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2004 No. 1255

NUCLEAR SAFEGUARDS

The Nuclear Safeguards (Notification) Regulations 2004

  Made 1st May 2004 
  Laid before Parliament 4th May 2004 
  Coming into force 5th May 2004 

The Secretary of State, in exercise of the powers conferred on her by section 3(1) of the Nuclear Safeguards Act 2000[1], hereby makes the following Regulations:

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

Interpretation
    
2. In these Regulations:

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;

Persons required to notify the Secretary of State
     3.  - (1) Subject to regulation 5, a person shall notify the Secretary of State not later than two months after the commencement date if at any time during the period of six months ending on the commencement date 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 Secretary of State not later than two months after the commencement date if at any time during the period of six months ending on the commencement date he has carried out in the United Kingdom any nuclear fuel cycle-related research and development activities which were:

     4.  - (1) Subject to regulation 5, a person shall notify the Secretary of State 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 Secretary of State 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:

Persons not required to notify the Secretary of State
    
5.  - (1) The Secretary of State may serve on a person a written notice setting out particulars which the Secretary of State 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 Secretary of State under regulation 3 or 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 Secretary of State under regulation 3 or 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 Secretary of State notice of the new particulars.

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

Form of notification to the Secretary of State
    
6.  - (1) A person who is required to notify the Secretary of State under regulation 3 or 4 shall do so by giving a notice to the Secretary of State 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 Secretary of State pursuant to paragraph (1) shall, within 14 days of any change in any of those particulars, give to the Secretary of State 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 Safeguards Office, Department of Trade and Industry, 4 Abbey Orchard Street, London SW1P 2HT, or sent by means of an electronic communications network to ukso@dti.gsi.gov.uk.


Nigel Griffiths,
Parliamentary Under Secretary of State for Small Business and Enterprise, Department of Trade and Industry

1st May 2004



SCHEDULE
Regulations 3(1) and 4(1)



PART I

ACTIVITIES REFERRED TO IN REGULATIONS 3(1) AND 4(1)

     1. The activities referred to in regulations 3(1) and 4(1) are:

     2. In paragraph 1:

     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.



PART II

EXTRACTS FROM ANNEX II TO THE ADDITIONAL PROTOCOL

     1. REACTORS AND EQUIPMENT THEREFOR


     1.1. 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.

EXPLANATORY NOTE
A "nuclear reactor" basically includes the items within or attached directly to the reactor vessel, the equipment which controls the level of power in the core, and the components which normally contain or come in direct contact with or control the primary coolant of the reactor core.

It is not intended to exclude reactors which could reasonably be capable of modification to produce significantly more than 100 grams of plutonium per year. Reactors designed for sustained operation at significant power levels, regardless of their capacity for plutonium production, are not considered as "zero energy reactors".



     1.4. 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.

EXPLANATORY NOTE
This item includes, in addition to the neutron absorbing part, the support or suspension structures therefor if supplied separately.



     1.6. 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.



     3. PLANTS FOR THE REPROCESSING OF IRRADIATED FUEL ELEMENTS, AND EQUIPMENT ESPECIALLY DESIGNED OR PREPARED THEREFOR


INTRODUCTORY NOTE
Reprocessing irradiated nuclear fuel separates plutonium and
uranium from intensely radioactive fission products and other transuranic elements. Different technical processes can accomplish this separation. However, over the years Purex has become the most commonly used and accepted process. Purex involves the dissolution of irradiated nuclear fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products by solvent extraction using a mixture of tributyl phosphate in an organic diluent.

Purex facilities have process functions similar to each other, including: irradiated fuel element chopping, fuel dissolution, solvent extraction, and process liquor storage. There may also be equipment for thermal denitration of uranium nitrate, conversion of plutonium nitrate to oxide or metal, and treatment of fission product waste liquor to a form suitable for long term storage or disposal. However, the specific type and configuration of the equipment performing these functions may differ between Purex facilities for several reasons, including the type and quantity of irradiated nuclear fuel to be reprocessed and the intended disposition of the recovered materials, and the safety and maintenance philosophy incorporated into the design of the facility.

A "plant for the reprocessing of irradiated fuel elements" includes the equipment and components which normally come in direct contact with and directly control the irradiated fuel and the major nuclear material and fission product processing streams.

These processes, including the complete systems for plutonium conversion and plutonium metal production, may be identified by the measures taken to avoid criticality (e.g. by geometry), radiation exposure (e.g. by shielding), and toxicity hazards (e.g. by containment).

Items of equipment that are considered to fall within the meaning of the phrase "and equipment especially designed or prepared" for the reprocessing of irradiated fuel elements include:

     3.1. Irradiated fuel element chopping machines


INTRODUCTORY NOTE
This equipment breaches the cladding of the fuel to expose the irradiated nuclear material to dissolution. Especially designed metal cutting shears are the most commonly employed, although advanced equipment, such as lasers, may be used.

Remotely operated equipment especially designed or prepared for use in a reprocessing plant as identified above and intended to cut, chop or shear irradiated nuclear fuel assemblies, bundles or rods.

     3.2. Dissolvers


INTRODUCTORY NOTE
Dissolvers normally receive the chopped-up spent fuel. In these critically safe vessels, the irradiated nuclear material is dissolved in nitric acid and the remaining hulls removed from the process stream.

Critically safe tanks (e.g. small diameter, annular or slab tanks) especially designed or prepared for use in a reprocessing plant as identified above, intended for dissolution of irradiated nuclear fuel and which are capable of withstanding hot, highly corrosive liquid, and which can be remotely loaded and maintained.



     3.4. Chemical holding or storage vessels


INTRODUCTORY NOTE
Three main process liquor streams result from the solvent extraction step. Holding or storage vessels are used in the further processing of all three streams, as follows:

Especially designed or prepared holding or storage vessels for use in a plant for the reprocessing of irradiated fuel. The holding or storage vessels must be resistant to the corrosive effect of nitric acid. The holding or storage vessels are normally fabricated of materials such as low carbon stainless steels, titanium or zirconium, or other high quality materials. Holding or storage vessels may be designed for remote operation and maintenance and may have the following features for control of nuclear criticality:

    (1) walls or internal structures with a boron equivalent of at least two per cent, or

    (2) a maximum diameter of 175 mm (7 in) for cylindrical vessels, or

    (3) a maximum width of 75 mm (3 in) for either a slab or annular vessel.



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


     5.1. Gas centrifuges and assemblies and components especially designed or prepared for use in gas centrifuges


INTRODUCTORY NOTE
The gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm (3 in) and 400 mm (16 in) diameter contained in a vacuum environment and spun at high peripheral speed of the order of 300 m/s or more with its central axis vertical. In order to achieve high speed the materials of construction for the rotating components have to be of a high strength to density ratio and the rotor assembly, and hence its individual components, have to be manufactured to very close tolerances in order to minimize the unbalance. In contrast to other centrifuges, the gas centrifuge for uranium enrichment is characterized by having within the rotor chamber a rotating disc-shaped baffle(s) and a stationary tube arrangement for feeding and extracting the UF6 gas and featuring at least 3 separate channels, of which 2 are connected to scoops extending from the rotor axis towards the periphery of the rotor chamber. Also contained within the vacuum environment are a number of critical items which do not rotate and which although they are especially designed are not difficult to fabricate nor are they fabricated out of unique materials. A centrifuge facility however requires a large number of these components, so that quantities can provide an important indication of end use.

     5.1.1. Rotating components




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.



EXPLANATORY NOTE
The materials used for centrifuge rotating components are:



     5.3.1. Gaseous diffusion barriers




     5.5.1. 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 UF6 and having a knife-edge within the nozzle that separates the gas flowing through the nozzle into two fractions.

     5.5.2. 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 UF6, 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.

EXPLANATORY NOTE
The feed gas enters the vortex tube tangentially at one end or through swirl vanes or at numerous tangential positions along the periphery of the tube.



     5.6.1. 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).

     5.6.2. 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).

     5.6.3. Uranium reduction systems and equipment (Chemical exchange)


EXPLANATORY NOTE
The cell cathodic compartment must be designed to prevent re-oxidation of uranium to its higher valence state. To keep the uranium in the cathodic compartment, the cell may have an impervious diaphragm membrane constructed of special cation exchange material. The cathode consists of a suitable solid conductor such as graphite.

EXPLANATORY NOTE
These systems consist of solvent extraction equipment for stripping the U4⫀ from the organic stream into an aqueous solution, evaporation and/or other equipment to accomplish solution pH adjustment and control, and pumps or other transfer devices for feeding to the electrochemical reduction cells. A major design concern is to avoid contamination of the aqueous stream with certain metal ions. Consequently, for those parts in contact with the process stream, the system is constructed of equipment made of or protected by suitable materials (such as glass, fluorocarbon polymers, polyphenyl sulfate, polyether sulfone, and resin-impregnated graphite).



     5.6.5. Uranium oxidation systems (Chemical exchange)
Especially designed or prepared systems for oxidation of U3⫀ to U4⫀ for return to the uranium isotope separation cascade in the chemical exchange enrichment process.

EXPLANATORY NOTE
These systems may incorporate equipment such as:

     5.6.6. 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.

     5.6.7. 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).

     5.6.8. Ion exchange reflux systems (Ion exchange)


EXPLANATORY NOTE
The ion exchange enrichment process may use, for example, trivalent titanium (Ti3⫀) as a reducing cation in which case the reduction system would regenerate Ti3⫀ by reducing Ti4⫀.

The process may use, for example, trivalent iron (Fe3⫀) as an oxidant in which case the oxidation system would regenerate Fe3⫀ by oxidizing Fe2⫀.

     5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plants


INTRODUCTORY NOTE
Present systems for enrichment processes using lasers fall into two categories: those in which the process medium is atomic uranium vapor and those in which the process medium is the vapor of a uranium compound. Common nomenclature for such processes include: first category - atomic vapor laser isotope separation (AVLIS or SILVA); second category - molecular laser isotope separation (MLIS or MOLIS) and chemical reaction by isotope selective laser activation (CRISLA). The systems, equipment and components for laser enrichment plants embrace: (a) devices to feed uranium-metal vapor (for selective photo-ionization) or devices to feed the vapor of a uranium compound (for photo-dissociation or chemical activation); (b) devices to collect enriched and depleted uranium metal as "product" and "tails" in the first category, and devices to collect dissociated or reacted compounds as "product" and unaffected material as "tails" in the second category; (c) process laser systems to selectively excite the uranium-235 species; and (d) feed preparation and product conversion equipment. The complexity of the spectroscopy of uranium atoms and compounds may require incorporation of any of a number of available laser technologies.

EXPLANATORY NOTE
Many of the items listed in this section come into direct contact with uranium metal vapor or liquid or with process gas consisting of UF6 or a mixture of UF6 and other gases. All surfaces that come into contact with the uranium or UF6 are wholly made of or protected by corrosion-resistant materials. For the purposes of the section relating to laser-based enrichment items, the materials resistant to corrosion by the vapor or liquid of uranium metal or uranium alloys include yttria-coated graphite and tantalum; and the materials resistant to corrosion by UF6 include copper, stainless steel, aluminium, aluminium alloys, nickel or alloys containing 60% or more nickel and UF6-resistant fully fluorinated hydrocarbon polymers.

     5.7.1. 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.

     5.7.2. 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.

EXPLANATORY NOTE
The crucibles and other parts of this system that come into contact with molten uranium or uranium alloys are made of or protected by materials of suitable corrosion and heat resistance. Suitable materials include tantalum, yttria-coated graphite, graphite coated with other rare earth oxides or mixtures thereof.

     5.7.3. 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.

EXPLANATORY NOTE
Components for these assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapor or liquid (such as yttria-coated graphite or tantalum) and may include pipes, valves, fittings, "gutters", feed-throughs, heat exchangers and collector plates for magnetic, electrostatic or other separation methods.

     5.7.4. 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.

EXPLANATORY NOTE
These housings have multiplicity of ports for electrical and water feed-throughs, laser beam windows, vacuum pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow refurbishment of internal components.

     5.7.5. Supersonic expansion nozzles (MLIS)
Especially designed or prepared supersonic expansion nozzles for cooling mixtures of UF6 and carrier gas to 150 K or less and which are corrosion resistant to UF6.

     5.7.6. Uranium pentafluoride product collectors (MLIS)
Especially designed or prepared uranium pentafluoride (UF5) solid product collectors consisting of filter, impact, or cyclone-type collectors, or combinations thereof, and which are corrosion resistant to the UF5/UF6 environment.

     5.7.7. UF6/carrier gas compressors (MLIS)
Especially designed or prepared compressors for UF6/carrier gas mixtures, designed for long term operation in a UF6 environment. The components of these compressors that come into contact with process gas are made of or protected by materials resistant to corrosion by UF6.

     5.7.8. 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 UF6/carrier gas mixture.

     5.7.9. Fluorination systems (MLIS)
Especially designed or prepared systems for fluorinating UF5 (solid) to UF6 (gas).

EXPLANATORY NOTE
These systems are designed to fluorinate the collected UF5 powder to UF6 for subsequent collection in product containers or for transfer as feed to MLIS units for additional enrichment. In one approach, the fluorination reaction may be accomplished within the isotope separation system to react and recover directly off the "product" collectors. In another approach, the UF5 powder may be removed/transferred from the "product" collectors into a suitable reaction vessel (eg, fluidized-bed reactor, screw reactor or flame tower) for fluorination. In both approaches, equipment for storage and transfer of fluorine (or other suitable fluorinating agents) and for collection and transfer of UF6 are used.

     5.7.10. UF6 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 UF6 gas streams and having all of the following characteristics:

     5.7.11. 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 UF6, including:

     5.7.12. UF6/carrier gas separation systems (MLIS)
Especially designed or prepared process systems for separating UF6 from carrier gas. The carrier gas may be nitrogen, argon, or other gas.

EXPLANATORY NOTE
These systems may incorporate equipment such as:

     5.7.13. Laser systems (AVLIS, MLIS and CRISLA)
Lasers or laser systems especially designed or prepared for the separation of uranium isotopes.

EXPLANATORY NOTE
The laser system for the AVLIS process usually consists of two lasers: a copper vapor laser and a dye laser. The laser system for MLIS usually consists of a CO2 or excimer laser and a multi-pass optical cell with revolving mirrors at both ends. Lasers or laser systems for both processes require a spectrum frequency stabilizer for operation over extended periods of time.



     5.8.3. 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.



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

EXPLANATORY NOTE
The housings are specially designed to contain the ion sources, collector plates and water-cooled liners and have provision for diffusion pump connections and opening and closure for removal and reinstallation of these components.



EXPLANATORY NOTE

(This note is not part of the Regulations)


These Regulations require persons engaged in specific nuclear and nuclear-related activities to give certain details about themselves and those activities to the Secretary of State. The United Kingdom is required to provide certain information in relation to nuclear and nuclear-related activities to the International Atomic Energy Agency ("IAEA") pursuant to the Additional Protocol referred to in section 1(1) of the Nuclear Safeguards Act 2000. These Regulations enable the Secretary of State to know who may have such information.

Regulations 3 and 4 provide that a person who has carried out any of the activities referred to in the respective paragraphs of those regulations, supplemented by the Schedule, must notify the Secretary of State. The activities referred to are those specified in the Additional Protocol about which information is required to be given by the Secretary of State to the IAEA, but which may be carried on without the Secretary of State knowing other than as a result of compliance with these Regulations. The relevant provisions from the Additional Protocol are reproduced in Part II of the Schedule.

Regulation 5 negates the obligation to notify the Secretary of State where the Secretary of State already has the details which that person would otherwise have to give under the Regulations, and serves on that person a written notice setting out those details. Such a person must still notify the Secretary of State if the details set out in the notice are incomplete or wrong, or if they change.

Regulation 6 describes what details a person has to give when notifying the Secretary of State under regulation 3 or 4.

A full regulatory impact assessment has not been produced for this instrument as it has no impact on the costs of business.


Notes:

[1] 2000 c. 5.back

[2] Cm 4282.back

[3] 2003 c. 21.back



ISBN 0 11 049362 1


  © Crown copyright 2004

Prepared 4 June 2004


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