ML22333A791

Japanese Certificate J-2026-AF-96

ML22333A791
Person / Time
Site:	07103100
Issue date:	02/07/2022
From:	Mitsubishi Nuclear Fuel Co, Ltd
To:	Office of Nuclear Material Safety and Safeguards
References
J/2026/AF-96
Download: ML22333A791 (1)

Text

IDENTIFICATION MARK J/2026/AF-96 COMPETENT AUTHORITY OF JAPAN CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1-9-9, ROPPONGI MINATO-KU TOKYO, JAPAN

CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS This is to certify, in response to the application by Mitsubishi Nuclear Fuel Co., LTD., that the package design described herein complies with the design requirements for a package containing Fresh Fuel Assembly for BWR, specified in the 2012 Edition of the Regulations for the Safe Transport of Radioactive Material (International Atomic Energy Agency, Safety Standards Series No.SSR-6) and the Japanese rules based on the Act on Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors.

This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be transported.

COMPETENT AUTHORITY IDENTIFICATION MARK: J/2026/AF-96 Date Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval

1.

The Competent Authority Identification Mark J/2026/ AF-96

2.

Name of Package : MX-6

3.

Type of Package : Type A Package containing Fissile Material

4.

Specification of Package (1) Materials of Packaging (i)

Body Stainless steel, Copper, Alloy steel, Resin (ii)

Lid parts Titanium alloy, Alloy steel, Resin (iii) Basket Aluminum alloy, Borated stainless steel Reference of J/2026/AF-96 Page 1 of 4 Pages (iv) Shock absorbing cover

Wood, Stainless steel, Alloy steel (2) Total Weight of Packaging : 15.35 tons or less (3) Outer Dimensions of Packaging (i)

Outer diameter (ii)

Length Approximately 2.1 m Approximately 6.0 m (including top and rear shock absorbing covers)

(4) Total Weight of Package : 19.5 tons or less (5) Illustration of Package : See the attached Figure

5.

Specification of Radioactive Contents : See the attached Table-I

6.

Description of Containment System The containment system of the package consists of the body and the lid. EPDM O-rings, referred to as the lid gaskets and the quick connection cover gaskets, shall be installed on the contact surface of the lid against the body and on the contact surface of the quick connection cover against the lid.

7.

For Package containing Fissile Materials, (1) Restrictions on Package (i)

Restriction Number "N" : No restriction (ii)

Array of Package: No restriction (iii) Criticality Safety Index (CSI) : 0 (2) Description of Confinement System The confinement system of the package consists of the fuel rods, the fuel assemblies, the basket and the inner shell of the body.

(3) Assumptions of Leakage of Water into Package In the criticality safety analysis for the package, water is assumed to leak into the void spaces of the packages.

(4) Special Features in Criticality Assessment Not applicable Reference of J/2026/AF-96 Page 2 of 4 Pages

8.

For Type B(M) Packages, a statement regarding prescriptions of Type B(U) Package that do not apply to this Package Not applicable

9.

Assumed Ambient Conditions (i)

Ambient Temperature Range : -40°C---.,,38°C (ii) Insolation Data : Table 12 ofIAEA Regulation

10. Handling, Inspection and Maintenance Packages must be handled, inspected and maintained in the manner described in the safety analysis report for the package.

11. Issue Date and Expiry Date (i) Issue Date

March 20, 2019 (ii) Expiry Date

March 19, 2024

External plate Shell part resin Stiffener Inner shell Top shock absorbing cover 1,(

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Top handlin,i; belt Top trunnion Figure MX-6 Packaging Rear shock absorbing cover

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Reference of Jl2026IAF-96 Page 4 of 4 Pages Table-1 Specifications of Radioactive Content ly 9x9 lte Description Fresh Fuel Assembly for BWR1)

Physical State Solid (UO2 Pellet or Gadolinia - UO2 Pellet)

Number of Assemblies 10 or less Weight of Content (kg) 4150 or less Total Activity (GBq) 3.10 x 102 or less (Total Major Nuclides: 2.59 x 102 or less)

'ti 232u 1.43 X 10-I (1)....

'ti 234u 2.29 X 102

~

<fcl Activity 23su 7.21 X 10° s*

Major Nuclides 2) (GBq)

()'Ci 236u 1.08 X 10° 23su 2.13x101 99Tc 1.13 X 10-2 Heat Generation Rate NIA (Fresh Fuel Assembly)

Enrichment (wt%)

5.0 or less Fuel Assembly (kg) 310 or less

'ti (Including Channel Box)

(1)....

Weight

'Tl Uranium Oxide (kg) 210 or less i:: 2. >

Uranium (kg) 180 or less Ul Ul (1) s Bum up Rate NIA (Fresh Fuel Assembly) cr' Cooling Time NIA (Fresh.Fuel Assembly) 232u

~ 0.0001 µg/gU 234u

~ 1.1ox104 µg/g235u Impurity Specification of Enriched Uranium 236u

~250 µg/gU 99Tc

~0.01 µg/gU In case of236U < 125µg/gU, 232U and 99Tc are not applicable.

Note 1) Fresh fuel assemblies stored in spent fuel pool Note 2) For enrichment of 5.0 wt%