ML19213A036
| 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: |
| 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 RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1-9-9, ROPPONGI MINATO-KU TOKYO, JAPAN
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Reference of J/61/B(U)F-96 (Rev.3)
Page 1 of 6 Pages 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)
OL!.t, tD, 2.o r 7
- 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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- 1. The Competent Authority Identification Mark
- 2. Name of Package
- 3. Type of Package
- 4. Specification of Package
- (1) Materii)l of Packaging
( i )Body&Lid
( ii)Basket
( iii) Fin(Heat dissipation and shock.absorbing)
(2) Total Weight of Packaging (3) Outer Dimensions of Packaging
( i ) Outer Diameter (ii)Height (4) Total Weight of Package (5) illustration of Package
- 5. Specification ofRadioactive Contents
- 6. Description of Containment System Reference of J/61/B(U)F-96(Rev.3)
Page 2 of 6 Pages
- J/61/B(U)F-96(Rev. 3)
- Type JRC-80Y-20T
- Type B(U) package for fissile material
- Stainless steel
- Stainless steel, Boron Carbide
- Stainiess steel
- Approximately 22.8x 103kg
- Approximately 1.9 m
- Approximately 2.1 ID
- Approximately 23.2 x 103 kg or less
- See the attached Figure-I (Bird's-eye view)
- See the attached Table-I 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
( 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 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
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Reference of J/61/B(U)F-96(Rev.3)
Page 3 of 6 Pages
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-~_(/J rrnJ 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).)
- 9. Assumed Ambient Conditions
( i ) Ambient Temperature Range
( ii) Insolation Data
- 10. Handling, Inspection and Maintenance (1) Handling Instructions
- -40°C-38°C
- Table 12 ofIAEA Regulation
( 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 i ) Lifting Inspection
( v ) Heat Transfer Inspection (3) Actions prior to Shipment
( ii ) Leakage Rate Measurement Inspection (iv) Subcriticality Inspection (vi) Shielding Inspection The following inspections should be performed prior to shipment
( i ) Visual Inspection
( ii ) Lifting Inspection (iii) Weight Measurement Inspection
( v ) Dose Rate Measurement Inspection (vii) Contents Inspection (ix) Leakage Rate Measurement Inspection (4) Precautions for Loading of Package for Shipment (iv) Surface Contamination Measurement Inspection
( vi ) Subcriticality Inspection (viii) Surface Temperature Measurement Inspection
( x ) Package Internal Pressure Measurement Inspection
. 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
( ii) Expiry Date
- May.29, 2017
- May.28, 2022.
Protection cover for lid lifting lug Lid lifting lug Lid bolt, L~ck, Security seal and Antirotation key Double O*ring Fin Drain hole Body(Shielding)
Tie down bolt Tie down device Figure-I Reference of J/61/B(U)F-96(Rev.3)
Page 4 of 6Pages Vent valve and Protection cover Lock, Security seal Lifting device Leak test hole Centering pin Package lifting lug Drain valve and Protection cover with fin Lock, Security seal (All dimensions in inm) illustration of JRC-80Y-20T Package i
Table-I Specification of Radioactive Contents ( 1/2)
Basket Box type Classifi Reactor JRR-3 JRR-3 JRR-4
-cation Fuel Standard aluminide Standard silicide Low enrichment element type type silicide type Item Fuel type*
Plate fuel Plate fuel Plate fuel Number of fuel elements 40 or less 40 orless 40 or less (piece)
Initial enrichment 20 or less 20 or less 20 or less
(%)1)
Total mass of 235U 306 or less 485 or less 210 or less (g/piece) 11 Total mass ofU 1,530 or less 2,481 or less 1,075 or less (g/piece) 1>
Bumup
(%) 2 50 or less 60 or less 50 or less Cooling time 300 or more 3>
600 or more 110 or more (day)
Total activity (Bq/package) 2.04x I 016 or less 4l 2.09xJ0 16 or less 2.02x I 016 or less Decay heat 2.25 x 1 03 or less 4>
2.24x I 03 or less
- 2. J5x103 or less (W /package)
Uranium aluminum Uranium silicon Uranium silicon Fuel meat dispersion type alloy aluminum aluminum dispersion type alloy dispersion type alloy Fuel material Clad Aluminum alloy Aluminum alloy Aluminum alloy Side plate, Aluminum alloy Aluminum alloy Aluminum alloy etc.
Dimension at contained widthxheightxlength 77.04X77.04X800 77.04x77.04x800 80x80x660 (mm)
Weight at conlained 8.0 or less 8.0 or less 5.6 orless (kg/piece)
Note. The fuel elements of JRR-3 and JRR-4 can be contained together (except MNU type fuel elements).
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 Box type(with Adapters)
. JRR-4 JRR-3 JRR-3 High enrichment Follower aluminide Follower silicide Instrumented type type type (HEU)
Plate fuel Plate fuel Plate fuel 40 or less 40 or less 40 or less 93 or less 20 or less 20 or less 168 or less 194 or less 310orless 186 or less 970 or less 1,586 or less 15 or less 50 or less 60 or less 10,000 or more 300 or more 31 600 or more 1.98x 1014 or less 9.53xJO" or less 41 1.33xJ016 or less 1.69xJ01 orless J.03xJ03 orless 41 l.43x!03 or less Uranium aluminum Uranium aluminum Uranium silicon alloy dispersion type alloy aluminum dispersion type alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy Aluminum alloy 80x80x840 63.6x63.6x880 63.6X63.6x880 6.0 or less 5.2 or less 5.2 or less MNUtype JRR-3 MNUtype Rod fuel 160 orless 0.72 61.2 or less 8,500 or less 23 or less 2, 190 or more 9.33xJ0 14 or less 7.24xJ01 or less Metallic natural uranium Aluminum alloy q,37x933 and
<p37X944 10 or less
- 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 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).
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Table-I Specification of Radioactive Contents (2/2)
Classifi
-cation Basket Box type Box type(with Adapters)
Reactor JRR-3 JRR-3 JRR-4 JRR-4 JRR-3
- JRR-3 Fuel Standard aluminide Standard silicide Low enrichment High enrichment Follower aluminide Follower silicide
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type type silicide type Instrumented type type type Item
- (HEU)
Nuclide Activity Nuclide Activity Nuclide Activity Nuclide j Activity Nuclide Activity Nuclide Activity (Bq)
(Bq)
(Bq)
(Bq)
(Bq)
(Bq)
Ce-144 6.12x!015 Ce-144 6.0Ix!015 Nb-95 3.54x!015 Cs-137 I 5.02xI013 Ce-144 2.77x.I015 Ce-144 3.84x!015 Quantities of major Pm-147 1.39x101s Pm-147 1.84xJ015 Ce-144 2.38x 1015 Sr-90 J 4.8Ix!013 Pm-I47, 7.8Ix!014 Pm-147 l.l 7x!Ols radionuclides I
I I 4.40xJQl4 Cs-137 j 6.98xJ014
( per package )
Nb-95 l.36XJ015 Cs-137 1.10x101s Zr-95 2.3JxJ015 Y-90 j 4.8JxJ013 Nb-95 Zr-95 6.4IxJ014 Sr-90 l.06xJ015 Y-91 2.03x!015 Kr-85 I 2.46x!012 Cs-137 J 3.85x1014 Sr-90
, 6.76x1014 Cs-137 6.J4xJOl4 Y-90 J.Q6xJOIS Sr-89 l.5JxJ015 Pm-14712.5!x1011 Sr-90 I 3.76xJ014 Y-90 j 6.76xJ014 I
I MNUtype JRR-3 MNUtype Nuclide Activity (Bq)
Cs-137 I 1.79xl014 Pm-147 1.57xl014 Sr-90 1.53x!014 Y-90 I l.53x!014 i
Ce-144 I 2.24x"J013 1~~\\'
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