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Annex I-C

Annex I-C

ANNEX I-C

CONVERSION AND FUEL FABRICATION INSTALLATIONS

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 of 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, boundaries, buildings, roads, rivers, railways, etc.).

11.

Layout of installation:

structural containment, fences and access routes;

containment of certain parts of the installation;

routes followed by nuclear material;

nuclear material storage areas;

each main processing area and process laboratory;

test or experimental areas;

waste storage area;

analytical laboratory.

12.

Safeguards responsible, also for nuclear material accountancy, with e-mail address (functional mailbox when available) and telephone number.

Overall process parameters

13.

Description of the installation (indicating main items of equipment).

14.

Process description (indicating type of conversion, method of fabrication, sampling methods, etc., indicating also the modification of physical and chemical forms).

15.

Design capacity (in weight of principal products per year).

16.

Anticipated throughput (in the form of a forward programme indicating proportion of various feeds and products).

17.

Other important items of equipment using, producing or processing nuclear material (such as testing and experimental equipment).

GENERAL ARRANGEMENTS AT THE INSTALLATION, INCLUDING THOSE RELATING TO MATERIAL USE AND ACCOUNTANCY, CONTAINMENT AND SURVEILLANCE

Description of nuclear material

18.

Main material description (feed, intermediate product, product):

chemical and physical form (for product include types of fuel element/assemblies, give detailed description indicating general structure and overall structure and overall dimensions of fuel element/assemblies, including nuclear material content and enrichment);

throughput, enrichment ranges and Pu contents (for normal flowsheet operation indicating if blending and/or recycling takes place);

batch size/flow rate and campaign period, means of batch identification;

maximum value of storage/plant inventory;

frequency of receipt or shipment (batches/units per month).

19.

Scrap material.

20.

Waste material (including contaminated equipment and retained waste). For each waste stream, description of:

major contributions (sources);

types of waste;

chemical and physical form (liquid, solid, etc.);

estimated enrichment ranges and uranium/plutonium content;

estimated quantities per year, period of storing;

waste generated rates (as % of input/ throughput, quantities per month);

store inventory range and maximum capacity;

method and frequency of recovery/discharge.

21.

Waste treatment system (attach diagrams).

22.

Other nuclear material in the installation and its location, if any.

23.

Schematic flowsheet for nuclear material (identifying sampling points, flow and inventory measurement points, accountability areas, inventory locations, etc.).

24.

Types, form, ranges of nuclear material content (including enrichment, as applicable), ranges of quantities of nuclear material flow for each nuclear material handling area.

25.

Recycle processes (brief description of any such processes giving source and form of material, method of storage, normal inventory, frequency of processing, duration of temporary storage, schedules for any external recycling, measurement method of fissile content of recycle material).

26.

Maximum capacity:

in-process (within plant and equipment during normal operation, indicate quantity, range of enrichment, Pu content, form and principal locations and any significant change in time or throughput; indicate anticipated residual hold-up and mechanism, e.g. plate out, condensation);

feed and product storages;

other locations (quantity, range of enrichment, Pu content, form and location of inventory not already specified).

Handling of nuclear material

27.

Containers, packaging and storage area description. Describe for feeds, products and wastes: the type and size of storage and shipping containers and packaging used (including nominal capacity and capacity for normal operation, and type of material); method of storage or packing, filling and emptying procedures, shielding; and any special identification features.

28.

Methods and means of transfer of nuclear material (describe also equipment used for handling of feed, product, waste).

29.

Transportation routes followed by nuclear material (with reference to plant layout).

30.

Shielding (for storage, transfer and process area).

Maintenance of the installation

31.

Maintenance, decontamination, clean-out (in cases where clean-out and/or sampling is not possible, indicate how the hold-up of nuclear material is measured or calculated):

normal maintenance of the installation;

installation and equipment decontamination and subsequent nuclear material recovery;

installation and equipment clean-out including means of ensuring vessels are empty;

installation start-up and plant shut-down (if different from normal operation).

Protection and safety rules

32.

Specific rules for the physical access to the nuclear material for inspector information.

33.

Specific radiological protection and health and safety rules for inspector compliance (if extensive, attach separately).

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL (NMAC)

34.

Description of the NMAC system, the method of recording and reporting accountancy data and establishing material balances, frequency of physical inventory takings, procedures for account adjustment after plant inventory, mistakes, etc., under the following headings:

General

Source data (e.g. shipping and receiving forms, internal transfer documents, physical inventory forms, the initial recording of measurements and measurement control sheets). Procedures for making adjustments and corrections (indicating how the adjustments are authorized and substantiated);

Receipts (including method of dealing with shipper/receiver differences and subsequent accounting corrections; checks and measurements used to confirm nuclear material content);

Shipments (products, waste);

Transfers to retained waste (method of establishing quantities, method and envisaged period of storage, possible subsequent uses of retained waste);

Discards to the environment (method of establishing quantities, method of discharge);

Other inventory changes, e.g. transfers to conditioned waste, unmeasured losses (method of establishing quantities);

Physical inventory

Description of procedures, scheduled frequency, estimated distribution of nuclear material, methods of operator’s inventory taking (both for the number of items as well as their nuclear material weights, including relevant assay method), accessibility and possible verification method for nuclear material, expected accuracy, and access to nuclear material. In particular the description of procedures shall also provide the basic inventory approach to be used, i.e. planning, organizing, and conducting the inventory taking, primary responsibility for inventory taking, process clean-out, accountancy of process residual hold-up;

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.

35.

Features related to containment and surveillance measures (general description of applied or possible measures in reference to floor plan or plant layout).

36.

For each flow and inventory measurement point, and sampling points of accountability areas, give the following:

description of location, type, identification;

expected types of inventory change at this measurement point and possibility to use this measurement point for physical inventory taking;

physical and chemical form of nuclear material (including enrichment range, Pu content, and cladding materials description);

nuclear material containers, packaging and method of storage;

sampling procedure and equipment used (including number of samples taken, frequency and rejection criteria);

measurement/analytical method(s) and equipment used and corresponding accuracies;

source and level of random and systematic errors for feed, product, scrap, waste (weight, volume, sampling, analytical);

calculative and error propagation techniques;

technique and frequency of calibration of equipment used, and standards used;

programme for the continuing appraisal of the accuracy of weight, volume, sampling and analytical techniques and measurement methods;

programme for statistical evaluation of data from (i) and (j);

means of batch identification;

anticipated batch flow rate per year;

anticipated number of inventory batches;

anticipated number of items per flow and inventory batches;

type, composition and quantity of nuclear material per batch (with indication of batch data, total weight of each element of nuclear material and form of nuclear material);

features related to containment-surveillance measures.

37.

Overall limit of error. Describe procedures to combine individual measurement error determination to obtain the overall limit of error for:

shipper/receiver differences;

book inventory;

physical inventory;

material unaccounted for (MUF).

POST-OPERATION INFORMATION

38.

Decommissioning schedule dates (end of operation and of decommissioning dates).

39.

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

40.

Other optional information that the operator considers relevant to safeguarding the installation.

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