N- 72 Research and Power Reactors - Design Information Questio

RESEARCH AND POWER REACTORS
APPROVED BY OMB: NO. 3150-0056

EXPIRES: (MM/DD/YYYY)

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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-72 (MM-YYYY)

Research and power reactors

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.)

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-72 (MM-YYYY)

DRAWING(S) ATTACHED UNDER REF. NOs.

DRAWING(S) AND/OR MAPS ATTACHED UNDER REF. NOs.

Operation (MM/DD/YYYY)

GENERAL REACTOR DATA
GENERAL FLOW DIAGRAM(S) ATTACHED UNDER REF. NOs.
13. Facility description
(indicating important items of
equipment which use, produce or
process nuclear material)

14. Rated thermal output,
Electricity Output
(for power reactors)
15. Number of units (reactors) and
their layout in the facility
16. Reactor type
17. Type of refueling
(on or off load)
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

NUCLEAR MATERIAL DESCRIPTION
22. Types of fresh fuel
23. Fresh fuel enrichment
(U-235) and/or Pu content
(average enrichment per each type of
assembly)

24. Nominal weight of fuel in
elements/assemblies
(with design tolerances)

25. Physical and chemical form of
fresh fuel
(General Description)

N-72 (MM-YYYY)

NUCLEAR MATERIAL DESCRIPTION
DRAWING(S) ATTACHED UNDER REF. NOs.
26. Reactor assemblies*
(Indicate for each type)
• types of 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;
• dimensions;
• cladding material
* Assembly is the combination of
elements or handling units such as
cluster or bundle.
** Element is the smallest contained
fuel unit.

DRAWING(S) ATTACHED UNDER REF. NOs.
27. Description of fresh fuel
elements
• physical and chemical form of fuel;
• nuclear material and fissionable
material and its quantity (with design
tolerances);
• enrichment and/or Pu content;
• geometric form;
• dimensions;
• number of slugs/pellets per element;
• composition of alloy;
• cladding material (thickness,
composition of material, bonding)

28. Provision for element
exchange in assemblies of each
type
(Indicate whether this is foreseen
to become a routine operation)
29. Basic operational accounting
unit(s)
(Fuel elements/assemblies, etc.)

30. Other types of units
31. Means of nuclear material/
fuel identification
32. Other nuclear material in
the facility (Each separately
identified)

N-72 (MM-YYYY)

DRAWING(S) ATTACHED UNDER REF. NOs.

NUCLEAR MATERIAL FLOW
33. Schematic flow sheet for
nuclear material the facility
(Identifying measurement points,
accountability areas, inventory
locations, etc.)

34. Inventory state quantity range,
number of items, and approximate
uranium enrichment and plutonium
content for (Under normal operating
conditions)
i) Fresh Fuel Storage
ii) Reactor Core
iii) Spent Fuel Storage
iv) Other Locations

DRAWING(S) ATTACHED UNDER REF. NOs.

i) Fresh Fuel Storage

ii) Reactor Core

iii) Spent Fuel Storage

iv) Other Locations
35. Load factor
(Power Reactor Only)
36. Reactor core loading
(Number of Elements/
Assemblies
37. Refueling requirements
(Quantity, Time Interval)
38. Burn-up
(Average/maximum)
39. Is the irradiated fuel to be
reprocessed or stored?
(If stored, indicate site)

NUCLEAR MATERIAL HANDLING
40. Fresh fuel
i) Packaging (description)

DRAWING(S) ATTACHED UNDER REF. NOs.
ii) Layout, general arrangements
and storage plan
iii) Capacity of store

DRAWING(S) ATTACHED UNDER REF. NOs.
iv) Fuel preparation and assay
room, and reactor loading area
(description and indication of layout
and general arrangement)

N-72 (MM-YYYY)

NUCLEAR MATERIAL HANDLING
DRAWING(S) ATTACHED UNDER REF. NOs.
41. Fuel transfer equipment
(including refueling machines)
42. Routes followed by nuclear
material
(fresh fuel, irradiated fuel, blanket,
other material)

DRAWING(S) ATTACHED UNDER REF. NOs.
43. Reactor vessel
(showing core location, access to
vessel, vessel openings, fuel handling
in vessel)

DRAWING(S) ATTACHED UNDER REF. NOs.
44. 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)

45. Number and size of channels
for fuel elements or assemblies and
for control elements in the core
46. Average mean neutron flux in
the core:

i) Thermal:

ii) Fast:

47. Instrumentation for measuring
neutron and gamma
flux

48. Irradiated fuel

DRAWING(S) ATTACHED UNDER REF. NOs.
i) Layout, spent fuel storage plan
and general arrangement (internal
and external)

ii) Method of storage

N-72 (MM-YYYY)

NUCLEAR MATERIAL HANDLING
iii) Design capacity of storage
iv) Minimum and normal cooling
period prior to shipment

DRAWING(S) ATTACHED UNDER REF. NOs.
v) Description of irradiated fuel
transport equipment and shipping
cask
(If no information on site, where is it
held?)

49. Maximum activity of fuel/blanket
after refueling
(at the surface and at a distance of 1
meter)

50. Methods and equipment for
handling irradiated fuel
(except for that already given under
Qs. 41, 48.v)

51. Nuclear material testing areas
(except as already given under Q. 40)
For each such area briefly describe

i) Nature of activities

ii) Major equipment available
(e.g., hot cell, fuel element decladding
and dissolution equipment)

iii) Shipping containers Used
(main-material, scrap and waste)

iv) Storage Areas for both
unirradiated and irradiated materials

DRAWING(S) ATTACHED UNDER REF. NOs.

v) Layout and general arrangement

N-72 (MM-YYYY)

COOLANT DATA
DRAWING(S) ATTACHED UNDER REF. NOs.
52. Flow diagram
(indicating mass flow, temperature and
pressure at major points, etc.)

PROTECTION AND SAFETY MEASURES
53. Basic measures for physical
protection of nuclear material

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

NUCLEAR MATERIAL ACCOUNTANY AND CONTROL
SPECIMEN FORMS USED IN ALL PROCEDURES ATTACHED UNDER REF. NOs.
55. System description
Give a description of the nuclear
material accounting system, of the
method of recording and reporting
accountancy data, the procedures for
account adjustment after inventory,
and correction of 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, 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

iii) Shipments

N-72 (MM-YYYY)

NUCLEAR MATERIAL ACCOUNTANY AND CONTROL
LIST OF MAJOR ITEMS OF EQUIPMENT REGARDED AS NUCLEAR MATERIAL
CONTAINERS ATTACHED UNDER REF. NOs.

iv) Physical inventory
description of procedures,
scheduled frequency, methods of
operator's inventory taking (both for
item and/or mass accountancy),
including relevant assay methods
and expected accuracy, access to
nuclear material, possible
verification method for irradiated
nuclear material, methods of
verification of nuclear material in
the core

v) Nuclear loss and production
(Estimation of elements)

vi) Operational records and
accounts (including method of
adjustment or correction and
place preservation and language)

56. Features related to containment
and surveillance measures (General
description)

57. For each measurement point of
accountability areas,
identified in particular under Qs. 13,
33, 34, Give the following
(If applicable)
For each measurement point fill in
separate sheet.
Number of measurement points: 1

i) Description of location, Type,
identification

ii) Anticipated types of inventory
change and possibility to use this
measurement point for physical
inventory taking

iii) Physical and chemical form of
nuclear material (with cladding
materials description)
iv) Nuclear material containers,
packaging

N-72 (MM-YYYY)

IF NECESSARY, ATTACH DRAWING(S)

NUCLEAR MATERIAL ACCOUNTANY AND CONTROL
v) Sampling procedures and
equipment used
vi) Measurement method(s) and
equipment used (item counting,
neutron flux, power level, nuclear burnup and production, etc.)
vii) Source and level of accuracy

viii) Technique and frequency of
calibration of equipment used

ix) Program for the counting
appraisal of the accuracy of
methods and techniques used

x) Method of converting source
data to batch data
(standard calculative procedures,
constants used, empirical
relationships, etc.)

xi) Anticipated batch flow for year

xii) Anticipated number of items per
flow and inventory batches

xiii) Type, composition and quantity
of nuclear material per batch
(with indication of batch data, total
weight of each element of nuclear
material and, in the case of plutonium
and uranium, the isotopic composition
when appropriate; form of nuclear
material)

xiv) Access to nuclear material and
its location

xv) Features related to
containment-surveillance measures

N-72 (MM-YYYY)

OPTIONAL INFORMATION
End of operations (MM/DD/YYYY)

58. Decommissioning
schedule dates
PLAN(s) ATTACHED UNDER REF. NOs
59. Facility decommissioning
plan

i) Key events of the
decommissioning plan

ii) Removal and recovery of
nuclear material

iii) Removing or rendering
inoperable of essential equipment

Signature of Responsible Officer

Date (MM/DD/YYYY)

N-72 (MM-YYYY)

Decommissioned (MM/DD/YYYY)