ML23115A077
| 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: |
| References | |
| 001794, EPID L-2023-DOT-0006 | |
| Download: ML23115A077 (9) | |
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--c, mfiO) c :to l'.J fil~ L- ~ T o 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 : JRC-80Y-20T
- 3. Type of Package : Type B(U) package for fissile material
- 4. Specification of Package (1) Materials of Packaging (i) Body and Lid : Stainless steel (ii) Basket : 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 : Approximately 1.9 m (ii) Height : Approximately 2.1 m (4) Total Weight of Package : 23.2 x 103 kg or less (5) Illustration of Package : See the attached Figure-l(Bird's-eye view)
- 5. Specification of Radioactive Contents : See the attached Table-1
. 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.
. 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 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 : -40°C~38°C (ii) Insolation Data : Table 12 of IAEA 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 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 Reference of J/2045/B(U)F Page 3 of 5 Pages
( 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.
- 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)
Reference of J/2045/B(U)F Page 4 of 5 Pages
Protection cover for lid lifting lug
Lid lifting lug Vent valve and Protection cover Lock, Security seal Lid bolt, Lock, Security seal and Antirotation key
Double O*ring
Fin Centering pin 0
N Drain hole N Package lifting lug N Body(Shielding)
Tie down bolt Tie down device Drain valve and Protection cover with fin Lock, Security seal
Lifting device ( All dimensions in mm)
Figure-I Illustration of JRC-80Y-20T Package l::tl (D tti"' 1--j (D :::i () (D 0 t-1') ~ ~ 0 ~ CJ1 ----t:r.::I,,......._ 1-:rj
l-1j >l:l (fQ (D CJ1 0 t-1') CJ1 l-1j >l:l (fQ s (D r:,;,
14 14 14 13 10 uranium less less less less Fuel less or or less more 1 or 14 orless 1.79xI0 1.57xI0'4 l.53x l.53xI0 2.24x10 or 0.72 or or or I 0 MNUtype Spent 160 natural 61.2 23 1,360 8,500 2,190 7.24x -9 0 -90 9.33xl0 Cs-137 Pm-147 Sr Y Ce-144 Metallic
elements).
fuel 15 15 14 14 14 type alloy less 10 type aluminum less less less Fuel less less type or less or less more 3 or 16 or 3.84xl0 I.17x!0 6.98xlQ 6.76x 6.76xl0 silicide or or Solid or or or Contents Spent 40 20 silicon.44 310 60 x l 0 9 0 0 63 1,586 600 l.43xI0 1.33 -9 ( except MNU more.
Follower dispersion Ce-144 Pm-147 Cs-137 Sr-Y or Uranium Radioactive together is 1 Gy/h tolerance.
of
contained package fabrication 100 be the
15 15 15 15 can of U))x Specification type alloy 10 contains 235 aluminum less less type of 1 fuel less less type less less less less more 6.0ixI0 1.84xI0 1.1ox10ts l.06x10 l.06x surface silicide or or or or or or or 3 or 10 16 or the which weight Spent 40 20 silicon 60 I 0 silicide Table-99.24 485 2,481 600 9 0 -90 from value Standard dispersion 2.24x 2.09x Ce-144 Pm-147 Cs-137 Sr-Y (Initial Uranium Follower away upper U)-;-
and an 1 m 235 type shows of
silicide weight IJ at a position t) major Il 1 > of air specification fuel activity to depletion 2 > Standard rate State /package) Total (Bq/package) radionuclides (Bq/package) of nuclear ((All Element elements(piece) nuclear 235U(g/piece) ofU(g/piece) time(day) Quantities dose =
fuel of of the Fuel of enrichment(%) Physical Burnup(3/4) heat(W elements in mass mass Cooling of up(%)
Initial Material weight(kg/package) Decay fuel absorbed value U Total The The The Burn Number Total Contents 1) 2)
Activity Note.
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