ANNEX I-A
POWER AND RESEARCH REACTORS
Administrative details:
(a) | date (date on which the BTC was completed); |
(b) | version (unique number for reference); |
(c) | responsible officer (name and contact details). |
IDENTIFICATION OF THE INSTALLATION
1. | Name of the installation (indicate usual abbreviation, if applicable). Indicate MBA code(s) (once attributed). |
2. | Location, postal and e-mail address (functional mailbox when available) and telephone number. |
3. | Owner (legally responsible body or individual) with contact details. |
4. | Operator (legally responsible body or individual) with contact details. |
5. | Description (main features only). |
6. | Purpose and type of the installation. |
7. | Present status (e.g. design phase, under construction, in operation, closed down and/or under decommissioning). |
8. | Pre-operation information Design and construction schedule dates, estimated commissioning and operation starting dates. Requested and/or approved licence dates (e.g. decision in principle, construction and expected operation licence request dates). Information on expected date of receipts of the nuclear material. Installation design drawings to be communicated as soon as these are available. |
9. | Normal operating mode (shift system adopted, approximate dates of operating periods in year, etc.). |
10. | Area layout (map showing the installation, reactor(s) and storage areas, boundaries, buildings, roads, rivers, railways, etc.). |
11. | Layout of installation: identification of main areas (structural containment, fences and access routes); incoming-material storage area; reactor(s) area; test and experiment area, laboratories; outgoing-material storage area; waste storage area. |
12. | Safeguards responsible, also for nuclear material accountancy, with e-mail address (functional mailbox when available) and telephone number. |
General reactor data
13. | Description of the installation (indicating main items of equipment). |
14. | Rated thermal and electricity output (when applicable). |
15. | Number of units. |
16. | Reactor type. |
17. | Type of refuelling (cycle length, on-load or off-load, percentage of fuel reloading). |
18. | Core enrichment range and Pu concentration (at equilibrium for on-load reactors, initial and final for off-load reactors). |
19. | Moderator. |
20. | Coolant. |
21. | Blanket, reflector. |
GENERAL ARRANGEMENTS AT THE INSTALLATION, INCLUDING THOSE RELATING TO MATERIAL USE AND HANDLING
Description of nuclear material
22. | Types of fresh fuel. |
23. | Fresh fuel enrichment (U-235) and/or Pu content (average enrichment for each type of assembly). |
24. | Nominal weight of fuel in elements/assemblies with design tolerances. |
25. | Detailed description of reactor assemblies: type of fuel assemblies; number of fuel assemblies, control and shim assemblies, experimental assemblies in the core, in blanket zone(s); number and types of fuel rods/elements; average enrichment and/or Pu content per assembly; general structure; geometric form; overall dimensions; cladding material. |
26. | Detailed description of each type of fresh fuel: physical and chemical form of fuel; nuclear material and its quantity; enrichment and/or Pu content; geometric form; dimensions; number of rods/pins per element; chemical composition or main alloy constituents; cladding material (thickness, composition of material, bonding). |
27. | Provision for pin exchange in each type of fuel assemblies. Indicate whether this is foreseen to become a routine operation. |
28. | Basic operational accounting units (fuel elements/assemblies, etc.). |
29. | Other types of accounting units. |
30. | Means of nuclear material and/or fuel identification. |
31. | Other nuclear material and dummies (e.g. shielding, fission chambers, sources, etc.). |
Flow of nuclear material
32. | Schematic flow sheet for nuclear material (identifying measurement points, accountability areas, inventory locations). |
33. | Inventory with quantity range including uranium enrichment and plutonium content, number of items in Key Measurement Points (under normal operating conditions) in: fresh fuel storage; reactor core; spent fuel storage; other locations. |
34. | Load factor. |
35. | Reactor core loading (number of elements and assemblies). |
36. | Refuelling requirements. |
37. | Burn-up, average and maximum. |
38. | Indicate the way to handle irradiated fuel assemblies (to be dry/wet stored or reprocessed). |
Handling of nuclear material
39. | General arrangement for fresh fuel: layout, storage plan and packaging; capacity of store; fuel preparation and assay room and reactor loading area, description and indication of layout and general arrangement. |
40. | Fuel transfer equipment (including refuelling machine). |
41. | Routes followed by fresh fuel, irradiated fuel, blanket and other nuclear material. |
42. | Reactor vessel (showing core location, access to vessel, vessel openings and fuel handling in vessel). |
43. | Reactor core diagram (showing general disposition, lattice, form, pitch, dimensions of core, reflector, blanket, location, shapes and dimensions of fuel elements/assemblies, control elements/assemblies, experimental elements/assemblies). |
44. | Number and size of channels for fuel elements or assemblies and for control elements in the core. |
45. | Average mean neutron flux in the core (thermal/fast). |
46. | Instrumentation for measuring neutron and gamma flux. |
47. | General arrangement for irradiated fuel: layout, spent fuel storages; method of storage; design capacity of storage; minimum and normal cooling period prior to shipment; description of irradiated fuel transport equipment and shipping cask. |
48. | Maximum radiation level of fuel/blanket after refuelling (dose rate at the surface and at a distance of 1 meter). |
49. | Methods and equipment used for handling irradiated fuel (pin removal, top nozzle) |
50. | Nuclear material testing area (if applicable): brief description of the activities performed; description of main equipment (e.g. hot cell, fuel assembly decladding and dissolving equipment); description of shipping and storage containers for nuclear material and of waste and scrap packaging (e.g. to determine whether sealing is possible); description of storage area for non-irradiated and irradiated nuclear material; layout and general arrangement. |
Coolant data
51. | Flow diagram (indicating mass flow, temperature and pressure at major points, etc.). |
Protection and safety rules
52. | Specific rules for the physical access to the nuclear material for inspector information. |
53. | Specific radiological protection and health and safety rules for inspector compliance. |
NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL (NMAC)
54. | The NMAC system shall be described under the following headings: General Description of the accountancy system used to record and report accountancy data, including method of recording accountancy data and establishing material balance; Main inventory changes Description of typical inventory changes e.g. receipts, shipments (including waste), nuclear loss and production, including a description of how these changes are determined. The corresponding operational records and source data (e.g. receiving and shipping forms, the initial recording of measurements and measurement control sheets) shall be identified; Physical inventory Description of procedures, scheduled frequency, methods of operator’s inventory taking (both for the number of items as well as their nuclear material weights), including relevant assay methods and expected accuracy, access to nuclear material, possible methods for the physical verification of fresh and irradiated nuclear materials; Operational and accounting records (including internal transfer forms, method of adjustment or correction, control measures and responsibility for records). Description of how these records are maintained, including when an adjustment or correction is needed, place where the records can be consulted, retention time and language; Particular accounting provisions Description of particular provisions, e.g. for the designation of batch IDs and methods for preventing, detecting and timely fixing of accounting discrepancies. |
55. | Provisions related to existing or foreseen containment and surveillance measures (general description in reference to floor plan and installation layout enabling to install seals, cameras, lasers, remote data transmission, etc.). |
56. | For each measurement point of the material balance area provide the following information, when applicable: location, type, identification; anticipated types of inventory changes; possibility to use this measurement point for physical inventory taking; physical and chemical form of nuclear material; nuclear material containers and packaging; sampling procedures and equipment used; measurement methods and equipment used for item counting, neutron flux, power level, nuclear burn-up and production etc; source and level of accuracy; technique and frequency of calibration of equipment used; programme for the continuing appraisal of the accuracy of methods and techniques used; method of converting source data to batch data (calculative procedures, constant used, etc.); anticipated batch flow per year; anticipated number of inventory batches; anticipated number of items per flow; type, composition and estimated quantity of nuclear material per batch (average), form of nuclear material and typical isotopic composition; access to nuclear material and its location. |
POST-OPERATION INFORMATION
57. | Decommissioning schedule dates (end of operation and of decommissioning dates). |
58. | Decommissioning plan, which shall include the following: key events of the decommissioning plan; removal and recovery of nuclear material. Provide a plan containing estimates of how, where and when nuclear material shall be recovered and/or removed (e.g. loose material consolidated into items, removal of items, recovery/removal of material from decontamination activities, and recovery/removal of nuclear material in waste) and how it shall be accounted for; removing or rendering inoperable of equipment essential for the functioning of the installation, for handling or storing nuclear material. |
OTHER INFORMATION RELEVANT FOR THE APPLICATION OF SAFEGUARDS
59. | Other optional information and drawings that the operator considers relevant to safeguarding the installation. |