N-77 Spent Fuel Encapsulation Plants

SPENT FUEL ENCAPSULATION PLANTS
CONFIDENTIAL
WHEN COMPLETED

APPROVED BY OMB: NO. 3150-0056

DATE:
EXPIRES: (MM/DD/YYYY)

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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, Privacy, and Information Collections Branch (T-5 F53), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to Infocollects.
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information collection does not display a currently valid OMB control number, the NRC may not conduct or
sponsor, and a person is not required to respond to, the information collection.

INTERNATIONAL ATOMIC ENERGY AGENCY
DEPARTMENT OF SAFEGUARDS AND INSPECTION

DESIGN INFORMATION
QUESTIONNAIRE *
(CONTINUED)
The "Confidential" marking on this form is for IAEA
purposes only. It indicates that the IAEA considers
the information in the completed form to be
'safeguards confidential' and is not to be confused
with any U.S. security classification.

IAEA USE ONLY

* Questions which are not applicable may be left
unanswered.

SPENT FUEL ENCAPSULATION PLANTS
OVERALL PROCESS PARAMETERS
13.

FACILITY DESCRIPTION
(indicating all process stages, storage areas and
points as pertaining to the measurement, control
and accountancy of nuclear material)

GENERAL FACILITY DIAGRAM(S) ATTACHED UNDER REF. Nos.

14.

PROCESS DESCRIPTION

PROCESS FLOW SHEET ATTACHED UNDER REF. Nos.

15.

DESIGN CAPACITY
(e.g. number of spent fuel assemblies or CANDU
bundies, other quantities of nuclear material in
metric tons)

16.

ANTICIPATED ANNUAL THROUGHPUT (e.g.
number of spent fuel assemblies or CANDU
bundies, other quantities of nuclear material in
effective kilograms)

17.

IMPORTANT ITEMS OF EQUIPMENT
PROCESSING NUCLEAR MATERIAL, IF ANY
(e.g. testing and experimental equipment)

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
bundies

N-77 (MM-YYYY)

DRAWING(S) ATTACHED UNDER REF. Nos.

CONFIDENTIAL

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SPENT FUEL ENCAPSULATION PLANTS

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NUCLEAR MATERIAL DESCRIPTION AND FLOW
iii)

Physical (mechanical) form, overall dimensions,
and capacity of disposal canisters

DRAWING(S) ATTACHED UNDER REF. Nos.

iv)

Physical form and overall dimensions of other
types of containers and packaging

DRAWING(S) ATTACHED UNDER REF. Nos.

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

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
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 AND
PROCESS AREA

DRAWING(S) ATTACHED UNDER REF. Nos.

NUCLEAR MATERIAL HANDLING
23.

CONTAINER AND PACKAGING DESCRIPTION

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DRAWING(S) ATTACHED UNDER REF. Nos.

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SPENT FUEL ENCAPSULATION PLANTS

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NUCLEAR MATERIAL HANDLING
i)

Describe containers and packaging in which
nuclear material is received:
-- TYPE:
-- MATERIAL:
-- CAPACITY (In terms of spent fuel assemblies
or CANDU bundies 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 bundies and other nuclear material):
-- IDENTIFICATION FEATURES:
-- SIZE:

iii)

Range of radiation and heat levels at exterior of
storage and transport packages and disposal
canisters

24.

DESCRIPTION OF EACH NUCLEAR MATERIAL
STORAGE AND PROCESS AREA (including
range of radiation levels in nuclear material
storage and process areas)

25.

SHIELDING
(for storage and transfer)

26.

METHODS AND MEANS OF HANDLING AND
TRANSPORT OF NUCLEAR MATERIAL
(including loading into disposal containers)

DRAWING(S) ATTACHED UNDER REF. Nos.

27.

TRANSPORTATION ROUTES FOLLOWED BY
NUCLEAR MATERIAL
(with reference to plant layout)

DIAGRAM(S) ATTACHED UNDER REF. Nos.

DRAWING(S) ATTACHED UNDER REF. Nos.

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
(if extensive, attach separately)

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SPENT FUEL ENCAPSULATION PLANTS

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NUCLEAR MATERIAL ACCOUTANCY AND CONTROL
31.

i)

ii)

SYSTEM DESCRIPTION
SPECIMEN FORMS USED IN ALL PROCEDURES ATTACHED UNDER
Give a description of the nuclear material
REF. Nos.
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:

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)
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
(disposal canisters; spent fuel assemblies or
CANDU bundies and other nuclear materials, if
applicable)

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)

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SPENT FUEL ENCAPSULATION PLANTS

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NUCLEAR MATERIAL ACCOUTANCY AND CONTROL
33.

FOR EACH FLOW AND INVENTORY
MEASUREMENT POINT IDENTIFIED UNDER
QUESTION 20, GIVE THE FOLLOWING

SEPARATE SHEET(S) CAN BE ATTACHED FOR EACH
MEASUREMENT POINT, IF NECESSARY, ATTACH DRAWING(S)

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

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)
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OPTIONAL INFORMATION
34.

OPTIONAL INFORMATION
(that the operator considers relevant to
safeguarding the facility)

Signature of Responsible Officer:

Date:

N-77 (MM-YYYY)

CONFIDENTIAL

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