ML23101A034
| ML23101A034 | |
| Person / Time | |
|---|---|
| Site: | 07103004 |
| Issue date: | 08/16/2020 |
| 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 | |
| ML23100A181 | List: |
| References | |
| Download: ML23101A034 (10) | |
Text
East Building, PHH-23 1200 New Jersey Ave, SE Washington, D.C. 20590 U.S. Department COMPETENT AUTHORITY CERTIFICATION FOR A of Transportation TYPE B(U)F FISSILE RADIOACTIVE MATERIALS PACKAGE DESIGN Pipeline and CERTIFICATE USA/0401/B(U)F-96, REVISION 14 Hazardous Materials Safety Administration REVALIDATION OF JAPANESE COMPETENT AUTHORITY CERTIFICATE J/111/B(U)F-96 The Competent Authority of the United States certifies that the radioactive material package design described in this certificate satisfies the regulatory requirements for a Type B(U)F package as prescribed in the regulations of the International Atomic Energy Agency1 and the United States of America2.
- 1. Package Identification - JMS-87Y-18.5T.
- 2. Package Description and Authorized Radioactive Contents - as described in Japanese Certificate of Competent Authority J/111/B(U)F-96, Revision 2 (attached).
- 3. Criticality - The minimum criticality safety index is 0.0. The maximum number of packages per conveyance is determined in accordance with Table X of the IAEA regulations cited in this certificate.
- 4. General Conditions -
- a. Each user of this certificate must have in his possession a copy of this certificate and all documents necessary to properly prepare the package for transportation. The user shall prepare the package for shipment in accordance with the documentation and applicable regulations.
- b. Each user of this certificate, other than the original petitioner, shall register his identity in writing to the Office of Engineering and Research, (PHH-23), Pipeline and Hazardous Materials Safety Administration, U.S. Department of Transportation, Washington D.C. 20590-0001.
1 "Regulations for the Safe Transport of Radioactive Material, 2012 Edition, No. SSR-6" published by the International Atomic Energy Agency (IAEA),
Vienna, Austria.
2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.
(- 2 -)
CERTIFICATE USA/0401/B(U)F-96, REVISION 14
- c. This certificate does not relieve any consignor or carrier from compliance with any requirement of the Government of any country through or into which the package is to be transported.
- d. Records of Management System activities required by Paragraph 306 of the IAEA regulations1 shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate. Consignors in the United States exporting shipments under this certificate shall satisfy the applicable requirements of Subpart H of 10 CFR 71.
- 5. Special Conditions -
- a. The package is not to be transported by air.
- b. Maximum decay heat per package is 1.5 kilowatts.
- c. Known or suspected failed fuel assemblies and fuel with cladding defects greater than pin holes and hairline cracks are not authorized.
- d. Neutron poison plates in the fuel basket must be constructed in accordance with JAERI document entitled "JMS-87Y-18.5T Package Information" dated June 11, 2003.
- e. For shipments which enter into or transit the United States, all international approvals and revalidations, including Approval of Packaging and Confirmation of Packaging certificates issued by the government of Japan, shall be issued prior to the commencement of transport.
- 6. Marking and Labeling - The package shall bear the marking USA/0401/B(U)F-96 in addition to other required markings and labeling.
- 7. Expiration Date - This certificate expires on September 11, 2023.
Previous editions which have not reached their expiration date may continue to be used.
(- 3 -)
CERTIFICATE USA/0401/B(U)F-96, REVISION 14 This certificate is issued in accordance with paragraph(s) 810 and 816 of the IAEA Regulations and Section 173.472 and 173.473 of Title 49 of the Code of Federal Regulations, in response to the November 2, 2018 petition by Edlow International Company, Washington, DC, and in consideration of other information on file in this Office.
Certified By:
November 16, 2018 William Schoonover (DATE)
Associate Administrator for Hazardous Materials Safety Revision 14 - Issued to endorse Japanese Certificate of Competent Authority No. J/111/B(U)F-96 (Rev.2) dated August 3, 2018.
IDENTIFICATION MARK J/111/B(U) F-96(Rev.2)
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
- Reference of J/111/B(U)F-96 (Rev.2)
Page 1 of 7 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 Material (International Atomic Energy Agency, Safety Standards Seri_es 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/111/B(U)F-96(Rev.2) a..,_qv£J-t ;;> ,. lo I~
Date Ii KazuyaAoki Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval
Page 2 of 7 Pages
- 1. The Competent Authority Identification Mark : J/111/B(U)F*96(Rev. 2)
- 2. Name of Package : JMS*87Y*18.5T
- 3. Type of Package : Type B(U) package containing fissile materials
- 4. Specification of Package (1) Materials of Packaging
( i ) Body & Lid ': Stainless steel
( ii) Basket : Stainless steel, Boral plate (iii) Shock absorber : Stainless steel, Fir-plywood (2) Total Weight of Packaging : 18110 kg or less (3) Outer Dimensions of Packaging
( i ) Outer Diameter : Approximately 1.9 m (ii) Height : Approximately 2.0 m (4) Total Weight of Package : 18440 kg or less (5) Illustration of Package : See the attached Figure
- 5. Specification of Radioactive Contents : See the attached Table
- 6. Description of Containment System Containment system consists of the body, the lid, the vent valve and the drain valve made of the stainless steel.
Silicone rubber is used for contact surface of lid, valves, and valve seat.
- 7. For Package containing Fissile Materials (1) Restrictions on Package
( i ) Restriction Number "N'. : No restriction (ii) Arra:y- of package : No restriction (iii) Criticality Safety lndex(CSI) :o (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 It is assumed in criticality analysis that water will leak into void spaces of inner packaging.
(4) Special FeatUl"es in Criticality Assessment There is no special device.
Page 3 of 7 Pages
- 8. For Type B(M) Packages, a statement regarding prescriptions of Type B(U) Package that do not apply to this Package No application. (This package is Type B(U))
- 9. Assumed Ambient Conditions
( i ) Ambient Temperature Range : -40°C~88°C
( ii) lnsolation Data : Table 12 of IAEA Regulation(No.SSR-6)
- 10. Handling, Inspection and Maintenance (1) Handling Instructions
( i ) Package should be handled carefully in accordance with the schedule and procedures estab*
lished 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 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 Appearance Inspection (ii) Pressure Durability Inspection (iii) Leakage Rate Measurement Inspection (iv) Maintenance ofO-ring, Valve, etc. Used for Containment System
( v) Shielding Inspection (vi) Subcriticality Inspection (vii) Heat Transfer Inspection (viii) Lifting Inspection (3) Actions prior to Shipment The following inspections should be performed prior to shipment.
( i ) Visual Appearance Inspection ( ii) Lifting Inspection (iii) Weight Measurement Inspection (iv) Surface Contamination Measurement Inspection
( v) Radiation Dose Rate Inspection (vi) Subcriticality Inspection (vii) Contents Specification Check Inspection (viii) Surface Temperature Inspection (ix) Leakage Rate Measurement Inspection
( x) Pressure 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.
t1 Page 4 of 7 Pages
- 11. Issue Date and Expiry Date
( i) Issue Date : Sep.12, 2018 (ii) Expiry Date : Sep.11, 2023
Page 5 of 7 Pages Upper shock absorber Bolts for fastening upper shock absorber Frame of access proof surface Lid Bolts for fastening lid Vent plug Lifting lug Tie-downl 0
8N j
Fins Bottom fin Drain valve Bolts for fastening bottom shock absorber Bottom shock absorber Approx. 1900 Figure Illustration of JMS-87Y-18.5T Package (Unit : mm)
Table Specification of contents(l/2)
Group Group1 Group 2 Reactor JMTR JMTR Hie-h Enriched Uranium Fuels(HEU) Medium Enriched Uranium Fuels(MEU)
Type Spent JMTR Standard Fuel JMTR Fuel Followers JMTR Standard Fuel JMTR Fuel Followers Fuel Elements (MEU)
Elements(HEU) (HEU) Elements(MEU)
Number of Spent Fuel Less than or equal to 30 Less than or equal to 30 Elements(element/oackae-e) 235U Initial Enrichment (wt%) Less than or equal to 93.3 Less than or equal to 46.0 Initial Gross Weight of Less than or Less than or Less than or Less than or 235U (g/element) equal to 284.3 eaual to 198.4 eaual to 315.6 eaual to 208. 7 Initial Gross Weight of Less than or Less than or Less than or Less ~han or U (g/element) equal to 307 equal to 214 equal to 719 equal to 475 Fuel Core Uranium-Aluminum Alloy Uranium-Aluminum Dispersion Alloy Material Cladding and Aluminum Alloy Aluminum Alloy Side Plate Burn*up (%) Less than or equal to 40 Less than or equal to 40 Cooling Time (days) More than or equal to 360 More than or equal to 360 Condition Solid Solid Total l.65X10 4 l.16Xl0 4 l.78X10 4 l.18X10 4 95Zr :9.62xl02 95Zr :6.76xl02 95Zr : L02x 103 95Zr :6.79x102 Activity of Con* 95Nb : 1.47x 103 95Nb : 2.08xl03 95Nb : 1.46xl03 95Nb :2.2lxl03 tents Principal (TBq/30 elements) I<<Ce: 4.6lxl03 144Ce: 3.24xl03 l44Ce: 4.98x 103 144Ce: 3.30xl0 3 radionuclide 144Pr:4.6lxl03 144Pr: 3.24xl03 1<<Pr: 4.98xl03 144Pr:3.30xl03 147Pm:9.39Xl02 147Pm:6.60xl02 147Pm: 1.00xl03 147Pm:6.65xl02 Total Heat Generation Rate 1.83 1.29 1.98 1.32 (KW/30 elements)
- Each package shall be loaded with a single fuel (i.e. only kind of "Spent Fuel Elements")or mixed fuels (i.e. two or more kinds of "Spent Fuel Elements") within an identical group. Regardless of the adobe condition, the loading of mixed fuels belonging to the group 2 and group 3 is acceptable up to .30 fuel elements.
In case of loading of mixed fuels, "Activity of contents" and "Total Heat Generation Rate" shall be determined by the proportional distribution.
-. ,* .. ~* * ' ...... t,*
Table Specification of contents(2/2)
Group Group 3 Group 4 Reactor JMTR JRR-3 Low Enriched Uranium Fuels(LEU) Low Enriched Uranium Fuels(LEU)
Typ Spent JMTR Standard Fuel JMTR Fuel Followers JRR-3 Standard-type JRR-3 Follower-type e
Fuel Elements Elements (LEU) (LEU) Fuel Elements Fuel Elements (LEU) (LEU)
Number of Spent Fuel Less than or equal to 30 Less than or equal to 30 Elements(element/packae:e) 235 u Initial Enrichment (wt%) Less than or equal to 19.95 Less than or equal to 19.95 Initial Gross Weight of 235U Less than or Less than or Less than or Less than or (g/element) equal to 450 equal to 302 equal to 315 equal to 205 Initial Gross Weight ofU Less than or Less than or Less than or Less than or (e:/element) eaual to 2338 eaual to 1569 eaual to 1612 eaual to 1049 Fuel Core Uranium-Silicon-Aluminum Dispersion Alloy Uranium-Aluminum Dispersion Alloy Mate-rial Cladding and Aluminum Alloy Aluminum Alloy Side Plate Less than or equal to Less than or equal to Less than or equal to Less than or equal to Burn-up(%) 50 60 50 60 Less than or equal to 50 More than or equal to . More than or equal to More than or equal to More than or equal to Cooling Time (days) 420 540 420 540 More than or equal to 360 Condition Solid Solid Total 2.43xl0 4 2.12X1Q4 l.63x1Q4 1.43X1Q4 l.76X1Q4 l.11X1Q4 95Zr :8.28X102 9DSr : 7.47x102
- 95Zr : 5.56x102 9DSr : 5.04x102 95Zr : 6.64x102 95Zr :4.21Xl02 Activity of 95Nb : 1. 76x 103 9DY :7.47X102 95Nb : l.18X10 3 ooy :5.04x102 95Nb : 1.45xl03 95Nb :9.l 7X102 Contents I<<Ce: 7.41Xl03 137Cs: 7.74x102 I<<Ce: 4.97x 103 137Cs:5.22X102 144Ce: 5.27X103 1<<Ce: 3.34xl03 Principal (TBq/30 ele- 1<<Pr: 5.27x10 3 radionuclide 1<<pr: 7.41x103 144Ce: 6.63x 103 I44Pr:4.97x103 144Ce : 4.47X 103 144Pr: 3.34xl03 ments) 147Pm: l.44Xl0 3 I44Pr: 6.63xl03 147Pm:9.68Xl02 144Pr: 4.47x 103 147Pm:9.58Xl02 147Pm:6.07xl02 I
147Pm: 1.40X103 147Pm: 9.43X 102 Total Heat Generation Rate 2.80 2.40 1.88 1._61 1.94 1.23 *
(KW/30 elements)
- Each package shall be loaded with a single fuel (i.e. only kind of "Spent Fuel Elements")or mixed fuels (i.e. two or more kinds of "Spent Fuel Elements") within an identical group. ~egardless of the adobe condition, the loading of mixed fuels belonging to the group 2 and group 3 is acceptable up to 30 fuel elements.
In case of loading of mixed fuels, "Activity of contents" and "Total Heat Generation Rate" shall be determined by the proportional distribution.
East Building, PHH-23 1200 New Jersey Ave, SE Washington, D.C. 20590 U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration CERTIFICATE NUMBER: USA/0401/B(U)F-96 ORIGINAL REGISTRANT(S):
Edlow International Company 1666 Connecticut Ave, N.W Suite 201 Washington, DC, 20009 USA Department of Energy U.S. Department of Energy 1000 Independence Ave, SW EM-60 Washington, DC, 20585 USA Secured Transportation Services 5210 Palmero Court Suite 107 Buford, GA, 30518 USA 1