ML21319A052
| ML21319A052 | |
| Person / Time | |
|---|---|
| Site: | 07103100 |
| Issue date: | 05/06/2021 |
| From: | Orano TN Americas |
| To: | Office of Nuclear Material Safety and Safeguards, Radioactive Material Transportation and Storage Consulting, US Dept of Transportation (DOT) |
| B WHITE NRC/NMSS/DFM/STLB 3014156577 | |
| Shared Package | |
| ML21319A049 | List: |
| References | |
| E-59637 | |
| Download: ML21319A052 (6) | |
Text
IDENTIFICATION MARK J/2037/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 fuel assemblies for pressurized water reactor (hereafter called "PWR"), 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 {rom compliance with any requirement of the government of any country through or into which the package will be transported.
COMPETENT AUTHORITY IDENTIFICATION MARK: J/2037/AF-96
Mav_ 6s UJr/ I
- I Date
Director, Division of Licensing for Nuclear Fuel Facilities
Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval Reference of J/2037 / AF-96 Page 1 of 4 Pages
- 1. The Competent Authority Identification Mark: J/2037/AF-96
- 2. Name of Package : MX-6P
- 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, Stainless steel (iv) Shock absorbing cover : Wood, Stainless steel, Alloy steel (2) Total Weight of Packaging : 14.7 tons or less (3) Outer Dimensions of Packaging (i) Outer diameter : Approximately 2.1 m (ii) Length : Approximately 6.0 m (including tqp 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, the lid, the quick connection cover and the gaskets for the lid and the quick connection cover.
- 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 which are arrayed infinitely.
( 4) Special Features in Criticality As~essment Not applicable Reference ofJ/203 7 / 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 (1) Issue Date : March 11, 2021 (2) Expiry Date : March 10, 2026
Reference of Jl203 71 AF-96 Page 4 of 4 Pages
Table~l Specifications ofRadioactive Content
ly 14 X 14 14 X 14 Ite (10 Feet) (12 Feet)
Description Fresh Fuel Assembly for PWR 1l
Physical State Solid (UO2 Pellet or Gadolinia - UO2Pellet)
Weight of Content (kg) 4800 or less
Number of Assemblies 8 or less
Weight of Fuel Assemblies (kg) 3920 or less 4720 or less 5.85 x 102 or less 7.05 x 102 orless Total Activity (GBq) (Total Major Nuclides: (Total Major Nuclides:
'1:1 4.89 x 102 or less) 5.90 x 102 or less)
~ 232u 2.70 X 10-l 3.25 X lQ-l
'1:1 p,
i s* 234U 4.33 X 102 5.22 X 102
(JQ Activity Major Nuclides 2l 23su 1.36 X 10 1 1.64 X 10 1 (GBq) 236U 2.04 X 10° 2.46 X 10°
23su 4.02 X 10 1 4.85 X 10 1
99Tc 2.14 X 10-2 2.58 X 10-2
Heat Generation Rate NI A (Fresh Fuel Assembly)
Enrichment (wt%) 5.0 or less
'1:1 Fuel Assembly (kg) 490 or less 590 or less
~ Weight Uranium Oxide (kg) 390 or less 470 or less
[
> Uranium (kg) 340 or less 410 or less CD
- g. Burn up Rate NIA (Fresh Fuel Assembly)
'< Cooling Time NIA (Fresh Fuel Assembly)
I 232u :S 0.0001 µglgU
\\ (Not applicable in case of 236U < 125µglgU)
Impurity Specification of Enriched 234U :::; 1.10 X 104 µglg235U Uranium 236U :S250 µglgU
99Tc :SO.QI µglgU (Not applicable in case of 236U < 125µglgU)
Note 1) Fresh fuel assemblies stored in spent fuel pool are included.
Note 2) For enrichment of 5.0 wt%.