The Nuclear Safeguards (Notification) Regulations 2004

• Citation: S.I. 2004/1255
• Sections: 39

Section 1 Citation and commencement

These Regulations may be cited as the Nuclear Safeguards (Notification) Regulations 2004, and shall come into force on 5th May 2004.

Section 2 Interpretation

In these Regulations:

“ Annex II ” means Annex II to the Additional Protocol ;

“ electronic communications network ” has the same meaning as in section 32 of the Communications Act 2003 ;

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“ high enriched uranium ” means uranium containing 20 per cent or more of the isotope uranium-235;

“ non-nuclear-weapon State ” means a State other than China, France, Russia, the United Kingdom and the United States of America;

“ nuclear fuel cycle-related research and development activities ” means research and development activities which are specifically related to any process or system development aspect of—

the enrichment of nuclear material,

the reprocessing of nuclear fuel, or

the processing of intermediate or high level waste containing plutonium, high enriched uranium, or uranium-233

but does not include activities related to theoretical or basic scientific research or to research and development on industrial radioisotope applications, medical, hydrological or agricultural applications, health or environmental effects or improved maintenance;

“ nuclear material ” means any source material (other than ore or ore residue) or any special fissionable material;

“the ONR ” means the Office for Nuclear Regulation;

“ processing of intermediate or high level waste ” does not include—

repackaging of the waste for storage or disposal,

conditioning of the waste not involving the separation of elements, for storage or disposal;

“ source material ” means uranium containing the mixture of isotopes occurring in nature, uranium depleted in the isotope 235, thorium, and any of the foregoing in the form of metal, alloy, chemical compound or concentrate;

“ special fissionable material ” means plutonium-239, uranium-233, uranium containing the isotopes 235 or 233 or both in an amount such that the abundance ratio of the sum of these isotopes to the isotope 238 is greater than the ratio of the isotope 235 to the isotope 238 occurring in nature, and any material containing one or more of the foregoing.

Section 3 Persons required to notify the Secretary of State

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Section 4

(1) Subject to regulation 5, a person shall notify the ONR on or before 15th January in each year if at any time during the previous calendar year he has carried out in the United Kingdom any of the activities specified in paragraph 1 of the Schedule.

(2) Subject to regulation 5, a person shall notify the ONR on or before 15th January in each year if at any time during the previous calendar year he has carried out in the United Kingdom any nuclear fuel cycle-related research and development activities which were:

(a) carried out in co-operation with, or otherwise relevant to, a non-nuclear-weapon State; and

(b) not funded, specifically authorised or controlled by, or carried out on behalf of, Her Majesty's Government.

Section 5 Persons not required to notify the ONR

(1) The ONR may serve on a person a written notice setting out particulars which the ONR already has in relation to that person.

(2) A person on whom a notice has been served under paragraph (1) is not required to notify the ONR under regulation ... 4 if the particulars set out in the notice are accurate at the time the notice is received by that person and are all the particulars which that person would be required to provide under these Regulations but for this paragraph.

(3) A person who by virtue of paragraph (2) is not required to notify the ONR under regulation ...4 shall, within 14 days of any change in any of the particulars which were set out in the notice served on him under paragraph (1), give to the ONR notice of the new particulars.

(4) Section 10 of the Nuclear Safeguards Act 2000 applies in relation to the service by the ONR of notices under paragraph (1).

Section 6 Form of notification to the ONR

(1) A person who is required to notify the ONR under regulation ... 4 shall do so by giving a notice to the ONR containing particulars of his name, his proper address (within the meaning of section 10(3) of the Nuclear Safeguards Act 2000), each activity, referred to in the regulation in question, which he has carried out during the relevant period and the address of each place at or from which he has carried out each such activity.

(2) A person who has given particulars to the ONR pursuant to paragraph (1) shall, within 14 days of any change in any of those particulars, give to the ONR notice of the new particulars.

(3) Any notice to be given by a person under paragraph (1) or (2), or under regulation 5(3), shall be in writing and sent by post or delivered to the Office for Nuclear Regulation at the address given on its website as its postal address , or sent by means of an electronic communications network to the address given on the Office’s website as its address for electronic communications .

Section 1

The activities referred to in regulation 4(1) are :

(i) the manufacture of centrifuge rotor tubes or the assembly of gas centrifuges;

(ii) the manufacture of diffusion barriers;

(iii) the manufacture or assembly of laser-based systems;

(iv) the manufacture or assembly of electromagnetic isotope separators;

(v) the manufacture or assembly of columns or extraction equipment;

(vi) the manufacture of aerodynamic separation nozzles or vortex tubes;

(vii) the manufacture or assembly of uranium plasma generation systems;

(viii) the manufacture of zirconium tubes;

(ix) the manufacture or upgrading of heavy water or deuterium;

(x) the manufacture of nuclear grade graphite;

(xi) the manufacture of flasks for irradiated fuel;

(xii) the manufacture of reactor control rods;

(xiii) the manufacture of criticality safe tanks and vessels;

(xiv) the manufacture of irradiated fuel element chopping machines;

(xv) the construction of hot cells.

Section 1 Complete nuclear reactors

Nuclear reactors capable of operation so as to maintain a controlled self-sustaining fission chain reaction, excluding zero energy reactors, the latter being defined as reactors with a designed maximum rate of production of plutonium not exceeding 100 grams per year.

Section 1 Reactor control rods

Rods especially designed or prepared for the control of the reaction rate in a nuclear reactor as defined in paragraph 1.1. above.

Section 1 Zirconium tubes

Zirconium metal and alloys in the form of tubes or assemblies of tubes, and in quantities exceeding 500 kg in any period of 12 months, especially designed or prepared for use in a reactor as defined in paragraph 1.1. above, and in which the relation of hafnium to zirconium is less than 1:500 parts by weight.

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Section 2

In paragraph 1:

“ centrifuge rotor tubes ” means thin-walled cylinders as described in entry 5.1.1(b);

“ gas centrifuges ” means centrifuges as described in the Introductory Note to entry 5.1;

“ diffusion barriers ” means thin, porous filters as described in entry 5.3.1(a);

“ laser-based systems ” means systems incorporating those items described in entry 5.7;

“ electromagnetic isotope separators ” means those items referred to in entry 5.9.1 containing ion sources as described in entry 5.9.1(a);

“ columns or extraction equipment ” means those items as described in entries 5.6.1, 5.6.2, 5.6.3, 5.6.5, 5.6.6, 5.6.7 and 5.6.8;

“ aerodynamic separation nozzles or vortex tubes ” means separation nozzles and vortex tubes as described respectively in entries 5.5.1 and 5.5.2;

“ uranium plasma generation systems ” means systems for the generation of uranium plasma as described in entry 5.8.3;

“ zirconium tubes ” means tubes as described in entry 1.6;

“ heavy water or deuterium ” means deuterium, heavy water (deuterium oxide) and any other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds 1:5000;

“ nuclear grade graphite ” means graphite having a purity level better than 5 parts per million boron equivalent and with a density greater than 1.50g/cm 3 ;

“ flask for irradiated fuel ” means a vessel for the transportation and/or storage of irradiated fuel which provides chemical, thermal and radiological protection, and dissipates decay heat during handling, transportation and storage;

“ reactor control rods ” means rods as described in entry 1.4;

“ criticality safe tanks and vessels ” means those items as described in entries 3.2 and 3.4;

“ irradiated fuel element chopping machines ” means equipment as described in entry 3.1;

“ hot cells ” means a cell or interconnected cells totalling at least 6m 3 in volume with shielding equal to or greater than the equivalent of 0.5m of concrete, with a density of 3.2g/cm 3 or greater, outfitted with equipment for remote operations.

Section 3

The numbered entries referred to in paragraph 2 are the entries so numbered in Annex II, which entries are set out (with other entries referred to in them) in Part II of this Schedule.

Section 5 PLANTS FOR THE SEPARATION OF ISOTOPES OF URANIUM AND EQUIPMENT, OTHER THAN ANALYTICAL INSTRUMENTS, ESPECIALLY DESIGNED OR PREPARED THEREFOR

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Section 5 Rotating components

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(b) Rotor tubes:

Especially designed or prepared thin-walled cylinders with thickness of 12 mm (0.5 in) or less, a diameter of between 75 mm (3 in) and 400 mm (16 in), and manufactured from one or more of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

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Section 5 Gaseous diffusion barriers

(a) Especially designed or prepared thin, porous filters, with a pore size of 100-1,000 Å (angstroms), a thickness of 5 mm (0.2 in) or less, and for tubular forms, a diameter of 25 mm (1 in) or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF 6 ...

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Section 5 Separation nozzles

Especially designed or prepared separation nozzles and assemblies thereof. The separation nozzles consist of slit-shaped, curved channels having a radius of curvature less than 1 mm (typically 0.1 to 0.05 mm), resistant to corrosion by UF 6 and having a knife-edge within the nozzle that separates the gas flowing through the nozzle into two fractions.

Section 5 Vortex tubes

Especially designed or prepared vortex tubes and assemblies thereof. The vortex tubes are cylindrical or tapered, made of or protected by materials resistant to corrosion by UF 6 , having a diameter of between 0.5 cm and 4 cm, a length to diameter ratio of 20:1 or less and with one or more tangential inlets. The tubes may be equipped with nozzle-type appendages at either or both ends.

Section 5 Liquid-liquid exchange columns (Chemical exchange)

Countercurrent liquid-liquid exchange columns having mechanical power input (i.e., pulsed columns with sieve plates, reciprocating plate columns, and columns with internal turbine mixers), especially designed or prepared for uranium enrichment using the chemical exchange process. For corrosion resistance to concentrated hydrochloric acid solutions, these columns and their internals are made of or protected by suitable plastic materials (such as fluorocarbon polymers) or glass. The stage residence time of the columns is designed to be short (30 seconds or less).

Section 5 Liquid-liquid centrifugal contactors (Chemical exchange)

Liquid-liquid centrifugal contactors especially designed or prepared for uranium enrichment using the chemical exchange process. Such contactors use rotation to achieve dispersion of the organic and aqueous streams and then centrifugal force to separate the phases. For corrosion resistance to concentrated hydrochloric acid solutions, the contactors are made of or are lined with suitable plastic materials (such as fluorocarbon polymers) or are lined with glass. The stage residence time of the centrifugal contactors is designed to be short (30 seconds or less).

Section 5 Uranium reduction systems and equipment (Chemical exchange)

(a) Especially designed or prepared electrochemical reduction cells to reduce uranium from one valence state to another for uranium enrichment using the chemical exchange process. The cell materials in contact with process solutions must be corrosion resistant to concentrated hydrochloric acid solutions.

Section 5 Uranium oxidation systems (Chemical exchange)

Especially designed or prepared systems for oxidation of U 3 + to U 4 + for return to the uranium isotope separation cascade in the chemical exchange enrichment process.

Section 5 Fast-reacting ion exchange resins/adsorbents (Ion exchange)

Fast-reacting ion-exchange resins or adsorbents especially designed or prepared for uranium enrichment using the ion exchange process, including porous macroreticular resins, and/or pellicular structures in which the active chemical exchange groups are limited to a coating on the surface of an inactive porous support structure, and other composite structures in any suitable form including particles or fibers. These ion exchange resins/adsorbents have diameters of 0.2 mm or less and must be chemically resistant to concentrated hydrochloric acid solutions as well as physically strong enough so as not to degrade in the exchange columns. The resins/adsorbents are especially designed to achieve very fast uranium isotope exchange kinetics (exchange rate half-time of less than 10 seconds) and are capable of operating at a temperature in the range of 100°C to 200°C.

Section 5 Ion exchange columns (Ion exchange)

Cylindrical columns greater than 1,000 mm in diameter for containing and supporting packed beds of ion exchange resin/adsorbent, especially designed or prepared for uranium enrichment using the ion exchange process. These columns are made of or protected by materials (such as titanium or fluorocarbon plastics) resistant to corrosion by concentrated hydrochloric acid solutions and are capable of operating at a temperature in the range of 100°C to 200°C and pressures above 0.7 MPa (102 psia).

Section 5 Ion exchange reflux systems (Ion exchange)

(a) Especially designed or prepared chemical or electrochemical reduction systems for regeneration of the chemical reducing agent(s) used in ion exchange uranium enrichment cascades.

(b) Especially designed or prepared chemical or electrochemical oxidation systems for regeneration of the chemical oxidizing agent(s) used in ion exchange uranium enrichment cascades.

Section 5 Uranium vaporization systems (AVLIS)

Especially designed or prepared uranium vaporization systems which contain high-power strip or scanning electron beam guns with a delivered power on the target of more than 2.5 kW/cm.

Section 5 Liquid uranium metal handling systems (AVLIS)

Especially designed or prepared liquid metal handling systems for molten uranium or uranium alloys, consisting of crucibles and cooling equipment for the crucibles.

Section 5 Uranium metal “product” and “tails” collector assemblies (AVLIS)

Especially designed or prepared “product” and “tails” collector assemblies for uranium metal in liquid or solid form.

Section 5 Separator module housings (AVLIS)

Especially designed or prepared cylindrical or rectangular vessels for containing the uranium metal vapor source, the electron beam gun, and the “product” and “tails” collectors.

Section 5 Supersonic expansion nozzles (MLIS)

Especially designed or prepared supersonic expansion nozzles for cooling mixtures of UF 6 and carrier gas to 150 K or less and which are corrosion resistant to UF 6 .

Section 5 Uranium pentafluoride product collectors (MLIS)

Especially designed or prepared uranium pentafluoride (UF 5 ) solid product collectors consisting of filter, impact, or cyclone-type collectors, or combinations thereof, and which are corrosion resistant to the UF 5 /UF 6 environment.

Section 5 UF 6 /carrier gas compressors (MLIS)

Especially designed or prepared compressors for UF 6 /carrier gas mixtures, designed for long term operation in a UF 6 environment. The components of these compressors that come into contact with process gas are made of or protected by materials resistant to corrosion by UF 6 .

Section 5 Rotary shaft seals (MLIS)

Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor rotor with the driver motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal gas into the inner chamber of the compressor which is filled with a UF 6 /carrier gas mixture.

Section 5 Fluorination systems (MLIS)

Especially designed or prepared systems for fluorinating UF 5 (solid) to UF 6 (gas).

Section 5 UF 6 mass spectrometers/ion sources (MLIS)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking “on-line” samples of feed, “product” or “tails”, from UF 6 gas streams and having all of the following characteristics:

(1) Unit resolution for mass greater than 320;

(2) Ion sources constructed of or lined with nichrome or monel or nickel plated;

(3) Electron bombardment ionization sources;

(4) Collector system suitable for isotopic analysis.

Section 5 Feed systems/product and tails withdrawal systems (MLIS)

Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF 6 , including:

(a) Feed autoclaves, ovens, or systems used for passing UF 6 to the enrichment process;

(b) Desublimers (or cold traps) used to remove UF 6 from the enrichment process for subsequent transfer upon heating;

(c) Solidification or liquefaction stations used to remove UF 6 from the enrichment process by compressing and converting UF 6 to a liquid or solid form;

(d) “Product” or “tails” stations used for transferring UF 6 into containers.

Section 5 UF 6 /carrier gas separation systems (MLIS)

Especially designed or prepared process systems for separating UF 6 from carrier gas. The carrier gas may be nitrogen, argon, or other gas.

Section 5 Laser systems (AVLIS, MLIS and CRISLA)

Lasers or laser systems especially designed or prepared for the separation of uranium isotopes.

Section 5 Uranium plasma generation systems

Especially designed or prepared systems for the generation of uranium plasma, which may contain high-power strip or scanning electron beam guns with a delivered power on the target of more than 2.5 kW/cm.

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Section 5 Electromagnetic isotope separators

Electromagnetic isotope separators especially designed or prepared for the separation of uranium isotopes, and equipment and components therefor, including:

(a) Ion sources

Especially designed or prepared single or multiple uranium ion sources consisting of a vapor source, ionizer, and beam accelerator, constructed of suitable materials such as graphite, stainless steel, or copper, and capable of providing a total ion beam current of 50 mA or greater.

(b) Ion collectors

Collector plates consisting of two or more slits and pockets especially designed or prepared for collection of enriched and depleted uranium ion beams and constructed of suitable materials such as graphite or stainless steel.

(c) Vacuum housings

Especially designed or prepared vacuum housings for uranium electromagnetic separators, constructed of suitable non-magnetic materials such as stainless steel and designed for operation at pressures of 0.1 Pa or lower.