Conversion and or Fuel Fabrication Plants- Design Inform

IAEA Design Information Questionnaire Forms

IAEA DIQ Conversion and-or fuel fabrication plants

Design Information Questionnaire - IAEA N-71, and Associated Forms N-72, N-73, N-74, N-75, N-76-, N-77, N-91, N-92, N-93, N-94

OMB: 3150-0056

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CONVERSION AND-OR FUEL FABRICATION PLANTS
APPROVED BY OMB: NO. 3150-0056

EXPIRES: (MM/DD/YYYY)

Estimated burden per response to comply with this mandatory collection request: 360 hours. NRC is
required to collect this information for reporting to IAEA from facility licensees appearing on the U.S.
Eligible List. Send comments regarding burden estimate to the FOIA, Library, and Information
Collections Branch (T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001,
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and Regulatory Affairs, (3150-0056), Attn: Desk Officer for the Nuclear Regulatory Commission, 725
17th Street NW, Washington, DC 20503; email: [email protected]. The NRC may not
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INTERNATIONAL ATOMIC ENERGY AGENCY
DEPARTMENT OF SAFEGUARDS

DESIGN INFORMATION
QUESTIONNAIRE *
IAEA USE ONLY

The purpose of this document is to
obtain the facility design information
required by the Agency in order to
discharge its safeguards responsibilities.
It will also serve as a checklist for
examination of design information by
Agency inspector(s). If, in any area,
insufficient space is available add further
shee ts to the extent necessary.

IAEA USE ONLY
COUNTRY

COUNTRY OFFICER

TYPE

DATE OF INITIAL DATA

VERIFICATION

LAST REVIEW AND UPDATING

N-73 (MM-DD-YYYY)

Conversion and-or fuel
fabrication plants

ALL FACILITIES
GENERAL INFORMATION
1. Name of the facility
(include usual abbreviation)
2. Location and postal
address
3. Owner
(Legally responsible)
4. Operator
(Legally responsible)
5. Description
(Main features only)

6. Purpose

7. Status
(e.g., planned; under construction,
in operation; shut down; closed
down; decommissioned)
Start of Construction (MM/DD/YYYY)

Commissioning (MM/DD/YYYY)

8. Construction schedule dates
(if not in operation)
9. Normal operating mode
(days only, two shift, three shift;
number of days/annum, etc.)
10. Facility layout
(structural containment, fences,
access, nuclear material storage
areas, laboratories, waste disposal
areas, routes followed by nuclear
material, experimental and test areas,
etc.)

DRAWING(S) ATTACHED UNDER REF. NOs.

DRAWING(S) AND/OR MAPS ATTACHED UNDER REF. NOs.
11. Sitting of facility
(Maps showing in sufficient detail:
location, premises and perimeter of
facility, other buildings, roads, railways,
rivers, etc.)

12. Names and/or titles and address
of responsible officers
(for nuclear material accountancy and
control and contact with the Agency. If
possible attach organization charts
showing position of officers)

N-73 (MM-DD-YYYY)

Operation (MM/DD/YYYY)

OVERALL PROCESS PARAMETERS
GENERAL FLOW DIAGRAM(S) ATTACHED UNDER REF. NOs. (The diagram(s) should also indicate
13. Facility description
equipment, hoods, cells, and those areas which contain nuclear material as those specific areas where hold(indicating important items of
up of nuclear material can occur.)
equipment which use, produce or
process nuclear material, all process
stages, storage areas and feed,
product and waste points as pertaining
to the measurement, control and
accountancy of nuclear material)
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
annum)
16. Anticipated annual throughput
(in the form of a forward programme
(if applicable), indicating the proportion
of various feeds and products)
17. Other important items of
equipment using, producing or
processing nuclear material
(such as testing and experimental
equipment)

NUCLEAR MATERIAL DESCRIPTION AND FLOW
18. Main material description
i) Main types of accountability units to
be handled in the facility
ii) 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). Attach
drawing(s)
iii) Throughput, enrichment ranges and
Pu contents
(for normal flowsheet operation
indicating if blending and/or recycling
takes place)
iv) Batch size/flow rate and campaign
period, means of batch identification
v) Storage and plant inventory
(indicating any change with
throughput)
vi) Frequency of receipt or shipment
(batches/units per month)

N-73 (MM-DD-YYYY)

Feed

Intermediate product
(powder, pellets, etc. separately stored
or shipped)

Product

NUCLEAR MATERIAL DESCRIPTION AND FLOW
19. Scrap material

20. Waste material
(including contaminated equipment,
measured discards and retained
waste)
Describe for each waste stream:
i) Major contributions (sources)

ii) Types of waste

iii) Chemical and physical form
(liquid, solid, etc.)
iv) Estimated enrichment ranges and
uranium/plutonium content
v) Estimated quantities per year,
period of storing
vi) Waste generated rates (as % of
input/ throughput, quantities per
month)

vii) Store inventory range and
maximum capacity

viii) Method and frequency of
recovery/disposal
DIAGRAM(S) ATTACHED UNDER FIG. NOs.
21. Waste treatment system

DIAGRAM(S) ATTACHED UNDER REF. NOs.
22. Other nuclear material in the
facility and it's location, if any

DIAGRAM(S) ATTACHED UNDER REF. NOs.
23. Schematic flowsheet for nuclear
material
(identifying sampling points, flow and
inventory measurement points,
accountability areas, inventory
locations, etc.)

N-73 (MM-DD-YYYY)

NUCLEAR MATERIAL DESCRIPTION AND FLOW
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, i.
e.:
-- process area
-- storage area
-- other locations
(Also indicate maximum quantities of
nuclear material to be handled in
accountability areas at the one time.)
25. Recycle processes
(briefly describe 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)

DIAGRAM(S) ATTACHED UNDER REF. NOs.

26. Inventory
(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)
i) In-process

ii) Feed and product storages
iii) Other locations
(quantity, range of enrichment, Pu
content, form and location of inventory
not already specified)

NUCLEAR MATERIAL HANDLING (FOR EACH ACCOUNTABILITY AREA)
DRAWING(S) ATTACHED UNDER REF. NOs.

27. Containers, packaging and
storage area description

SEPARATE NOTE TO BE ATTACHED.
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)

N-73 (MM-DD-YYYY)

DRAWING(S) ATTACHED UNDER REF. NOs.

PLANT MAINTENANCE
SEPARATE NOTE TO BE ATTACHED.

31. Maintenance,
decontamination, clean-out

Describing plans and procedures for decontamination and clean-out of equipment containing nuclear material,
defining all sampling and measurement points associated with:
(In cases where clean-out and/or sampling is not possible, indicate how the hold-up of nuclear material is
measured or calculated.)

i) Normal plant maintenance
ii) Plant and equipment
decontamination and subsequent
nuclear material recovery
iii) Plant and equipment clean-out
including means of ensuring vessels
are empty
iv) Plant start-up and and plant
shut-down (If different from normal
operation)

PROTECTION AND SAFETY MEASURES
32. Basic measures for physical
protection of nuclear material
33. Specific health and safety rules
for inspector compliance
(if extensive, attach separately)

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
34. System description
Give a description of the nuclear
material accountancy system, the
method of recording and reporting
accountancy data and establishing
material balances, frequency of
material balances, procedures for
account adjustment after plant
inventory, mistakes, etc., under the
following headings:
i) General
(This section should also state what
general and subsidiary ledgers will be
used, their form (hard copies, tapes,
microfilms, etc.) as well as who has the
responsibility and authority. Source
data (e.g. shipping and receiving
forms, internal transfer documents,
physical inventory forms, the initial
recording of measurements and
measurement control sheets) should
be identified. The procedures for
making adjustments, the source data
and records should be covered as well
as how the adjustments are authorized
and substantiated.)

ii) Receipts
(including method of dealing with
shipper/receiver differences and
subsequent account corrections; the
checks and measurements used to
confirm nuclear material content and
the persons responsible for those
determinations should be defined)
N-73 (MM-DD-YYYY)

SPECIMEN FORMS USED IN ALL PROCEDURES ATTACHED UNDER REF. No.

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
iii) Shipments
(products, waste, measured discards)
LIST OF MAJOR ITEMS OF EQUIPMENT REGARDED AS NUCLEAR MATERIAL CONTAINERS
iv) Physical inventory
Description of procedures, scheduled ATTACHED UNDER REF. NOS.
frequency, estimated distribution of
nuclear material, methods of operator's
inventory taking (both for item and/or
bulk accountancy, 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
should also provide the basic inventory
approach to be used, i.e. planning,
organizing, and conducting the
inventory, prelisting, use of prior
measurement data; who has the
primary responsibility for the inventory;
how process clean-out is
accomplished; the accountancy of
process residual hold-up.)
v) Measured discards
(method of estimation of quantities per
year/month, method of disposal)
vi) Retained waste
(method of estimation of quantities per
year, method and envisaged period of
storage; indicate also possible
subsequent uses of retained waste)
vii) Unmeasured losses
(indicate the methods used to estimate
unmeasured losses)
viii) Operational records and accounts
(including logbooks, general ledgers,
internal transfer forms, method of
adjustment or correction and retention
location, and languages; control
measures and responsibility for
records)
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,
identified in particular under Qs. 13,
23, 24, Give the following:
For each measurement point fill in
separate sheet.
Number of measurement points: 1
i) Description of location, type,
identification
ii) Expected types of inventory change
at this measurement point

N-73 (MM-DD-YYYY)

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
iii) Possibilities to use this
measurement point for physical
inventory taking
iv) Physical and chemical form of
nuclear material (including enrichment
range, Pu content, and cladding
materials description)
v) Nuclear material containers,
packaging and method of storage
vi) Sampling procedure and
equipment used (including number of
samples taken, frequency and
rejection criteria)
vii) Measurement/analytical method(s)
and equipment used and
corresponding accuracies
viii) Source and level of random and
systematic errors for feed, product,
scrap, waste (weight, volume,
sampling, analytical)
ix) Calculative and error propagation
techniques
x) Technique and frequency of
calibration of equipment used, and
standards used

xi) Programme for the continuing
appraisal of the accuracy of weight,
volume, sampling and analytical
techniques and measurement methods

xii) Programme for statistical
evaluation of data from (x) and (xi)

xiii) Method of converting source data
to batch data
(standard calculative procedures,
constants and empirical relationships
for feed, products in sub-accounting
areas, waste and scrap)

xiv) Means of batch identification
xv) Anticipated batch flow rate per
year

N-73 (MM-DD-YYYY)

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
xvi) Anticipated number of inventory
batches
xvii) Anticipated number of items per
flow and inventory batches
xviii) 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)
xix) Features related to containmentsurveillance measures
37. Overall limit of error
Describe procedures to combine
individual measurement error
determination to obtain the overall limit
of error for:
i) S/R differences
ii) Book inventory

iii) Physical inventory

iv)

MUF

POST-OPERATION INFORMATION
38. Decommissioning
schedule dates
39. Facility decommissioning
plan

End of operations (MM/DD/YYYY)

PLAN(s) ATTACHED UNDER REF. NOs

i) Key events of the decommissioning
plan
ii) Removal and recovery of nuclear
material
iii) Removing or rendering inoperable
essential equipment

OPTIONAL INFORMATION
40. Optional information

(that the operator considers relevant to
safeguarding the facility)

Signature of Responsible Officer

Date (MM/DD/YYYY)

N-73 (MM-DD-YYYY)

Decommissioned (MM/DD/YYYY)


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