Spent Fuel Encapsulation Plants- Design Information Ques

IAEA Design Information Questionnaire Forms

IAEA DIQ Spent Fuel Encapsulation Plants

OMB: 3150-0056

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SPENT FUEL ENCAPSULATION PLANTS
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-77 (MM-DD-YYYY)

Spent Fuel Encapsulation 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-77 (MM-DD-YYYY)

Operation (MM/DD/YYYY)

OVERALL PROCESS PARAMETERS
13. Facility description
GENERAL FACILITY DIAGRAM(S) ATTACHED UNDER REF. NOs.)
(indicating important items of
equipment which use, produce or
process nuclear material, all process
stages, storage areas and points as
pertaining to the measurement, control
and accountancy of nuclear material)
PROCESS FLOW SHEET ATTACHED UNDER REF. NOs.)
14. Process description

15. Design capacity
(e.g. number of spent fuel assemblies
or CANDU bundles, other quantities of
nuclear material in metric tons)
16. Anticipated annual disposals
(e.g. number of spent fuel assemblies
or CANDU bundles, other quantities of
nuclear material in effective kilograms)
17. Other important items of
equipment processing nuclear
material, if any

NUCLEAR MATERIAL DESCRIPTION AND FLOW
18. Main material description
i) Main types of nuclear materials and
accountability units to be handled in
the facility
ii) Physical (mechanical) form,
cladding, and overall dimensions of
spent fuel assemblies or CANDU
bundles
iii) Physical (mechanical) form, overall
dimensions, and capacity of disposal
canisters

DRAWING(S) ATTACHED UNDER REF. NOs.

DRAWING(S) ATTACHED UNDER REF. NOs.

DRAWING(S) ATTACHED UNDER REF. NOs.
iv) Physical form and overall
dimensions of other types of
containers and packaging

v) Means of item identification

vi) Range of initial weights of heavy
metal and initial enrichments of
uranium in fuel assemblies
vii) Range of spent fuel burn-ups,
cooling times, and Pu contents of fuel
assemblies
viii) Means of batch identification,
batch size, flow rate, and campaign
period

N-77 (MM-DD-YYYY)

NUCLEAR MATERIAL DESCRIPTION AND FLOW
ix) Range of radiation levels in nuclear
material storage and process areas
x) Range of radiation and heat levels
at exterior of transport and disposal
containers
xi) Frequency of receipt and shipment
(batches/units per month)
19. Other nuclear material in the
facility and its location, if any
20. Schematic flowsheet for nuclear DRAWING(S) ATTACHED UNDER REF. NOs.
material
(identify flow and inventory
measurement points, accountability
areas, inventory locations, etc.)
21. Nuclear material flow quantities
for each nuclear material handling
area
(including range and maximum
quantities of nuclear material at one
time) i.e.:
-- process area (handling cell)
-- storage area (input fuel assemblies;
disposal canisters)
-- other locations
22. Design range of inventories of
nuclear material in each storage
area and process area

NUCLEAR MATERIAL HANDLING
23. Container and packaging
description
i) Describe containers and packaging
in which nuclear material is received:
-- TYPE:
-- MATERIAL:
-- CAPACITY (In terms of spent fuel
assemblies or CANDU bundles and
other nuclear material):
-- IDENTIFICATION FEATURES:
-- SIZE:
ii) Describe containers and packaging
in which nuclear material is shipped:
(Inner container and over pack
container:
-- TYPE:
-- MATERIAL:
-- CAPACITY (In terms of spent fuel
assemblies or CANDU bundles and
other nuclear material):
-- IDENTIFICATION FEATURES:
-- SIZE:
iii) Range of radiation and heat
levels at exterior of storage and
transport packages and disposal
canisters

N-77 (MM-DD-YYYY)

DRAWING(S) ATTACHED UNDER REF. NOs.

NUCLEAR MATERIAL HANDLING
24. Description of each nuclear
material storage and process area
(Including range of radiation levels in
nuclear material storage and process
areas)

DRAWING(S) ATTACHED UNDER REF. NOs.

25. Shielding
(for storage and transfer)
26. Methods and means of handling
and transport of nuclear material
(Including loading into disposal
containers)
27. Transportation routes followed
by nuclear material
(With reference to plant layout)

PLANT MAINTENANCE
28. Maintenance, decontamination
i) Normal plant maintenance
ii) Plant and equipment
decontamination
iii) Plant start-up and plant shutdown
procedures if different from normal
operation

PROTECTION AND SAFETY MEASURES
29. Basic measures for physical
protection of nuclear material
30. Specific health and safety rules
for inspector compliance

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
31. System description
Give a description of the nuclear
material accountancy system, the
method of recording and reporting
accountancy data and establishing
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)

N-77 (MM-DD-YYYY)

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

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
ii) Receipts
(including method of dealing with
account corrections; the checks and
measurements used to confirm spent
fuel items, and the persons
responsible for those determinations
should be defined)
iii) Shipments

iv) Physical inventory
(Description of procedures and
methods of operator's inventory taking
(for item accountancy), frequency,
estimated distribution and accessibility
of nuclear material, and verification
method, and expected accuracy for
nuclear material measurements. 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)

v) 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)

32. Features related to containment
and surveillance measures
(general description of applied or
possible measures in reference to floor
plan or plant layout)
SEPARATE SHEET(S) CAN BE ATTACHED FOR EACH MEASUREMENT POINT. IF NECESSARY,
33. For each flow and inventory
ATTACH DRAWING(S)
measurement point identified under
Question 20, Give the following:
For each measurement point fill in
separate sheet.
Number of measurement points: 1
i) Description of location, type
identification

ii) Types of inventory change at this
measurement point

iii) Possibilities to use this
measurement point for physical
inventory taking

N-77 (MM-DD-YYYY)

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
iv) Description of nuclear material
(including physical and chemical form,
cladding, initial and final heavy metal
weight, initial and final uranium isotopic
composition, burn-up, cooling time,
and Pu content)
v) Nuclear material containers,
packaging, and method of storage
vi) Item identification and
containment-surveillance measures
(including special identifying features
and radiation and heat characteristics
of disposal canisters)
vii) Measurement equipment used and
corresponding accuracies
(including radiation measurements of
fuel assemblies in handling cell)
viii) Measurement control, including
technique and frequency of calibration
of equipment used, and standards
used
ix) Method of converting source data
to batch data

x) Means of batch identification

xi) Anticipated batch flow rate per year

xii) Anticipated number of inventory
batches
xiii) Anticipated number of items per
flow and inventory batches
xiv) 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)

POST-OPERATION INFORMATION
End of operations (MM/DD/YYYY)

34. Decommissioning
schedule dates
PLAN(s) ATTACHED UNDER REF. NOs
35. Facility decommissioning
plan

N-77 (MM-DD-YYYY)

Decommissioned (MM/DD/YYYY)

POST-OPERATION INFORMATION
i) Key events of the
decommissioning plan

ii) Removal and recovery of
nuclear material

iii) Removing or rendering
inoperable of essential equipment

OPTIONAL INFORMATION
36. Optional information

(that the operator considers relevant to
safeguarding the facility)

Signature of Responsible Officer

Date (MM/DD/YYYY)

N-77 (MM-DD-YYYY)


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