- Latest available (Revised)
- Original (As made)
This is the original version (as it was originally made).
Regulation 2(1)
1. An effective dose of 5 mSv in the period of one year immediately following the radiation emergency.
2. Without prejudice to paragraph 1—
(a)an equivalent dose for the lens of the eye of 15 mSv in the period of one year immediately following the radiation emergency; and
(b)an equivalent dose for the skin of 50 mSv in the period of one year immediately following the radiation emergency over 1cm2 area of skin, regardless of the area exposed.
3. In this Schedule—
(a)any reference to an effective dose means the sum of the effective dose to the whole body from external radiation and the committed effective dose from internal radiation;
(b)any reference to equivalent dose to a human tissue or organ includes the committed equivalent dose to that tissue or organ from internal radiation;
(c)“external radiation” means, in relation to a person, ionising radiation coming from outside the body of that person; and
(d)“internal radiation” means, in relation to a person, ionising radiation coming from inside the body of that person.
Regulation 3(1) and (2)
Radionuclide name, symbol | Radionuclide form | Quantity (Bq) |
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Note: In the case of radionuclides not specified elsewhere in this Part, the quantity specified in this entry is to be used unless the Executive has approved some other quantity for that radionuclide. | ||
Actinium | ||
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Aluminium | ||
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Americium | ||
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Antimony | ||
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Argon | ||
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Arsenic | ||
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Astatine | ||
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Barium | ||
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Berkelium | ||
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Beryllium | ||
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Bismuth | ||
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Bromine | ||
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Cadmium | ||
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Caesium | ||
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Calcium | ||
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Californium | ||
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Carbon | ||
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Cerium | ||
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Chlorine | ||
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Chromium | ||
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Cobalt | ||
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Copper | ||
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Curium | ||
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Dysprosium | ||
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Einsteinium | ||
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Erbium | ||
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Europium | ||
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Fermium | ||
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Fluorine | ||
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Francium | ||
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Gadolinium | ||
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Gallium | ||
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Germanium | ||
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Gold | ||
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Hafnium | ||
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Holmium | ||
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Hydrogen | ||
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Indium | ||
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Iodine | ||
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Iridium | ||
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Iron | ||
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Krypton | ||
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Lanthanum | ||
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Lead | ||
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Lutetium | ||
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Magnesium | ||
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Manganese | ||
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Mendelevium | ||
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Mercury | ||
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Molybdenum | ||
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Neodymium | ||
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Neon | ||
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Neptunium | ||
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Nickel | ||
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Niobium | ||
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Nitrogen | ||
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Osmium | ||
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Palladium | ||
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Phosphorus | ||
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Platinum | ||
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Plutonium | ||
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Polonium | ||
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Potassium | ||
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Praseodymium | ||
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Promethium | ||
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Protactinium | ||
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Radium | ||
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Rhenium | ||
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Rhodium | ||
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Rubidium | ||
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Ruthenium | ||
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Samarium | ||
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Scandium | ||
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Selenium | ||
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Silicon | ||
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Silver | ||
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Sodium | ||
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Strontium | ||
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Sulphur | ||
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Tantalum | ||
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Technetium | ||
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Tellurium | ||
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Terbium | ||
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Thallium | ||
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Thorium | ||
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Thulium | ||
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Tin | ||
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Titanium | ||
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Tungsten | ||
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Uranium | ||
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Vanadium | ||
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Xenon | ||
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Ytterbium | ||
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Yttrium | ||
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Zinc | ||
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Zirconium | ||
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Other radionuclides not listed above (see note) |
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1. For the purpose of regulation 3(2), the quantity ratio for more than one radionuclide is the sum of the quotients of the quantity of a radionuclide present Qp divided by the quantity of that radionuclide specified in the appropriate column of Part I of this Schedule Qlim, namely—
2. In any case where the isotopic composition of a radioactive substance is not known or is only partially known, the quantity ratio for that substance shall be calculated by using the values specified in the appropriate column in Part 1 for `other radionuclides not listed above' for any radionuclide that has not been identified or where the quantity of a radionuclide is uncertain, unless the employer can show that the use of some other value is appropriate in the circumstances of a particular case, when he may use that value.
Regulation 3(1)
For the purpose of regulation 3(1), the specified mass of a fissile material shall be—
(a) | plutonium as Pu 239 or Pu 241 or as a mixture of plutonium isotopes containing Pu 239 or Pu 241— | 150 grams; |
(b) | uranium as U233— | 150 grams; |
(c) | uranium enriched in U 235 to more than 1% but not more than 5%— | 500 grams;(r) |
(d) | uranium enriched in U 235 to more than 5%— | 250 grams. |
Regulation 3(1) and (3)
Radionuclide name, symbol | Radionuclide form | Quantity (Bq) |
---|---|---|
Note 1: Values include contributions from daughter nuclides with half-lives less than 10 days. | ||
Note 2: These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport. | ||
Note 3: These values apply only to compounds of uranium that take the chemical form of O3, UF4, UCl4 and hexavalent compounds other than those specified in Note 2 above in both normal and accident conditions of transport. | ||
Note 4: These values apply to all compounds of uranium other than those specified in Notes 2 and 3 above. | ||
Note 5: These values apply to unirradiated uranium only. | ||
Note 6: In the case of radionuclides not specified elsewhere in this Part, the quantity specified in this entry is to be used unless the Executive has approved some other quantity for that radionuclide. | ||
Actinium | ||
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Aluminium | ||
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Americium | ||
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Antimony | ||
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Argon | ||
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Arsenic | ||
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Astatine | ||
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Barium | ||
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Berkelium | ||
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Beryllium | ||
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Bismuth | ||
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Bromine | ||
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Cadmium | ||
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Caesium | ||
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Calcium | ||
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Californium | ||
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Carbon | ||
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Cerium | ||
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Chlorine | ||
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Chromium | ||
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Cobalt | ||
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Copper | ||
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Curium | ||
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Dysprosium | ||
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Erbium | ||
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Europium | ||
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Fluorine | ||
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Gadolinium | ||
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Gallium | ||
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Germanium | ||
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Gold | ||
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Hafnium | ||
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Holmium | ||
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Indium | ||
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Iodine | ||
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Iridium | ||
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Iron | ||
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Krypton | ||
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Lanthanum | ||
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Lead | ||
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Lutetium | ||
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Magnesium | ||
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Manganese | ||
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Mercury | ||
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Molybdenum | ||
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Neodymium | ||
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Neptunium | ||
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Nickel | ||
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Niobium | ||
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Nitrogen | ||
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Osmium | ||
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Palladium | ||
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Phosphorus | ||
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Platinum | ||
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Plutonium | ||
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Polonium | ||
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Potassium | ||
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Praseodymium | ||
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Promethium | ||
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Protactinium | ||
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Radium | ||
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Radon | ||
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Rhenium | ||
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Rhodium | ||
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Rubidium | ||
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Ruthenium | ||
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Samarium | ||
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Scandium | ||
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Selenium | ||
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Silicon | ||
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Silver | ||
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Sodium | ||
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Strontium | ||
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Sulphur | ||
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Tantalum | ||
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Technetium | ||
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Tellurium | ||
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Terbium | ||
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Thallium | ||
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Thorium | ||
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Thulium | ||
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Tin | ||
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Titanium | ||
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Tungsten | ||
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Uranium | ||
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Vanadium | ||
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Xenon | ||
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Ytterbium | ||
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Yttrium | ||
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Zinc | ||
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Zirconium | ||
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Other radionuclides not listed above where only beta or gamma emitting nuclides are known to be present |
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Other radionuclides not listed above where alpha emitting nuclides are known to be present or no relevant data are available |
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1. For the purpose of regulation 3(3), the quantity ratio for more than one radionuclide is the sum of the quotients of the quantity of a radionuclide present Qp divided by the quantity of that radionuclide specified in the appropriate column of Part I of this Schedule Qlim, namely—
2. In any case where the isotopic composition of a radioactive substance is not known or is only partially known, the quantity ratio for that substance shall be calculated by using the values specified in the appropriate column in Part I for “other radionuclides not listed above” for any radionuclide that has not been identified or where the quantity of a radionuclide is uncertain, unless the employer can show that the use of some other value is appropriate in the circumstances of a particular case, when he may use that value.
Regulation 6(4)
The following particulars are required to be included in an assessment report under regulation 6(4)—
(a)the name and address of the operator or carrier;
(b)the postal address of the premises where the radioactive substance will be processed, manufactured, used or stored, or where the facilities for processing, manufacture, use or storage exist or, in the case of transport, the postal address of the transport undertaking;
(c)the date on which it is anticipated that the work with ionising radiation will commence or, if it has already commenced, a statement to that effect;
(d)a general description of the premises or place including the geographical location, meteorological, geological, hydrographic conditions and, where material, the history of the premises, except that in the case of transport a general description shall be given of either—
(i)the starting and end points of the journey and transhipment points, or
(ii)the criteria to be used for route selection;
(e)in the case of an assessment by an operator, a description of any radioactive substance on the premises which is likely to exceed any quantity or mass specified in Schedule 2 or Schedule 3, as the case may be, which description shall where practicable include details of the radionuclides present and their likely maximum quantities;
(f)in the case of an assessment by a carrier, a description of any radioactive substance which is likely to exceed any quantity or mass specified in Schedule 4 or Schedule 3, as the case may be, which description shall where practicable include details of the radionuclides present and their likely maximum quantities;
(g)except in the case of an assessment relating to transport, a plan of the premises in question and a map of the environs to a scale large enough to enable the premises and any features which could affect the general risk in an emergency to be identified;
(h)a diagram and description of any single plant or enclosed system containing more than the quantity or mass of any radioactive substance specified in Schedule 2 or Schedule 3, as the case may be, or, in the case of the transport of more than the quantity or mass of any radioactive substance specified in Schedule 4 or Schedule 3, as the case may be, the nature of the containment for the radioactive substance, the type of vehicle and the means of securing the load within or on the vehicle;
(i)those factors which could precipitate a major release of any radioactive substance and the measures to be taken to prevent or control such release and information showing the maximum quantity of radioactive substance which, in the event of a major failure of containment, would be released to the atmosphere including, in respect of premises, the identification of plant and other activities anywhere on the premises which could precipitate such release;
(j)those factors which could precipitate a smaller but continuing release of any radioactive substance and the measures to be taken to prevent or control such releases to atmosphere;
(k)those factors which could give rise to an incident involving the initiation of an unintended self-sustaining nuclear chain reaction or the loss of control of an intended self-sustaining nuclear chain reaction and, in either case, the measures to be taken to prevent or control any such incident;
(l)information concerning the management systems and staffing arrangements by which the radioactive substance is controlled and by which the procedures are controlled;
(m)except in the case of an assessment relating to transport, information about the size and distribution of the population in the vicinity of premises to which the report relates;
(n)an assessment of the area which is likely to be affected by the dispersal of any radioactive substance as a result of any radiation emergency and the period of time over which such dispersal is likely to take place;
(o)an assessment of the likely exposures to ionising radiation of any person or class of persons as a result of any radiation emergency; and
(p)an assessment of the necessity for an emergency plan to be prepared by the operator or carrier.
Regulation 6(5)
A further assessment and report may be required under regulation 6(5) in respect of the following matters—
(a)the analysis carried out to establish the likely consequences of any hazard, including the likely doses of ionising radiation to which members of the public might be exposed, and the probability of the occurrence of such hazard;
(b)the number of persons whose health or safety might be affected by the hazard;
(c)the management systems and staffing arrangements by which any hazard is to be or is controlled;
(d)the safety systems, procedures and monitoring systems by which any hazard is to be or is controlled;
(e)the qualifications, experience and training of staff concerned;
(f)the design, construction, operation or maintenance of any equipment (including the incorporation of adequate safety or reliability features of such equipment) which is used for the purposes of intervention or which is used to control any hazard;
(g)the design and operating documentation;
(h)the design and operation of containment and pressure systems;
(i)the protection of persons from the effects of loss of containment; and
(j)the procedures for the reporting of and learning from radiation emergencies.
Regulations 7(2), 8(2) and 9(2)
The information referred to in regulation 7(2) is as follows—
(a)the names or positions of persons authorised to set emergency procedures in motion and the person in charge of and co-ordinating the on-site mitigatory action;
(b)the name or position of the person with responsibility for liaison with the local authority responsible for preparing the off-site emergency plan;
(c)for reasonably foreseeable conditions or events which could be significant in bringing about a radiation emergency, a description of the action which should be taken to control the conditions or events and to limit their consequences, including a description of the safety equipment and the resources available;
(d)the arrangements for limiting the risks to persons on the premises including how warnings are to be given and the actions persons are expected to take on receipt of a warning;
(e)the arrangements for providing early warning of the incident to the local authority responsible for setting the off-site emergency plan in motion, the type of information which should be contained in an initial warning and the arrangements for the provision of more detailed information as it becomes available;
(f)the arrangements for providing assistance with off-site mitigatory action; and
(g)the arrangements for emergency exposures including the dose levels which have been determined as appropriate for the purposes of putting into effect the emergency plan.
The information referred to in regulation 8(2) is as follows—
(a)the names or positions of persons authorised to set emergency procedures in motion and the person in charge of and co-ordinating the mitigatory action;
(b)for reasonably foreseeable conditions or events which could be significant in bringing about a radiation emergency, a description of the action which should be taken to control the conditions or events and to limit their consequences, including a description of the safety equipment and the resources available;
(c)the arrangements for providing early warning of the incident, the type of information which should be contained in an initial warning and the arrangements for the provision of more detailed information as it becomes available; and
(d)the arrangements for emergency exposures including the dose levels which have been determined as appropriate for the purposes of putting into effect the emergency plan.
The information referred to in regulation 9(2) is as follows—
(a)the names or positions of persons authorised to set emergency procedures in motion and of persons authorised to take charge of and co-ordinate the off-site mitigatory action;
(b)the arrangements for receiving early warning of incidents, and alert and call-out procedures;
(c)the arrangements for co-ordinating resources necessary to implement the off-site emergency plan;
(d)the arrangements for providing assistance with on-site mitigatory action;
(e)the arrangements for off-site mitigatory action;
(f)the arrangements for providing the public with specific information relating to the emergency and the behaviour which it should adopt; and
(g)the arrangements for emergency exposures including the dose levels which have been determined as appropriate for the purposes of putting into effect the emergency plan.
Regulations 7(4) and (5), 8(5) and (6) and 9(10) and (11)
An emergency plan drawn up pursuant to regulation 7, 8 or 9 respectively shall, in so far as it applies to any radiation emergency, be drawn up having regard to the following principles—
(a)the intervention shall be undertaken only if the reduction in the detriment due to the radiation resulting from the radiation emergency is sufficient to justify the harm and costs, including the social costs, of the intervention; and
(b)the form, scale and duration of the intervention shall be carried out in such a way as to ensure that exposures to radiation are kept as low as is reasonably practicable so that the benefit of the reduction in health detriment less the detriment associated with the intervention will be maximised.
The purposes of intervention referred to in regulations 7(5), 8(6) and regulation 9(11) are—
(a)reducing or stopping at source direct radiation and the emission of radionuclides;
(b)reducing the transfer of radioactive substances to individuals from the environment; and
(c)reducing the exposure and organising the treatment of persons who have been subject to exposure to radiation.
Regulation 16(1)
1. Basic facts about radioactivity and its effects on persons and on the environment.
2. The various types of radiation emergency covered and their consequences for the general public and the environment.
3. Emergency measures envisaged to alert, protect and assist the general public in the event of a radiation emergency.
4. Appropriate information on action to be taken by the general public in the event of a radiation emergency.
5. The authority or authorities responsible for implementing the emergency measures and action referred to in paragraphs 3 and 4 above.
Regulation 17(4)
1. Information on the type of emergency which has occurred, and, where possible, its characteristics, for example, its origin, extent and probable development.
2. Advice on health protection measures, which, depending on the type of emergency, might include—
(a)any restrictions on the consumption of certain foodstuffs and water supply likely to be contaminated;
(b)any basic rules on hygiene and decontamination;
(c)any recommendation to stay indoors;
(d)the distribution and use of protective substances;
(e)any evacuation arrangements;
(f)special warnings for certain population groups.
3. Any announcements recommending co-operation with instructions or requests by the competent authorities.
4. Where an occurrence which is likely to give rise to a release of radioactivity or ionising radiation has happened but no release has yet taken place, the information and advice should include the following—
(a)an invitation to tune in to radio or television;
(b)preparatory advice to establishments with particular collective responsibilities; and
(c)recommendations to occupational groups particularly affected.
5. If time permits, information setting out the basic facts about radioactivity and its effects on persons and on the environment.
Regulation 21
1. Paragraph 14 of Schedule 1 to the Fire Certificates (Special Premises) Regulations 1976(1) shall be deleted and the following substituted—
“14. Premises to which the Radiation (Emergency Preparedness and Public Information) Regulations 2001 apply by virtue of regulation 3 of those Regulations.”.
2. The 1999 Regulations shall be amended in accordance with paragraphs 3 to 9.
3. In regulation 21(3)(i), the word “to” shall be inserted before “maintain”.
4. In regulation 35(1), after the words “these Regulations” there shall be inserted the words “or of the Radiation (Emergency Preparedness and Public Information) Regulations 2001.”.
5. After regulation 35, there shall be inserted the following regulation—
35A. Insofar as any provision of regulation 21 is made under section 2(2) of the European Communities Act 1972, sections—
(a)16 to 21 (approval of codes of practice and enforcement);
(b)23 (provisions supplementary to sections 21 and 22) and 24 (appeal against improvement or prohibition notice), so far as they relate to an improvement notice;
(c)26 (power to indemnify inspectors); and
(d)33 to 42 (provisions as to offences),
of the Health and Safety at Work etc. Act 1974 shall apply to that provision as if that provision had been made under section 15 of that Act.”
6. Paragraph (7) of regulation 36 shall be deleted and the following substituted—
“(7) Where a contravention of these Regulations by any person is due to the act or default of some other person, that other person shall be guilty of the offence which would, but for any defence under this regulation available to the first-mentioned person, be constituted by the act or default.”.
7. In paragraph 6 of Schedule 4, after “trainee” there shall be inserted the words “referred to in paragraphs 1 or 3”.
8. In paragraph 19 of Schedule 4, in place of “pursuant to regulation 11(2)” there shall be substituted “in accordance with regulation 11(1)”.
9. In column 1 of Schedule 8, under the entry for Ruthenium, in place of “Ru-160+”, there shall be substituted “Ru-106+”.
10. In Schedule 7 of the Reporting of Injuries, Diseases and Dangerous Occurrences Regulations 1995(2)—
(a)“The Ionising Radiations Regulations 1985” shall be deleted and “The Ionising Radiations Regulations 1999” substituted; and
(b)after the final entry there shall be added: “The Radiation (Emergency Preparedness and Public Information) Regulations 2001.”.
S.I.1985/1333, revoked (subject to a saving) by regulation 41 of the Ionising Radiations Regulations 1999.
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