Form N-72 Research and Power Reactors

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

IAEA N-72

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

CONFIDENTIAL
WHEN COMPLETED

DATE:
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, Privacy, and
Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, or by internet e-mail to [email protected], and to the Desk Officer,
Office of Information and Regulatory Affairs, NEOB-10202, (3150-0056), Office of Management
and Budget, Washington, DC 20503. If a means used to impose an 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.

RESEARCH AND POWER REACTORS
GENERAL REACTOR DATA
13. FACILITY DESCRIPTION

GENERAL FLOW DIAGRAM(S) ATTACHED UNDER REF. NOS.

14. RATED THERMAL OUTPUT,
ELECTRICITY OUTPUT
(for power reactors)

15. NUMBER OF UNITS (REACTORS) AND
THEIR LAYOUT IN THE NUCLEAR POWER
PLANT

16. REACTOR TYPE

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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

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)

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26. REACTOR ASSEMBLIES*
(indicate for each type)

DATE:

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

-- 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

27. DESCRIPTION OF FRESH FUEL ELEMENTS
(indicate for each type)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

-- physical and chemical form of fuel;
-- nuclear material and fissionalbe 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)

* Assembly is the combination of elements or handling units such as cluster o r bundle.
** Element is the smallest contained fuel unit.
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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.)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

30. OTHER TYPES OF UNITS

31. MEANS OF NUCLEAR MATERIAL/FUEL
IDENTIFICATION

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NUCLEAR MATERIAL DESCRIPTION
32. OTHER NUCLEAR MATERIAL IN
THE FACILITY
(each separately identified)

NUCLEAR MATERIAL FLOW
33. SCHEMATIC FLOW SHEET FOR
NUCLEAR MATERIAL
(identifying measurement points,
accountability areas, inventory locations,
etc.)

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DIAGRAM(S) ATTACHED UNDER REFERENCE NUMBERS:

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NUCLEAR MATERIAL FLOW
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

35. LOAD FACTOR
(power reactor only)

36. REACTOR CORE LOADING
(number of elements/assemblies)

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NUCLEAR MATERIAL FLOW
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)

ii)

Layout, General Arrangements, and
Storage Plan

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DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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NUCLEAR MATERIAL HANDLING
40. FRESH FUEL (Continued)
iii)

Capacity of Store

(iv)

Fuel Preparation and Assay Room, and
Reactor Loading Area
(description and indication of layout
and general arrangement)

41. FUEL TRANSFER EQUIPMENT
(including refueling machines)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

42. ROUTES FOLLOWED BY
NUCLEAR MATERIAL
(fresh fuel, irradiated fuel, blanket,
other material)

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DATE:

NUCLEAR MATERIAL HANDLING
43. REACTOR VESSEL
(showing core location, access to vessel,
vessel openings, fuel handling in vessel)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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:
Thermal:

Fast:

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NUCLEAR MATERIAL HANDLING
47. INSTRUMENTATION FOR MEASURING
NEUTRON AND GAMMA FLUX

48. IRRADIATED FUEL
i)

Layout, Spent Fuel Storage Plan, and
General Arrangements
(internal and external)

ii)

Method of Storage

iii)

Design Capacity of Storage

iv)

Minimum and Normal Cooling Period
Prior to Shipment

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DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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NUCLEAR MATERIAL HANDLING
48. IRRADIATED FUEL (Continued)
v)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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 metre)

50. METHODS AND EQUIPMENT FOR
HANDLING IRRADIATED FUEL
(except for that already given under
Qs. 41, 48.v)

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NUCLEAR MATERIAL HANDLING
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

v)

Layout and General Arrangement

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DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

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COOLANT DATA
52. FLOW DIAGRAM
(indicating mass flow, temperature and
pressure at major points, etc.)

DRAWING(S) ATTACHED UNDER REFERENCE NUMBERS:

PROTECTION AND SAFETY MEASURES
53. BASIC MEASURES FOR PHYSICAL
PROTECTION OF NUCLEAR MATERIAL

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PROTECTION AND SAFETY MEASURES
54. SPECIFIC HEALTH AND SAFETY RULES
FOR INSPECTOR COMPLIANCE
(if extensive, attach separately)

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NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
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 adjustments after
inventory, and correction of mistakes, etc.,
using the following headings:
i)

SPECIMEN FORMS USED IN ALL PROCEDURES ATTACHED UNDER
REFERENCE NUMBERS:

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.)

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NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
55. SYSTEM DESCRIPTION (Continued)
ii)

Receipts

iii)

Shipments

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NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
55. SYSTEM DESCRIPTION (Continued)
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 limits)

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LIST OF MAJOR ITEMS OF EQUIPMENT REGARDED AS NUCLEAR
MATERIAL CONTAINERS ATTACHED UNDER REFERENCE NUMBERS:

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NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
55. SYSTEM DESCRIPTION (Continued)
vi)

Operational Records and Accounts
(including method of adjustment or
correction and place or preservation
and language)

56. FEATURES RELATED TO CONTAINMENT
AND SURVEILLANCE MEASURES
(general description)

N-72 (01-2013)

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DATE:

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
57. FOR EACH MEASUREMENT POINT OF
ACCOUNTABILITY AREAS, IDENTIFIED
IN PARTICULAR UNDER QS. 13, 33, 34,
GIVE THE FOLLOWING (IF APPLICABLE)*
i)

Description of Location, Type,
Identification

ii)

Anticipated Types of Inventory Change
and Possibilities to Use This
Measurement
Point for Physical Inventory Taking

iii)

Physical and Chemical Form of
Nuclear Material
(with cladding materials description)

IF NECESSARY, ATTACH DRAWING(S)

* For each measurement point, fill in separate sheet.
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DATE:

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
57. FOR EACH MEASUREMENT POINT OF
ACCOUNTABILITY AREAS, IDENTIFIED
IN PARTICULAR UNDER QS. 13, 33, 34,
GIVE THE FOLLOWING (IF APPLICABLE)*
(Continued)
iv)

Nuclear Material Containers, Packaging

v)

Sampling Procedures and
Equipment Use

vi)

Measurement Method(s) and
Equipment Use
(item counting, neutron flux,
power level, nuclear burn-up
and production, etc.)

* For each measurement point, fill in separate sheet.
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DATE:

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
57. FOR EACH MEASUREMENT POINT OF
ACCOUNTABILITY AREAS, IDENTIFIED
IN PARTICULAR UNDER QS. 13, 33, 34,
GIVE THE FOLLOWING (IF APPLICABLE)*
(Continued)
vii)

IF NECESSARY, ATTACH DRAWING(S)

Source and Level of Accuracy

viii) Technique and Frequency of
Calibration of Equipment Used

ix)

Programme for the Counting Appraisal
of the Accuracy of Methods and
Techniques Used

* For each measurement point, fill in separate sheet.
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DATE:

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
57. FOR EACH MEASUREMENT POINT OF
ACCOUNTABILITY AREAS, IDENTIFIED
IN PARTICULAR UNDER QS. 13, 33, 34,
GIVE THE FOLLOWING (IF APPLICABLE)*
(Continued)
x)

Methods of Converting Source Data
to Batch Data
(standard calculative procedures,
constants used, empirical
relationships, etc.)

xi)

Anticipated Batch Flow Per Year

xii)

Anticipated Number of Items Per Flow
and Inventory Batches

IF NECESSARY, ATTACH DRAWING(S)

* For each measurement point, fill in separate sheet.
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DATE:

NUCLEAR MATERIAL ACCOUNTANCY AND CONTROL
57. FOR EACH MEASUREMENT POINT OF
ACCOUNTABILITY AREAS, IDENTIFIED
IN PARTICULAR UNDER QS. 13, 33, 34,
GIVE THE FOLLOWING (IF APPLICABLE)*
(Continued)

IF NECESSARY, ATTACH DRAWING(S)

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 ContainmentSurveillance Measures

* For each measurement point, fill in separate sheet.
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OPTIONAL INFORMATION
58. OPTIONAL INFORMATION
(that the operator considers relevant
to safeguarding the facility)

Signature of Responsible Officer:

Date:

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