10. Article

The specimen shall be rigidly clamped in a horizontal position so that one half of its length protrudes from the face of the clamp. The orientation of the specimen shall be such that the specimen will suffer maximum damage when its free end is struck by the flat face of a steel bar. The bar shall strike the specimen so as to cause an impact equivalent to that resulting from a free vertical drop of 1.4 kg through 1 m. The lower part of the bar shall be 25 mm in diameter with the edges rounded off to a radius of (3.0 ± 0.3) mm; (d) Heat test: The specimen shall be heated in air to a temperature of 800 °C and held at that temperature for a period of 10 minutes and shall then be allowed to cool. 2.2.7.2.3.3.6 Specimens that comprise or simulate radioactive material enclosed in a sealed capsule may be excepted from: (a) The tests prescribed in 2.2.7.2.3.3.5 (a) and (b) provided the mass of the special form radioactive material: (i) is less than 200 g and they are alternatively subjected to the Class 4 impact test prescribed in ISO 2919:1999 "Radiation protection - Sealed radioactive sources - General requirements and classification"; or (ii) is less than 500 g and they are alternatively subjected to the Class 5 impact test prescribed in ISO 2919:1999 "Radiation protection - Sealed radioactive sources - General requirements and classification"; and (b) The test prescribed in 2.2.7.2.3.3.5 (d) provided they are alternatively subjected to the Class 6 temperature test specified in ISO 2919:1999 "Radiation protection - Sealed radioactive sources - General requirements and classification". 2.2.7.2.3.3.7 For specimens which comprise or simulate indispersible solid material, a leaching assessment shall be performed as follows: (a) The specimen shall be immersed for 7 days in water at ambient temperature. The volume of water to be used in the test shall be sufficient to ensure that at the end of the 7 day test period the free volume of the unabsorbed and unreacted water remaining shall be at least 10% of the volume of the solid test sample itself. The water shall have an initial pH of 6-8 and a maximum conductivity of 1 mS/m at 20 °C; (b) The water with specimen shall then be heated to a temperature of (50 ± 5) °C and maintained at this temperature for 4 hours; (c) The activity of the water shall then be determined; (d) The specimen shall then be kept for at least 7 days in still air at not less than 30 °C and relative humidity not less than 90%; (e) The specimen shall then be immersed in water of the same specification as in (a) above and the water with the specimen heated to (50 ± 5) °C and maintained at this temperature for 4 hours; (f) The activity of the water shall then be determined. 2.2.7.2.3.3.8 For specimens which comprise or simulate radioactive material enclosed in a sealed capsule, either a leaching assessment or a volumetric leakage assessment shall be performed as follows: (a) The leaching assessment shall consist of the following steps: (i) the specimen shall be immersed in water at ambient temperature. The water shall have an initial pH of 6-8 with a maximum conductivity of 1 mS/m at 20 °C; (ii) the water and specimen shall be heated to a temperature of (50 ± 5) °C and maintained at this temperature for 4 hours; (iii) the activity of the water shall then be determined; (iv) the specimen shall then be kept for at least 7 days in still air at not less than 30 °C and relative humidity of not less than 90%; (v) the process in (i), (ii) and (iii) shall be repeated; (b) The alternative volumetric leakage assessment shall comprise any of the tests prescribed in ISO 9978:1992 "Radiation Protection - Sealed radioactive sources - Leakage test methods", which are acceptable to the competent authority. 2.2.7.2.3.4 Low dispersible radioactive material 2.2.7.2.3.4.1 The design for low dispersible radioactive material shall require multilateral approval. Low dispersible radioactive material shall be such that the total amount of this radioactive material in a package shall meet the following requirements: (a) The radiation level at 3 m from the unshielded radioactive material does not exceed 10 mSv/h; (b) If subjected to the tests specified in 6.4.20.3 and 6.4.20.4, the airborne release in gaseous and particulate forms of up to 100 μm aerodynamic equivalent diameter would not exceed 100 A2. A separate specimen may be used for each test; and (c) If subjected to the test specified in 2.2.7.2.3.1.4 the activity in the water would not exceed 100 A2. In the application of this test, the damaging effects of the tests specified in (b) above shall be taken into account. 2.2.7.2.3.4.2 Low dispersible radioactive material shall be tested as follows: A specimen that comprises or simulates low dispersible radioactive material shall be subjected to the enhanced thermal test specified in 6.4.20.3 and the impact test specified in 6.4.20.4. A different specimen may be used for each of the tests. Following each test, the specimen shall be subjected to the leach test specified in 2.2.7.2.3.1.4. After each test it shall be determined if the applicable requirements of 2.2.7.2.3.4.1 have been met. 2.2.7.2.3.4.3 Demonstration of compliance with the performance standards in 2.2.7.2.3.4.1 and 2.2.7.2.3.4.2 shall be in accordance with 6.4.12.1 and 6.4.12.2. 2.2.7.2.3.5 Fissile material Packages containing fissile radionuclides shall be classified under the relevant entry of Table 2.2.7.2.1.1 for fissile material unless one of the conditions (a) to (d) of this paragraph is met. Only one type of exception is allowed per consignment. (a) A mass limit per consignment such that: mass of uranium - 235 (g) + mass of other fissile material (g) < 1 X Y where X and Y are the mass limits defined in Table 2.2.7.2.3.5, provided that the smallest external dimension of each package is not less than 10 cm and that either: (i) each individual package contains not more than 15 g of fissile material; for unpackaged material, this quantity limitation shall apply to the consignment being carried in or on the wagon; or (ii) the fissile material is a homogeneous hydrogenous solution or mixture where the ratio of fissile nuclides to hydrogen is less than 5% by mass; or (iii) there are not more than 5 g of fissile material in any 10 litre volume of material. Neither beryllium nor deuterium shall be present in quantities exceeding 1% of the applicable consignment mass limits provided in Table 2.2.7.2.3.5, except for deuterium in natural concentration in hydrogen. (b) Uranium enriched in uranium-235 to a maximum of 1% by mass, and with a total plutonium and uranium-233 content not exceeding 1% of the mass of uranium-235, provided that the fissile material is distributed essentially homogeneously throughout the material. In addition, if uranium-235 is present in metallic, oxide or carbide forms, it shall not form a lattice arrangement; (c) Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of 2% by mass, with a total plutonium and uranium-233 content not exceeding 0.002% of the mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) of 2; (d) Packages containing, individually, a total plutonium mass not more than 1 kg, of which not more than 20% by mass may consist of plutonium-239, plutonium-241 or any combination of those radionuclides. Table 2.2.7.2.3.5: Consignment mass limits for exceptions from the requirements for packages containing fissile material Fissile material Fissile material mass (g) mixed with substances having an average hydrogen density less than or equal to water Fissile material mass (g) mixed with substances having an average hydrogen density greater than water Uranium-235 (X) 400 290 Other fissile material (Y) 250 180 2.2.7.2.4 Classification of packages or unpacked material The quantity of radioactive material in a package shall not exceed the relevant limits for the package type as specified below. 2.2.7.2.4.1 Classification as excepted package 2.2.7.2.4.1.1 Packages may be classified as excepted packages if: (a) They are empty packagings having contained radioactive material; (b) They contain instruments or articles in limited quantities; (c) They contain articles manufactured of natural uranium, depleted uranium or natural thorium; or (d) They contain radioactive material in limited quantities. 2.2.7.2.4.1.2 A package containing radioactive material may be classified as an excepted package, provided that the radiation level at any point on its external surface does not exceed 5 μSv/h. Table 2.2.7.2.4.1.2: Activity limits for excepted packages Physical state of contents Instruments or articles Materials Item limits(a) Package limits(a) Package limits(a) (1) (2) (3) (4) Solids special form 10-2 A1 A1 10-3 A1 other form 10-2 A2 A2 10-3 A2 Liquids 10-3 A2 10-1 A2 10-4 A2 Gases tritium 2 x 10-2 A2 2 x 10-1 A2 2 x 10-2 A2 special form 10-3 A1 10-2 A1 10-3 A1 other form 10-3 A2 10-2 A2 10-3 A2 (a) For mixtures of radionuclides, see 2.2.7.2.2.4 to 2.2.7.2.2.6. 2.2.7.2.4.1.3 Radioactive material which is enclosed in or is included as a component part of an instrument or other manufactured article may be classified under UN No. 2911 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - INSTRUMENTS or ARTICLES, provided that: (a) The radiation level at 10 cm from any point on the external surface of any unpackaged instrument or article is not greater than 0.1 mSv/h; and (b) Each instrument or manufactured article bears the marking "RADIOACTIVE" except: (i) radioluminescent time-pieces or devices; (ii) consumer products that either have received regulatory approval according to 1.7.1.4 (d) or do not individually exceed the activity limit for an exempt consignment in Table 2.2.7.2.2.1 (column 5), provided such products are carried in a package that bears the marking "RADIOACTIVE" on an internal surface in such a manner that warning of the presence of radioactive material is visible on opening the package; and (c) The active material is completely enclosed by non-active components (a device performing the sole function of containing radioactive material shall not be considered to be an instrument or manufactured article); and (d) The limits specified in columns 2 and 3 of Table 2.2.7.2.4.1.2 are met for each individual item and each package, respectively. 2.2.7.2.4.1.4 Radioactive material with an activity not exceeding the limit specified in column 4 of Table 2.2.7.2.4.1.2, may be classified under UN No. 2910 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - LIMITED QUANTITY OF MATERIAL, provided that: (a) The package retains its radioactive contents under routine conditions of carriage; and (b) The package bears the marking "RADIOACTIVE" on an internal surface in such a manner that a warning of the presence of radioactive material is visible on opening the package. 2.2.7.2.4.1.5 An empty packaging which had previously contained radioactive material with an activity not exceeding the limit specified in column 4 of Table 2.2.7.2.4.1.2 may be classified under UN No. 2908 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGING, provided that: (a) It is in a well-maintained condition and securely closed; (b) The outer surface of any uranium or thorium in its structure is covered with an inactive sheath made of metal or some other substantial material; (c) The level of internal non-fixed contamination, when averaged over any 300 cm2, does not exceed: (i) 400 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters; and (ii) 40 Bq/cm2 for all other alpha emitters; and (d) Any labels which may have been displayed on it in conformity with 5.2.2.1.11.1 are no longer visible. 2.2.7.2.4.1.6 Articles manufactured of natural uranium, depleted uranium or natural thorium and articles in which the sole radioactive material is unirradiated natural uranium, unirradiated depleted uranium or unirradiated natural thorium may be classified under UN No. 2909 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - ARTICLES MANUFACTURED FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUM, provided that the outer surface of the uranium or thorium is enclosed in an inactive sheath made of metal or some other substantial material. 2.2.7.2.4.2 Classification as Low specific activity (LSA) material Radioactive material may only be classified as LSA material if the conditions of 2.2.7.2.3.1 and 4.1.9.2 are met. 2.2.7.2.4.3 Classification as Surface contaminated object (SCO) Radioactive material may be classified as SCO if the conditions of 2.2.7.2.3.2 and 4.1.9.2 are met. 2.2.7.2.4.4 Classification as Type A package Packages containing radioactive material may be classified as Type A packages, provided that the following conditions are met: Type A packages shall not contain activities greater than the following: (a) For special form radioactive material: A1; or (b) For all other radioactive material: A2. For mixtures of radionuclides whose identities and respective activities are known, the following condition shall apply to the radioactive contents of a Type A package: ∑i B(i) + ∑j C(j) ≤1 A1(i) A2(j) where B(i) is the activity of radionuclide i as special form radioactive material; A1(i) is the A1 value for radionuclide i; C(j) is the activity of radionuclide j as other than special form radioactive material; and A2(j) is the A2 value for radionuclide j. 2.2.7.2.4.5 Classification of Uranium hexafluoride Uranium hexafluoride shall only be assigned to UN Nos. 2977 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, FISSILE, or 2978 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, non-fissile or fissile-excepted. 2.2.7.2.4.5.1 Packages containing uranium hexafluoride shall not contain: (a) A mass of uranium hexafluoride different from that authorized for the package design; (b) A mass of uranium hexafluoride greater than a value that would lead to an ullage smaller than 5% at the maximum temperature of the package as specified for the plant systems where the package shall be used; or (c) Uranium hexafluoride other than in solid form or at an internal pressure above atmospheric pressure when presented for carriage. 2.2.7.2.4.6 Classification as Type B(U), Type B(M) or Type C packages 2.2.7.2.4.6.1 Packages not otherwise classified in 2.2.7.2.4 (2.2.7.2.4.1 to 2.2.7.2.4.5) shall be classified in accordance with the competent authority approval certificate for the package issued by the country of origin of design. 2.2.7.2.4.6.2 A package may only be classified as a Type B(U) if it does not contain: (a) Activities greater than those authorized for the package design; (b) Radionuclides different from those authorized for the package design; or (c) Contents in a form, or a physical or chemical state different from those authorized for the package design; as specified in the certificate of approval. 2.2.7.2.4.6.3 A package may only be classified as a Type B(M) if it does not contain: (a) Activities greater than those authorized for the package design; (b) Radionuclides different from those authorized for the package design; or (c) Contents in a form, or a physical or chemical state different from those authorized for the package design; as specified in the certificate of approval. 2.2.7.2.4.6.4 A package may only be classified as a Type C if it does not contain: (a) Activities greater than those authorized for the package design; (b) Radionuclides different from those authorized for the package design; or (c) Contents in a form, or physical or chemical state different from those authorized for the package design; as specified in the certificate of approval. 2.2.7.2.5 Special arrangements Radioactive material shall be classified as transported under special arrangement when it is intended to be carried in accordance with 1.7.4." Section 2.2.8 Footnotes 8 to 10 become 7 to 9. 2.2.8.1.6 (c) In the first sentence of the second indent, replace "corrosion rate on steel" with: "corrosion rate on either steel". At the end of the first sentence of the second indent, insert: "when tested on both materials". Add a new note at the end to read as follows: "NOTE: Where an initial test on either steel or aluminium indicates the substance being tested is corrosive the follow up test on the other metal is not required." Section 2.2.9 2.2.9.1.7 Insert the following new first sentence: "The term "lithium battery" covers all cells and batteries containing lithium in any form." At the beginning of the second sentence (current first sentence), replace "Lithium cells and batteries" with: "They". 2.2.9.1.9 Amend to read as follows: "2.2.9.1.9 (Deleted)". Delete the preceding title ("Environmentally hazardous substances"). 2.2.9.1.10 Amend to read as follows: "2.2.9.1.10 Environmentally hazardous substances (aquatic environment) 2.2.9.1.10.1 General definitions 2.2.9.1.10.1.1 Environmentally hazardous substances include, inter alia, liquid or solid substances pollutant to the aquatic environment and solutions and mixtures of such substances (such as preparations and wastes). For the purposes of 2.2.9.1.10, "substance" means chemical elements and their compounds in the natural state or obtained by any production process, including any additive necessary to preserve the stability of the product and any impurities deriving from the process used, but excluding any solvent which may be separated without affecting the stability of the substance or changing its composition. 2.2.9.1.10.1.2 The aquatic environment may be considered in terms of the aquatic organisms that live in the water, and the aquatic ecosystem of which they are part10. The basis, therefore, of the identification of hazard is the aquatic toxicity of the substance or mixture, although this may be modified by further information on the de gradation and bioaccumulation behaviour. 10 This does not address aquatic pollutants for which there may be a need to consider effects beyond the aquatic environment such as the impacts on human health etc. 2.2.9.1.10.1.3 While the following classification procedure is intended to apply to all substances and mixtures, it is recognised that in some cases, e.g. metals or poorly soluble inorganic compounds, special guidance will be necessary11. 11 This can be found in Annex 10 of the GHS. 2.2.9.1.10.1.4 The following definitions apply for acronyms or terms used in this section: - BCF: Bioconcentration Factor; - BOD: Biochemical Oxygen Demand; - COD: Chemical Oxygen Demand; - GLP: Good Laboratory Practices; - EC50: the effective concentration of substance that causes 50% of the maximum response; - ErC50: EC50 in terms of reduction of growth; - Kow: octanol/water partition coefficient; - LC50 (50% lethal concentration): the concentration of a substance in water which causes the death of 50% (one half) in a group of test animals; - L(E)C50: LC50 or EC50; - NOEC: No Observed Effect Concentration; - OECD Test Guidelines: Test guidelines published by the Organization for Economic Cooperation and Development (OECD). 2.2.9.1.10.2 Definitions and data requirements 2.2.9.1.10.2.1 The basic elements for classification of environmentally hazardous substances (aquatic environment) are: - Acute aquatic toxicity; - Potential for or actual bioaccumulation; - Degradation (biotic or abiotic) for organic chemicals; and - Chronic aquatic toxicity. 2.2.9.1.10.2.2 While data from internationally harmonised test methods are preferred, in practice, data from national methods may also be used where they are considered as equivalent. In general, it has been agreed that freshwater and marine species toxicity data can be considered as equivalent data and are preferably to be derived using OECD Test Guidelines or equivalent according to the principles of Good Laboratory Practices (GLP). Where such data are not available, classification shall be based on the best available data. 2.2.9.1.10.2.3 Acute aquatic toxicity shall normally be determined using a fish 96 hour LC50 (OECD Test Guideline 203 or equivalent), a crustacea species 48 hour EC50 (OECD Test Guideline 202 or equivalent) and/or an algal species 72 or 96 hour EC50 (OECD Test Guideline 201 or equivalent). These species are considered as surrogate for all aquatic organisms and data on other species such as Lemna may also be considered if the test methodology is suitable. 2.2.9.1.10.2.4 Bioaccumulation means net result of uptake, transformation and elimination of a substance in an organism due to all routes of exposure (i.e. air, water, sediment/soil and food). The potential for bioaccumulation shall normally be determined by using the octanol/water partition coefficient, usually reported as a log Kow determined according to OECD Test Guideline 107 or