ML23115A077

Enclosure 1 - Japanese Certificate of Competent Authority Model No. JRC-80Y-20T (English)

ML23115A077
Person / Time
Site:	07103035
Issue date:	10/19/2022
From:	Boyle R, Neely R Edlow International Co, US Dept of Transportation (DOT), Office of Hazardous Materials Safety
To:	Division of Fuel Management
Shared Package
ML23115A059	List: ML23115A074 ML23115A075 ML23115A076 ML23115A077 ML23115A078 ML23115A081 ML23115A082 ML23115A084 ML23115A086
References
001794, EPID L-2023-DOT-0006
Download: ML23115A077 (9)

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IDENTIFICATION MARK J/2045/B(U)F 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 Japan Atomic Energy Agency, that the package design described herein complies with the design requirements for a package containing Standard silicide type Spent fuel, Follower silicide type Spent Fuel and MNU type Spent Fuel, specified in the 2018 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/2045/B(U)F

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Date

/

Hasegawa Kiyfo* su Dixector, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval

Reference of J/2045/B(U)F

. Page 1 of 5 Pages

1. The Competent Authority Identification Mark : J/2045/B(U)F

2. Name of Package

3. Type of Package

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

Body and Lid (ii) Basket

JRC-80Y-20T

Type B(U) package for fissile material

Stainless steel

Stainless steel, Boron Carbide (iii) Fin(Heat dissipation and shock absorbing)

Stainless steel (2) Total Weight of Packaging

22.8 x 103 kg or less (3) Outer Dimensions of Packaging (i) Outer Diameter (ii) Height (4) Total Weight of Package (5) Illustration of Package

5. Specification of Radioactive Contents

. Description of Containment System

Approximately 1.9 m

Approximately 2.1 m

23.2 x 103 kg or less

See the attached Figure-l(Bird's-eye view)

See the attached Table-1 Containment system consists of body, lid, vent valve, and drain valve made of stainless steel.

Silicone rubber is used for contact surface of the lid, the valves, and valve seat.

. For Package containing Fissile Materials,

( 1) Restrictions on Package (i) Restriction Number N" (ii) Array of Package (iii) Criticality Safety Index (CSI)

(2) Description of Confinement System

No restriction

No restriction

0 Confinement system consists of the basket which maintains the fuel elements contained in the package.

(3) Assumptions of Leakage of Water into Package It is assumed in criticality analysis that water will leak into void space of inner shell.

(4) Special Features in Criticality Assessment Not applicable

Reference of J/2045/B(U)F Page 2 of 5 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 (This package is Type B(U))

. Assumed Ambient Conditions (i) Ambient Temperature Range (ii) Insolation Data

10. Handling, Inspection and Maintenance (1) Handling Instructions

-40°C~38°C

Table 12 of IAEA Regulation (i)

Package should be handled carefully in accordance with the schedule and procedures established properly taking all possible safety measur~s.

(ii)

Package should be handled using appropriate lifting devices and the crane.

(iii) When packaging is stored outdoors, it should be covered with an appropriate waterproof sheet, avoiding the situation where it is placed directly on the ground.

(2) Inspections and Maintenance of Packaging The following inspections should be performed not less than once a year ( once for every ten times in a case where the packaging is used not less than ten times a year) and defect of packaging should be repaired, if any, in order to maintain the integrity of packaging.

(i)

Visual Inspection (ii) Leak Inspection (iii) Lifting Inspection (iv) Subcriticality Inspection (v) Heat Transfer Inspection (vi) Shielding Inspection (3) Actions prior to Shipment The following inspections should be performed prior to shipment.

(i)

Visual Inspection (ii)

Lifting Inspection (iii)

Weight Measurement Inspection (iv)

Surface Contamination Measurement Inspection (v)

Radiation Dose Rate Measurement Inspection (vi)

Subcriticality Inspection (vii) Contents Inspection (viii) Surface Temperature Measurement Inspection (ix)

Leak Inspection (x)

Package Internal Pressure Measurement Inspection

( 4) Precautions for Loading of Package for Shipment Reference of J/2045/B(U)F Page 3 of 5 Pages Package should be securely loaded to the conveyance at the designated tie-down portion of the packaging so as not to move, roll down or fall down from the loading position during transport.

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

Sep 21, 2022 (ii) Expiry Date

Sep 20, 2092 However, if this certificate no longer meets the technical standards (limited to those related to the design of package) due to a revision of the regulations*1*2, this certificate will be expired.

• 1 The NRA Ordinance on Off-Site Transportation of Nuclear Fuel Materials, etc.

(Ministerial ordinance issued by the Prime Minister's Office No. 57 of 1978)

• 2 The Notification on Technical Details for Off-Site Transportation of Nuclear Fuel Materials, etc.(Notice issued by Science and Technology Agency No. 5 of 1990)

Protection cover for lid lifting lug Lid lifting lug Lid bolt, Lock, Security seal and Antirotation key Double O*ring Fin Drain hole Body(Shielding)

Tie down bolt Tie down device Figure-I Reference of J/2045/B(U)F Page 4 of 5 Pages Vent valve and Protection cover Lock, Security seal Lifting device Centering pin Package lifting lug 0

N N

N Drain valve and Protection cover with fin Lock, Security seal

( All dimensions in mm)

Illustration of JRC-80Y-20T Package

Table-1 Specification of Radioactive Contents Fuel Element Standard silicide type Follower silicide type MNUtype Spent fuel Spent Fuel Spent Fuel Number of fuel elements(piece) 40 or less 40 or less 160 or less Initial enrichment(%) Il 20 or less 20 or less 0.72 Physical State Solid Uranium silicon aluminum Uranium silicon aluminum Material of nuclear fuel Metallic natural uranium dispersion type alloy dispersion type alloy U weight(kg/package) 1 >

99.24 or less 63.44 or less 1,360 or less Total mass of 235U(g/piece) IJ 485 or less 310 or less 61.2 or less Total mass ofU(g/piece) t) 2,481 or less 1,586 or less 8,500 or less Burnup(3/4) 2>

60 or less 60 or less 23 or less Cooling time(day) 600 or more 600 or more 2,190 or more Decay heat(W /package) 2.24x 103 or less l.43xI03 or less 7.24x I 01 or less Total activity 2.09x I 016 or less 1.33 x l 016 or less 9.33xl014 orless (Bq/package)

Ce-144 6.0ixI0 15 Ce-144 3.84xl015 Cs-137 1.79xI014 Activity of Quantities of major Pm-147 1.84xI015 Pm-147 I.17x!015 Pm-147 1.57xI0'4 Contents radionuclides Cs-137 1.1ox10ts Cs-137 6.98xlQ14 Sr - 9 0 l.53x 1014 l::tl (D

(Bq/package)

Sr-9 0 l.06x1015 Sr-9 0 6.76x 1014 Y -90 l.53xI014 tti"'

1--j Y -90 l.06x 1015 Y -9 0 6.76xl014 Ce-144 2.24x1013 (D

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Note. The fuel elements of Standard silicide type and Follower silicide type can be contained together ( except MNU type fuel elements).

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The absorbed dose rate to air at a position 1 m away from the surface of the package is 1 Gy/h or more.

1) The value in the nuclear specification shows an upper value which contains fabrication tolerance.

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2) Burn up(%) = ((All depletion weight of 235U)-;- (Initial weight of 235U))x 100 CJ1 CJ1 l-1j t:r.::I

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