________(dd/mm/yyyy)


(*) Use only one statement marked with a star; cross out those that are not applicable.

31 This permit does not in any way reduce the responsibility of the holder, shipper, owner, receiver or any other physical or legal entity affected by the transport.


PART B-4BREFUSAL TO transport spent fuel

(24) Name of competent authority responsible for the refusal to transport:_____________________________________________________________________________________________________________Member State (check the applicable box and fill in): ___________________________ □ origin, □ destination, □ transit or □ where the spent fuel enters the CommunityAddress:_______________________________________________________________Post code:_______________ City:_________________ Country:__________________Tel.:___________________ Fax:________________ E-mail:____________________Contact person: Mr./Ms.______________________________________________________________

(25) Enumeration in case of approval and/or refusal from the country affected by the transport:

Member State / country

Approved ?

List of conditions for acceptance or reasons for refusal, as the case may be:


1. YES/NO*

2. YES/NO*

3. YES/NO*

4. YES/NO*

5. YES/NO*

6. YES/NO*

7. YES/NO*

8. YES/NO*

The decision stated in this part was made in accordance with the stipulations of directive 2006/117/Euratom.32 The competent authorities of the affected countries have been informed that theone-time transport*repeated transport*of spent fuel described in part B1 was

REFUSED


(*)Use only one statement marked with a star; cross out those that are not applicable.

32 This permit does not in any way reduce the responsibility of the holder, shipper, owner, receiver or any other physical or legal entity affected by the transport.


PART B-5DESCRIPTION OF SPENT FUEL CONSIGNMENT AND LIST OF PACKAGING

(26) Applicant (commercial name):_____________________________________________________________□ holder,____ □ recipient,____□ other, provide details:_____________________________________Address:____________________________________________________________________________Post code:__________ City: _______________Country:____________________________Tel.:______________________Fax:________________E-mail:__________________________________Contact person: Mr./Ms.:________________________________________________________________

(27) Expiry date of permit __________________________________(dd/mm/yyyy), for □ one-time transport, □ repeated transport, serial number of consignment:

(28) Type of spent fuel: □ metal uranium, □ uranium oxide, □ mixed fuel (MOX), □ other, provide details: ______________________________________________________________________________

Original fissile substance: □ uranium 235___________ [maximum enrichment…….……………. %] □ MOX__________ [nominal enrichment with uranium…………. %] _________ [max. PU content …….….%]□ other, provide details _____________________________________________________________

Spent fuel (average or normal range):________________________________MWdny/teHMTotal amount of sets/packets/components/specimens (provide details):______________________________Maximum volume of spent fuel for one packaging (kg):_______________________________________

(29) *ID No.: *Type33 *gross weight (kg)

*net weight(kg)

*activity (GBq)

Total amount: Total / type: Total: Total: Total:(*) Fill in for every packaging; if there is not enough space attach a separate list!

(30) Consignment dispatch date: ____________________________________________ (dd/mm/yyyy) I confirm that the information provided in this part (and in the attached lists or documents) is according to my best knowledge and conscience true.

__________________________________________________________________________________…… (date and place)…………….……………….. (stamp)………………………..(signature)………………..

33 According to the Rules for safe transport of radioactive material TS-R-1, IAEA, Vienna, 2005.


PART B-6CONFIRMATION OF RECEIPT OF SPENT FUEL

(31) Recipient (commercial name): _____________________________________________________________ Address:_____________________________________________________________________________Post code:________ City:___________________ Country :________________________Tel.:_________________ Fax:_____________________ E-mail:_______________________________Contact person:

(32) Storage of spent fuel after transport (commercial name): __________________________ Address:_____________________________________________________________________________Post code:________ City:___________________ Country :________________________Tel.:_________________ Fax:_____________________ E-mail:_______________________________Contact person: Mr./Ms._______________________________________________________________

(33) Permit granted (check the applicable box):□ for one-time MM or IM transport, □ for one-time ME or TT transport □ for repeated MM or IM transport, serial number of consignment: _________________________________________________________________Last transport to which the permit applies: □Yes □No□ for repeated ME or TT transport, serial number of consignment: _________________________________________________________________ Last transport to which the permit applies: □ Yes □No

(34) □ not used.□ for ME or TT transport: (this item can be replaced with a separate declaration; provide references to supplements): _______________________________________________________________Entry border crossing of destination or transit third country:___________________________Third country:___________________________ Border crossing:_______________________________

(35) According to the type of transport the recipient can send confirmation of receipt together with part B-5: (MM or IM): to the competent authority of the destination Member State; (ME or TT): to the applicants (ME: holders, TT: persons responsible for transport in the Member

State where spent fuel enters the Community), according to items 4 (part B-1).Receipt date of spent fuel:___________________________________________(dd/mm/yyyy)Dispatch date of confirmation of receipt:_______________________________________(dd/mm/yyyy)I as the recipient confirm that the information in this part (and attached lists) is according to my best knowledge and conscience true.


(36) □ Not used.□ ME or TT transport: the applicant sends confirmation of receipt and if necessary statement of receipt to the authority that issued the permit.1. Recipients with registered seat outside of the European Union can confirm receipt of spent fuel by means of a statement or testimonial that includes at least the information shown in items 32 to 37. 2. The competent authority who holds the original confirmation of receipt must send a copy of it to other competent authorities. 3. The originals of B-5 and B-6 must be finally sent to the competent authority that issued the permit. 4. For transport between Member States the competent authority of the Member State or state of origin where the consignment first entered the Community must send a copy of the confirmation of receipt to the holder.

Dispatch date of confirmation of receipt (with part B-5): ____________(dd/mm/yyyy)

Border crossing exit from Community:__________________________________

Country: Border crossing:

__________________________________________________________________________________(date and place).......................(stamp)……………….(signature of applicant)

EXPLANATORY NOTESto each item of the standard document parts A-1 to A-6 and B-1 to B-6:

Definition of duly filled in application: Application for transport permit for radioactive waste or spent fuel is duly filled in in accordance with directive 2006/117/Euratom, if for transport of radioactive waste in every item of part A-1 or for transport of spent fuel in each item of part B-1 the requested information was provided by checking the corresponding box, crossing out the options that are not applicable or filling in the relevant information and figures. For applications involving repeated transport, items 8 and 9 can contain estimates.

(1) The applicant must duly fill in all items 1 to 14. In item 1 check off one of the boxes specifying the type of transport and fill in the corresponding border crossings if the transport involves third countries,

Check off MM for transport between Member States, where the consignment can possibly pass through other Member States or third countries;

Check off IM for transport from a third country to a Member State (= import to Community), in which case the application must contain a document showing that the recipient entered into an agreement with the holder settled in a third country, which accepted the competent authority of the given third country and which obliges the holder to reassume the radioactive waste or spent fuel if it is not possible or not permitted to complete the transport;

Check off ME for transport from the Member State to a third country (= export from Community) or

Check off TT for transport from one third country to another third country, when the consignment passes through one or more Member States, in which case the application must contain a document showing that the recipient settled in the third country entered into an agreement with the holder settled in the third country, which was accepted by the competent authority of the given third country and in which the holder is obliged to reassume the radioactive waste or spent fuel if it is not possible or not permitted to complete the transport.

(2) By checking off the corresponding box, the applicant must clearly indicate whether the application involves only a one-time transport in a particular period (e.g. 05/2010, 2009 or 2010–2011), or whether the application involves repeated transport in a particular period, which nevertheless does not exceed three years from the date of issuing the permit. For repeated transport, a single application can be sent if the conditions stipulated in art. 6 para. 2 of directive 2006/117/Euratom are met:

radioactive waste or spent fuel, which the application refers to, have the same basic physical, chemical and radioactive characteristics; and

the consignment is sent by the same holder to the same receiver with the participation of the same competent authorities; and

in cases where the transport involves transit through a third country, this transit takes place through the same border crossing when entering the Community or exiting the Community, and through the same border crossing or crossing of an affected third country or countries, unless the affected competent authority agrees otherwise.

(3) If the transport involves one or more third countries, the applicant must fill in the relevant border crossings. These border crossings must be the same for all transports involved in the application, unless the competent authority agrees otherwise.

(4) The applicant must fill in his commercial name, address and contact information. The commercial name, marked also as the commercial name or trade name, is the name which the company uses in its business relations, though its registered legal name used for contracts and other official situations can be different. The applicant must check off the corresponding box marking his function, which depends on the type of transport:

holder for transport between Member States (MM) or export from the Community to a third country (ME);

recipient for import to the Community from a third country (IM);

person responsible for the transport in the Member State from which the radioactive waste or spent fuel enters the Community in case of transit to the Community (TT).

(5) The applicant must fill in the commercial name, address and contact information of the place where the radioactive waste or spent fuel is stored before transport and which can be different from the address of the applicant.

(6) The applicant must fill in the commercial name, address and contact information of the recipient. For IM transports, this information is the same as the information in item 4.

(7) The applicant must fill in the commercial name, address and contact information of the place where the radioactive waste or spent fuel is stored after transport and which can be different from the address of the recipient.

(8) The applicant must fill in all fields by checking off the corresponding box (more than one answer is possible) or by filling in the particular characteristics and values of the radioactive waste or spent fuel. For repeated transports, the values provided can be estimates.

(9) The applicant must fill in item 9; the values provided can be estimates.

(10) The applicant must check off and specify the type of activity that created the radioactive waste or spent fuel and check off the corresponding box or specify another activity. More than one answer is possible.

(11) The applicant must provide the purpose of the transport and check off the corresponding box (only one answer is possible) or specify another purpose.

(12) The applicant must provide an inventory of individual planned types of shipping methods for the transport (road, rail, sea, air, domestic water) and fill in the relevant place of dispatch, place of receipt and the planned shipper (if known). Later changes to this plan during the course of processing the application are possible and must be reported to the competent authority; however, this does not require a new permit application.

(13) The applicant must include all countries which the transport will involve, starting with the first Member State or third country where the radioactive waste or spent fuel originates, and ending with the last Member State or third country where the waste or fuel will end up after the conclusion of transport. If the applicant wants to change the enumeration of countries, he must make a new application.

(14) The applicant must state who will reassume the radioactive waste or spent fuel if it will not be possible to realize the transport or meet the conditions of transport. For IM or TT transport, the applicant must supplement the application with a document about the agreement between the recipient in the destination Member State or third country and the holder of the radioactive waste or spent fuel in the third country which is accepted by the competent authority of the given third country.

After filling in items 1 to 14, the applicant must send part 1 of the standard document to the competent authority responsible for issuing the transport permit.

The competent authority responsible for issuing the transport permit or for refusing the application depends on the type of transport:

the competent authority of the Member State of origin for transport between Member States (MM) and export from the Community (ME);

the competent authority of the destination Member State in case of import to the Community (IM);

the competent authority of the first transit Member State, where the consignment enters the Community, in case of transit through the territory of the Community (TT).

Relevant contact information can be acquired from the electronic communications platform established and administered by the Commission or from the published list of competent authorities.

(15) Immediately after the receipt of the application, the competent authority responsible for issuing the transport permit must:

enter the registration No. of the application in the upper part of each part of the standard document, starting with part 1,

certify whether the applicant duly filled in all items of part 1, fill in item 15 of part 2 and provide a sufficient number of copies of 1, 2 and 3 for each affected

Member State or country. Consultation with third transit countries takes place only for information purposes.

(16) The competent authority responsible for issuing permits must:

fill in item 16 of part 2 (and item 18 of part 3) for each competent authority of affected Member States or countries included in the list in item 13, whose acceptance is required for the transport permit; and

immediately send a duly filled in application (part 1) together with part 2 for approval to each affected competent authority included in item 16.

(17) Item 17 is filled in by the competent authority of the affected Member State (competent authorities of affected Member States). The date of delivery and receipt of the application must be recorded immediately after receipt of the application. Within 20 days from the date of receipt the competent authority of the affected Member States must certify whether the application is duly filled in (all items 1 to 14 must be filled in and no information can be missing; some values can be estimates). Only item 17(a) or item 17(b) can apply; cross out those items that are not applicable.

If the competent authority of the Member State (competent authorities of Member States), as the case may be, for transit or destination consider the application incomplete, item 17(a) must be filled in, item 17(b) crossed out and specify its application for missing information to the competent authority responsible for issuing permits (shown in item 15). It must clearly state which information is missing (fill in or attach a document). The competent authority requesting the missing information must ensure copies of part 2 for all other competent authorities of affected Member States included in item 13 within 20 days from the date the application is received. Relevant contact information can be acquired from the electronic communications platform established and administered by the Commission or from the published list of competent authorities. If one Member State doubts whether the application was duly filled in, the process will stop. In this case the competent authority of the destination Member State cannot send confirmation of receipt before the requested information has been provided and within 10 days from the receipt of missing information is not sent any other application, and this even if the application is considered duly filled in. This procedure can be repeated until all missing information is acquired and further requests for missing information are no longer sent.

If in the 20-day period from the receipt of the application no request for missing information was received and if the competent authority of the affected Member State doubts whether the application is duly filled in, the competent authority must not later than within 10 days from the expiry of the 20-day period send part 2 to the competent authority responsible for issuing permits included in item 15 and copies of the included parts to all other competent authorities of affected Member States included in item 13. Relevant contact information can be acquired from the electronic communications platform established and administered by the Commission or from the published list of competent authorities.

All competent authorities of affected Member States can agree on a shorter deadline.

So that the competent authorities can request missing information in a period of 20 days from the receipt of the application, the competent authority of the destination Member State cannot issue its confirmation of receipt before the expiry of the 20-day period. If the competent authority of the destination Member State announces that the application was duly filled in after the expiry of the 20-day period and if there are no other affected Member States or another affected competent authority has not put in a request for missing information, the competent authority must fill in item 17(b).

(18) As soon as the competent authority responsible for issuing permits obtains confirmation of receipt of a duly filled in application from the competent authority of the destination Member State, it must confirm whether the deadlines were adhered to and must fill in item 18 part 3 for each affected Member State included in item 13, whose acceptance is required for the transport permit.The affected competent authority must fill in other required information in item 18.

(19) The competent authority responsible for issuing permits must carry out the recording in the general period for automatically conferring acceptance valid for all affected Member States. This expiry date of validity usually falls on the day two months after the date when the destination Member State issued

confirmation of receipt according to items 17(b). The competent authority responsible for the permit must then send part 3 containing the approval or refusal to all affected Member States or countries.

Immediately after receiving part 3 each affected competent authority must decide whether a further deadline for the decision on refusal or approval of transport is necessary. By crossing out the general deadline in item 19 and filling in a new deadline, a period not longer than one month can be requested in such a way that the extension of the deadline is announced to all affected competent authorities.

(20) The affected competent authority must duly consider the application. Not later than the expiry of the deadline for automatically conferring acceptance, the affected competent authority must fill in item 20 and return the original part 3 (scanned original, if sent by e-mail) to the competent authority responsible for conferring permits (shown in item 15). In case of refusal of the application it is necessary to provide reasons and support them (in transit Member States) by relevant legal regulations of the Community or international legal regulations valid for transporting radioactive material or (in destination Member States) relevant legal regulations valid for disposing of radioactive waste or spent fuel or relevant domestic legal regulations, legal regulations of the Community or international legal regulations valid for transporting radioactive material. No imposed conditions can be stricter than the conditions which are stipulated for similar transport in Member States. Uncompleted and unreturned standard documents in the required deadline are considered accepted with application for transport with the exception of art. 9 para. 2 of directive 2006/117/Euratom.

(21) The competent authority responsible for issuing transport permits must fill in items 21 to 23 as soon as all affected competent authorities issue acceptance required for transport, while for that which default acceptance was given is possible only in these cases:

if confirmation of receipt was given (at least) from the competent authority of the destination Member State (shown in item 17(b);

no request for missing information is pending; and

the affected competent authorities in the valid deadlines shown in item 19 did not give an answer (neither acceptance nor refusal).

(22) The competent authority stated in item 21 must provide or if there is not enough space attach a list on a separate page of all obtained acceptances (including conditions) and refusals (including reasons) from all affected competent authorities.

(23) The competent authority stated in item 21 must

fill in item 23 so that the validity period of the permit is not more than three years and so that one permit can apply to repeated transport if the conditions stipulated in art. 6 para. 2 of directive Rules are met;

send the original of part 4a to the applicant together with part 1, 4a, 5 and 6 a;

send a copy of part 4a to all other affected competent authorities.

(24) The competent authority responsible for issuing the transport permit must fill in items 24 and 25, as long as at least one of the affected competent authorities did not accept the transport.

(25) The competent authority stated in item 24 must provide on a separate page a list of all obtained acceptances and refusals from all affected competent authorities and send the original of part 4b to the applicant and the copy stated in part to all other affected competent authorities.

(26) If the transport is permitted and the applicant obtains parts 4a, 5 and 6, he must duly fill in item 26. If the application is for repeated transport, the applicant must arrange a sufficient number of copies of part 5 for each consignment.

(27) The applicant must check off the corresponding box and state whether the permit is for one-time or repeated transport. For repeated transport the corresponding serial number must be filled in.

(28) Before each transport the applicant must duly fill in items 28 to 30 (even if the permit is for repeated transport). The values in this part must not be estimates!

(29) The applicant must duly fill in item 29 (list of packaging) and in the lower part state the total amount of packaging, the total amount of each type of packaging, the total net weight, the total gross weight and the total activity (GBq) of all packaging. If there is not enough space on the document, attach a separate page with the required information.

(30) The applicant must fill in item 30 (date of dispatch and declaration) before each transport of radioactive waste or spent fuel (even if the permit is for repeated transport). Part 5 is attached together with parts 1 and 4a during transport to the consignment of radioactive waste or spent fuel. A description of the consignment and a list of packaging (part 5) is then attached to part 6 (confirmation of receipt).

(31) The recipient (for MM and IM transports), holder (for ME transport) or the person responsible for the transport (for TT transport) must duly fill in items 31 to 35 (or 36 in necessary); all required filling in is done by the applicant. Recipients located outside the European Union can confirm receipt of radioactive waste or spent fuel by means of a declaration which is not a part of the standard document.

(32) The recipient must duly fill in the name, address and contact information of the place where the radioactive waste or spent fuel is stored for transport.

(33) The recipient must fill in item 33 (according to item 23) and state whether the received consignment is the last which the given permit is for.

When the permit is for one-time MM or IM transport, the recipient must fill in part 6 within 15 days of the receipt of the radioactive waste or spent fuel and submit parts 5 and 6 to the competent authority of the destination Member State. The competent authority of the destination Member State then sends copies of parts 5 and 6 to the other affected competent authorities (and the original, if necessary, of both parts to the competent authority that issued the permit). For MM transports, the competent authority of the Member State of origin must send a copy of the confirmation of receipt to the holder.

When the permit is for one-time ME or TT transport, the applicant must ensure that recipients located outside the European Union send him duly filled in part 5 and part 6 immediately after the receipt of radioactive waste or spent fuel. Part 6 can be replaced by a declaration from the recipient that contains at least the information stated in items 31 to 36. Within 15 days of the receipt of the radioactive waste or spent fuel the applicant must send part 5, part 6 (if the recipient did not use part 6, the applicant must fill it in) and if necessary a declaration from the recipient to the competent authority which issued the permit. This authority then sends copies of parts 5 and 6 and if necessary a declaration from the recipient to the other affected competent authorities.

When the permit is for repeated MM or IM transport, the recipient must fill in part 6 after the transport of each consignment (and for this purpose earlier provide copies of the non filled in part 6) and submit this part directly to the competent authority that issued the permit. Submit part 5 referring to the same cargo.

When the permit is for repeated ME or TT transport, the applicant must ensure that after each consignment to recipients located outside the European Union he has filled in for each consignment (non filled in) copies of part 6 and returned it together with the corresponding part 5.

(34) For ME or TT transports the recipient must mark “not used” or fill in item 34 or submit a separate declaration and provide a reference to the attachment.

(35) As soon as the one-time transport or the transport of all cargo which the permit is for has been completed, the recipient must fill in item 35. If the permit is for repeated transport, the final confirmation of receipt is filled in and submitted in the same way as permits valid for one-time transport, with these exceptions:

In item 30 parts 6 state that the transport of the consignment is the last that the permit applies to.

In every declaration, recipients located outside the European Union must be notified that all radioactive waste or spent fuel which the permit applies to was indeed taken over.

According to the type of transport, the recipient must send part 6 (confirmation of receipt) together with part 5 to the competent authority of the destination Member State for MM or IM transport, or the applicant stated in item 5 (part 1) for ME or TT transport. For a total overview to be available, part 6 for each consignment which the permit applies to must be submitted for final confirmation of receipt.

(36) For ME or TT transport the recipient must mark “not used” or fill in item 36 or replace it with a separate declaration and provide a reference to an attachment. The applicant must send parts 5 and 6 to the authority that issued the permit. For a total overview to be available, part 6 for each consignment to which the permit applies must be submitted for final confirmation of receipt.

Documents

€¦ · Web viewCriticality Safety Index (CSI) number, which proves the maintenance of a criticality state of the radioactive cargo, external package or shipping container