ML19213A036

Enclosure 2: Certificate from Competent Authority (Letter to R. Boyle Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035))

ML19213A036
Person / Time
Site:	07103035
Issue date:	08/01/2019
From:	John Mckirgan Spent Fuel Licensing Branch
To:	Boyle R US Dept of Transportation (DOT)
Garcia-Santos N
Shared Package
ML19213A035	List: ML19213A036 ML19213A037
References
EPID L-2018-LLA-0219
Download: ML19213A036 (8)

Text

Japanese Certificate of Approval No. J/61/B(U)-96 Revision 3 Model No. JCR-80Y-20T

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, ,, ..--~w*-*--.......---~-.. -**w IDENTIFICATION MARK J/61/B(U)F-96(Rev.3)

COMPETENT AUTHORITY OF JAPAN CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF

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RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1-9-9, ROPPONGI MINATO-KU TOKYO, JAPAN

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I Reference of J/61/B(U)F-96 (Rev.3)

Page 1 of 6 Pages

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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 spent fuel elements, specified in the 2012 Edition of the Regulations for the Safe Transport of Radioactive Materials (International Atomic Energy Agency, Safety Standards Series No.SSR-6) and the Japanese rules .based on the Act on the 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/61/B(U)F-96(Rev.3)

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• Date KazuyaAoki Director, Division of Licensing for Nuclear Fuel Facilities Secretariat ofNuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval

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.! Reference of J/61/B(U)F-96(Rev.3)

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1. The Competent Authority Identification Mark  : J/61/B(U)F-96(Rev. 3)

2. Name of Package  : Type JRC-80Y-20T

3. Type of Package  : Type B(U) package for fissile material

4. Specification of Package

• (1) Materii)l of Packaging

( i )Body&Lid  : Stainless steel

( ii)Basket  : Stainless steel, Boron Carbide

( iii) Fin(Heat dissipation and shock .absorbing)  : Stainiess steel (2) Total Weight of Packaging  : Approximately 22.8x 103kg (3) Outer Dimensions of Packaging

( i ) Outer Diameter  : Approximately 1.9 m (ii)Height  : Approximately 2.1 ID (4) Total Weight of Package  : Approximately 23.2 x 103 kg or less (5) illustration of Package  : See the attached Figure-I (Bird's-eye view)

5. Specification ofRadioactive Contents  : See the attached Table- I

6. Description of Containment System 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.

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

(3) Assumptions of Leakage of Water into Package The subcriticality calculation is evaluated upon the assumption that internal void spaces of the package are filled with water, not only during routine transport but also under both normal and accident conditions.

(4) Special Features in Criticality Assessment Any special features are not considered in the criticality assessment

/ Reference of J/61/B(U)F-96(Rev.3)

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-~_(/J rrnJ Type B(M) Packages, a statement regarding prescriptions ofType B(U) Package that do not apply to this Package Not applicable. (This package is Type B(U).)

• 9. Assumed Ambient Conditions

( i ) Ambient Temperature Range  : -40°C-38°C

( ii) Insolation Data  : Table 12 ofIAEA Regulation

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

( i ) Package should be handled carefully in accordance with the schedule and procedures established properly taking all possible safety measures.

( 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 i~ 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 ) Leakage Rate Measurement Inspection (ii i ) 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 ) Dose Rate Measurement Inspection ( vi ) Subcriticality Inspection (vii) Contents Inspection (viii) Surface Temperature Measurement Inspection (ix) Leakage Rate Measurement Inspection ( x ) Package Internal Pressure Measurement Inspection (4) Precautions for Loading of Package for Shipment

. 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.

11. Issue Date and Expiry Date

( i ) Issue Date  : May.29, 2017

( ii) Expiry Date  : May.28, 2022 .

Reference of J/61/B(U)F-96(Rev.3)

Page 4 of 6Pages Protection cover for lid lifting lug Vent valve and Protection cover Lid lifting lug Lock, Security seal Lid bolt, L~ck, Security seal and Antirotation key Leak test hole Double O*ring Fin Centering pin Drain hole Package lifting lug Body(Shielding)

Tie down bolt Tie down device Drain valve and Protection cover with fin Lock, Security seal Lifting device (All dimensions in inm)

Figure-I illustration of JRC-80Y-20T Package i

Table-I Specification of Radioactive Contents ( 1/2)

Basket Box type Box type(with Adapters) MNUtype Classifi Reactor JRR-3 JRR-3 JRR-4 . JRR-4 JRR-3 JRR-3 JRR-3

-cation Fuel High enrichment Standard aluminide Standard silicide Low enrichment Follower aluminide Follower silicide

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element Instrumented type MNUtype type type silicide type type type Item '------- (HEU)

Fuel type* Plate fuel Plate fuel Plate fuel Plate fuel Plate fuel Plate fuel Rod fuel Number of fuel elements 40 or less 40 orless 40 or less 40 or less 40 or less 40 or less 160 orless (piece)

Initial enrichment

(%)1) 20 or less 20 or less 20 or less 93 or less 20 or less 20 or less 0.72 235 Total mass of U (g/piece) 11 306 or less 485 or less 210 or less 168 or less 194 or less 310orless 61.2 or less Total mass ofU 1,530 or less 2,481 or less 1,075 or less 186 or less 970 or less 1,586 or less 8,500 or less (g/piece) 1>

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Bumup 50 or less 60 or less 50 or less 15 or less 50 or less 60 or less 23 or less

(%) 2 Cooling time 300 or more 3> 600 or more 110 or more 10,000 or more 300 or more 31 600 or more 2, 190 or more (day)

Total activity 2.04x I 0 16 or less 4l 2.09xJ0 16 or less 2.02x I 0 16 or less 1.98x 10 14 or less 9.53xJO" or less 41 1.33xJ0 16 or less 9.33xJ0 14 or less (Bq/package)

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Decay heat 2.25 x 103 or less 4> 2.24x I 0 3 or less 2. J5x10 3 or less 1.69xJ0 1 orless J.03xJ03 orless 41 l.43x!0 3 or less 7.24xJ0 1 or less (W/package)

Uranium silicon Uranium silicon Uranium silicon ~

Uranium aluminum Uranium aluminum Uranium aluminum Metallic natural Fuel meat aluminum aluminum aluminum (1) dispersion type alloy alloy dispersion type alloy uranium dispersion type alloy dispersion type alloy dispersion type alloy ct'

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Fuel (1) material Clad Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy  :::s C')

(1)

Side plate, -- '"d 0 Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy >-+,

etc.  !>>

OQ Dimension at contained q,37x933 (1) ~

O'I widthxheightxlength 77.04X77.04X800 77.04x77.04x800 80x80x660 80x80x840 63.6x63.6x880 63.6X63.6x880 and Vo ......

(mm) <p37X944 0

>-+, b3 Weight at conlained (kg/piece) 8.0 or less 8.0 or less 5.6 orless 6.0 or less 5.2 or less 5.2 or less 10 or less O'I

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!>> I OQ \0 Note. The fuel elements of JRR-3 and JRR-4 can be contained together (except MNU type fuel elements). (1)

. O'I I) The value in the nuclear specification shows an upper value which contains fabrication tolerance. "' ~

2) Burn up(%) = ((All depletion weight of 235U) + (Initial weight of 235U))x!OO * (1)

3) One operation cycle of JRR-3 with JRR-3 aluminide fuels (standard type and follower type) is 35 days (27 days for reactor operation and 8 days for shutdown). Refueling work is carried out once in an <

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operation cycle, and 4 standard type fuels and 2 follower type fuels are refueled in an operation cycle. Therefore, cooling time of fuels contained in the package are at a minimum of 300 days, and .._,

added 35 days in turn for every 4 standard type fuels and 2 follower type fuels. (Standard type fuel: 300 days or more (4 fuels), 335 days or more (4 fuels), ... , 615 days or more (4 fuels). Follower type fuel: 300 days or more (2 fuels), 335 days or more (2 fuels), ... , 965 days or more (2 fuels).)

4) The values in total activity and decay heat are based on the cooling time (day) in 3).

Table-I Specification of Radioactive Contents (2/2) 1~~\'

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Classifi Basket Box type Box type(with Adapters) MNUtype ri _,...._.;;,.:...,.)

-cation "I"'"""'"*~-***--**----

Reactor JRR-3 JRR-3 JRR-4 JRR-4 JRR-3

• JRR-3 JRR-3 Fuel Standard aluminide High enrichment Standard silicide Low enrichment Follower aluminide Follower silicide Instrumented type MNUtype Item type type silicide type type type

• (HEU)

Activity Activity Activity Activity Activity Activity Activity Nuclide (Bq)

Nuclide (Bq) Nuclide (Bq) Nuclide j Nuclide Nuclide Nuclide (Bq) (Bq) (Bq) (Bq)

Ce-144 6.12x!0 15 Ce-144 6.0Ix!0 15 Nb-95 3.54x!0 15 Cs-137 I 5.02xI013 Ce-144 2.77x.I0 15 Ce-144 3.84x!0 15

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Cs-137

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I 1.79xl0 14 Quantities of major Pm-147 1.39x101s Pm-147 1.84xJ0 15 Ce-144 2.38x 10 15 Sr-90 J 4.8Ix!0 13 Pm-I47 , 7.8Ix!014 Pm-147 l.l 7x!Ols Pm-147 1.57xl0 14 radionuclides

( per package ) Nb-95 l.36XJ015 Cs-137 I 1.10x101s Zr-95 2.3JxJ015 Y-90 I

j 4.8JxJ0 13 Nb-95 I 4.40xJQl4 Cs-137 j 6.98xJ0 14 Sr-90 1.53x!014 Zr-95 6.4IxJ014 Sr-90 l.06xJ0 15 Y-91 2.03x!0 15 Kr-85 I 2.46x!0 12 Cs-137 J 3.85x10 14 Sr-90 , 6.76x10 14 Y-90 Ii l.53x!0 14 Cs-137 6.J4xJOl4 Y-90 J.Q6xJOIS Sr-89 l.5JxJ0 15 Pm-14712.5!x10 11 Sr-90 I I

3.76xJ014 Y-90 j I

6.76xJ0 14 Ce-144 I 2.24x"J0 13