ML22080A174
| ML22080A174 | |
| Person / Time | |
|---|---|
| Site: | 07109380 |
| Issue date: | 04/07/2022 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | |
| P SAVEROT NRC/NMSS/DFM/STLB 3014157505 | |
| Shared Package | |
| ML22080A171 | List: |
| References | |
| CoC 9380, EPID L-2021-LLA-0102 | |
| Download: ML22080A174 (19) | |
Text
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 1 OF 19
- 2. PREAMBLE
- a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material.
- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
- a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Westinghouse Electric Company, LLC Westinghouse Electric Company, LLC, application Nuclear Fuel Revision No. 2, as supplemented.
Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061
- 4. CONDITIONS
This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
5.
(a) Packaging
(1) Model Nos.: Traveller STD, Traveller XL
(2) Description
The Traveller package is designed to transport fresh uranium or slightly contaminated uranium fuel assemblies with enrichment up to 6.0 weight percent or rods with enrichment up to 7.0 weight percent. The package is designed to carry one fuel assembly or one container for loose rods. The package consists of three components: 1) an O uterpack, 2) a C lamshell,
and 3) a fuel assembly or rod. pipe
The Outerpack serves as the primary impact and thermal protection for the fuel assembly and also provides for lifting, stacking, and tie down during transportation. Two independent impact limiters consist ing of two sections of foam of different densities sandwiched between three layers of sheet metal are integral parts of the Outerpack. Polyethylene foam sheeting may be positioned between the Clamshell and the lower Outerpack to augment shock absorbing characteristics during routine transportation. A weather gasket between the mating surfaces of the upper and lower Outerpack is used to mitigate rain and debris from entering the package.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 2 OF 19
5.(a)(2) Description (Continued)
The purpose of the Clamshell is to protect the contents during routine handling and limit rearrangement of the contents in the event of a transport accident. During routine handling, the Clamshell doors open to load the contents and are secured with multi-point cammed latches and hinge pins. The Clamshell is a part of the confinement system that protects and restrains the fuel assembly or fuel rod pipe contents during all transport conditions. Neutron
absorber plates are installed on the inside surface of the Clamshell along the full length of each main door and the top door.
A rectangular Clamshell is used in both the Traveller STD and XL packages, consisting of an aluminum v extrusion strong back base and two aluminum panel doors, bottom and top end plates, and similar multi-point cammed latch closure mechanism. The Clamshell uses piano-type hinges (continuous hinges) to connect each main door to the strong back. The strong back and bottom plate are lined with a cork rubber pad to cushion and protect the contents during normal handling and transport conditions. The Clamshell is fastened to the lower Outerpack using shock absorbing rubber mounts.
For any shipment of contents that are classified as Type B quantity material, a bottom support spacer/plate is required to be used along with the top axial clamping mechanism configuration, to ensure proper structural support for the fuel assembly during a free drop.
The fuel assembly is positioned on top of the reusable aluminum bottom support spacer/plate, which rests on top of the Clamshell bottom plate (and fuel axial bottom spacer for shorter assemblies) and fits under the fuel assembly bottom nozzle structure. The bottom support spacer/plate is a stiff structure to ensure the fuel assembly bottom nozzle is supported during all transport conditions.
The Traveller package is designed to carry loose rods using a rod pipe. The rod pipe consists of a 15.2 cm (6 in.) standard 304 stainless steel, Schedule 40 pipe, and standard 304 stainless steel closures at each end. The closure is a 0.635 cm (0.25 in.) thick cover secured with Type 304 stainless steel hardware to a flange fabricated from 0.635 cm (0.25 in.) thick plate.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 3 OF 19
5.(a)(2) Description (Continued)
There are two models of the Traveller packaging: the Traveller STD and the Traveller XL.
Traveller STD:
Package gross weight 2,041 kilograms (kg) (4,500 pounds (lbs))
Packaging gross weight 1,293 kg (2,850 lbs)
Contents gross weight 748 kg (1,650 lbs)
Outer dimensions Length 500.4 cm (197 in.)
Width 68.8 cm (27.1 in.)
Height 99.8 cm (39.3 in.)
Traveller XL:
Package gross weight 2,372 kg (5,230 lbs)
Packaging gross weight 1,479 kg (3,260 lbs)
Contents gross weight 893 kg (1,970 lbs)
Outer dimensions Length 574 cm (226.0 in.)
Width 68.8 cm (27.1 in.)
Height 99.8 cm (39.3 in.)
5.(a)(3) Drawings
The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:
10004E58, Rev. 9 (sheets 1-9) 10071E36, Rev. 4 (sheets 1-9) 10006E58, Rev. 7
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 4 OF 19
- 5. (b) Contents (Type and Form of Material)
(1) PWR Group 1 Fuel Assembly
(i) PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent. The parameters of the fuel assemblies that are permitted are as follows:
Parameters for Square Lattice Group 1 Fue l Assemblies
Fuel Assembly Description Fabrication 14 Bin 1 14 Bin 2 15 Bin 1 Tolerance Limit
Array Size - 14 x 14 14 x 14 15 x 15
No. of Fuel Rods per Assembly - 176 179 204
No. of Non-Fuel Holes - 20 17 21
Nominal Pitch (in./cm) +0.005 0.580 0.556 0.563
(+0.0127) (1.4732) (1.4122) (1.4300)
Minimum Fuel Pellet Outer Diameter -0.0007 0.3805 0.3439 0.3582 (in./cm) (-0.0018) (0.9665) (0.8735) (0.9098)
Minimum Cladding Inner Diameter -0.002 0.3855 0.3489 0.3636 (in./cm) (-0.0051) (0.9792) (0.8862) (0.9235)
Minimum Cladding Thickness -0.002 0.0245 0.0228 0.0228 (in./cm) (-0.0051) (0.0622) (0.0579) (0.0579)
Maximum Active Fuel Length +0.500 136.70 144.00 144.00 (in./cm) (+1.270) (347.22) (365.76) (365.76)
14 Bin 1 14 Bin 2 15 Bin 1 Rod Pattern Rod Pattern Rod Pattern
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 5 OF 19
5.(b)(1)(i) PWR Group 1 Fuel Assembly (Continued)
Parameters for Group 1 Fuel Assemblies
Fabrication Fuel Assembly Description Tolerance Limit 15 Bin 2
Array Size - 15x15
No. of Fuel Rods per Assembly - 205
No. of Non-Fuel Holes - 20
Nominal Pitch (in./cm) +0.0118 0.563
(+0.03) (1.4300)
Minimum Fuel Pellet OD (in./cm) -0.0007 0.3580
(-0.0018) (0.9092)
- 0.002 0.3627 Minimum Cladding ID (in./cm) ( - 0.0051) (0.9214)
Minimum Cladding Thickness (in./cm) - 0.002 0.0265
( - 0.0051) (0.0674)
Maximum Active Fuel Length (in./cm) +0.500 139.76
(+1.270) (355.00)
15 Bin 2 Rod Pattern
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 6 OF 19
5.(b)(1)(i) PWR Group 1 Fuel Assembly (Continued)
Parameters for Group 1 Fuel Assemblies
Fabrication Fuel Assembly Description Tolerance Limit 16 Bin 2 16 Bin 3
Array Size - 16x16 16x16
No. of Fuel Rods per Assembly - 236 235
No. of Non-Fuel Holes - 20 21
Nominal Pitch (in./cm) +0.005 0.506 0.485
(+0.0127) (1.2852) (1.2319)
Minimum Fuel Pellet OD (in./cm) -0.0007 0.3220 0.3083
(-0.00178) (0.8179) (0.7831)
Minimum Cladding ID (in./cm) -0.002 0.3265 0.3125
(-0.0051) (0.8293) (0.7938)
Minimum Cladding Thickness (in./cm) -0.002 0.0210 0.0210
(-0.0051) (0.0533) (0.0533)
Maximum Active Fuel Length (in./cm) +0.500 150.00 144.00
(+1.270) (381.00) (365.76)
16 Bin 2 16 Bin 3 Rod Pattern Rod Pattern
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 7 OF 19
5.(b)(1)(i) PWR Group 1 Fuel Assembly (Continued)
Parameters for Group 1 Fuel Assemblies
Fuel Assembly Description Fabrication Tolerance Limit 17 Bin 1 17 Bin 2
Array Size - 17x17 17x17
No. of Fuel Rods per Assembly - 264 264
No. of Non-Fuel Holes - 25 25
Nominal Pitch (in./cm) +0.005 0.496 0.502
(+0.0127) (1.2598) (1.2751)
Minimum Fuel Pellet OD (in./cm) - 0.0007 0.3083 0.3238
( - 0.00178) (0.7831) (0.8225)
Minimum Cladding ID (in./cm) - 0.002 0.3125 0.3276
( - 0.00508) (0.7938) (0.8321)
Minimum Cladding Thickness (in./cm) - 0.002 0.0210 0.0220
( - 0.00508) (0.0533) (0.0559)
Maximum Active Fuel Length (in./cm) +0.500 168.00 144.00
(+1.270) (426.72) (365.76)
17 Bin 1 / Bin 2 Rod Pattern
(ii) For each parameter, the listed fabrication toler ance limit applies to all bins included in the table. For maximum parameters, only the positive tolerance is limited and for minimum parameters, only the negative tolerance is limited.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 8 OF 19
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
(iv) There is no restriction on the length of top and bottom annular blankets. The annular fuel pellet inner diameter in the blanket region must be 0.155 in. and 0.183 in. (0.3937 cm and 0.4648 cm).
(v) Any quantity of stainless steel replacement rods is allowed in the assembly.
(vi ) Primary neutron sources or other radioactive material are not permitted.
(vi i) Polyethylene packing materials are limited to a maximum of 2.0 kg in the Clamshell and may not have a hydrogen density greater than 0.1325 g/cm3.
(viii ) Non-fissile base-plate mounted core components, and spider-body core components, including burnable absorbers, secondary source rods, and axial spacer assemblies, are permitted.
(ix) Fuel rods in any location of the assembly may include ADOPT uranium dioxide pellets that are doped with up to 700 ppm Cr2O3 and up to 200 ppm Al2O3.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 9 OF 19
5.(b)(2) PWR Group 2 Fuel Assembly
(i) PWR uranium dioxide fuel assemblies with a maximum uranium -235 enrichment of 5.0 weight percent. The parameters of the fuel assemblies that are permitted are as follows:
Parameters for Square Lattice Group 2 Fuel Assemblies
Fuel Assembly Description Fabrication 16 Bin 1 18 Bin 1 Tolerance Limit
Array Size - 16x16 18x18
No. of Fuel Rods per Assembly - 236 300
No. of Non-Fuel Holes - 20 24
Nominal Pitch (in./cm) +0.01181 0.563 0.500
(+0.0300) (1.430) (1.27)
Minimum Fuel Pellet OD (in./cm) -0.0007 0.3581 0.3165
(-0.0018) (0.9097) (0.8039)
Minimum Cladding ID (in./cm) -0.002 0.3665 0.3236
(-0.0051) (0.9310) (0.8220)
Minimum Cladding Thickness (in./cm) -0.002 0.0283 0.0252
(-0.0051) (0.0720) (0.0640)
Maximum Active Fuel Length (in./cm) +0.500 153.54 153.54
(+1.270) (390.00) (390.00)
16 Bin 1 18 Bin 1 Rod Pattern Rod Pattern
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F -96 10 OF 19
(ii) For each parameter, the listed fabrication toler ance limit applies to all bins included in the table. For maximum parameters, only the positive tolerance is limited and for minimum parameters, only the negative tolerance is limited.
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
(iv) The length of top and bottom annular blankets is restricted to 50.8 cm (20 in.). The annular fuel pellet inner diameter in the blanket region must be 0.155 in. and 0.183 in. (0.3937 cm and 0.4648 cm).
(v) Any quantity of stainless steel replacement rods is allowed in the assembly.
(vi) Polyethylene packing materials are limited to a maximum of 2.0 kg in the Clamshell and may not have a density greater than 0.1325 g/cm3.
(vi i) Non-fissile base-plate mounted core components, and spider-body core components, including burnable absorbers, secondary source rods, and axial spacer assemblies, are permitted.
(viii ) Primary neutron sources or other radioactive material are not permitted.
(ix) Fuel rods in any location of the assembly may include ADOPT uranium dioxide pellets that are doped with up to 700 ppm Cr2O3 and up to 200 ppm Al2O3.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 11 OF 19
5.(b)(3) PWR Group 4 Fuel Assembly
(i) PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 6.0 weight percent. The parameters of the fuel assemblies that are permitted are as follows:
Parameters for Square Lattice Group 4 Fuel Assemblies
Fuel Assembly Description Fabrication 14 Bin 1 16 Bin 2 Tolerance Limit
Array Size - 14 x 14 16x16
No. of Fuel Rods per Assembly - 176 236
No. of Non-Fuel Holes - 20 20
Guide Tubes/Instrument Tubes - 5a 5a
Nominal Pitch (in./cm) +0.005 0.580 0.506
(+0.0127) (1.4732) (1.2852)
Minimum Fuel Pellet Outer Diameter - 0.3805 0.3220 (in./cm) (0.9665) (0.8179)
Minimum Cladding Inner Diameter - 0.3855 0.3265 (in./cm) (0.9792) (0.8293)
Minimum Cladding Thickness - 0.0245 0.0210 (in./cm) (0.0622) (0.0533)
Minimum GT/IT Inner Diameter - 0.9630 0.5450 (in./cm) (2.4460) (1.3843)
Minimum GT/IT Thickness (in./cm) - 0.0360 0.0360 (0.0914) (0.0914)
Maximum Active Fuel Length +0.500 136.70 150.00 (in./cm) (+1.270) (347.22) (381.00)
Note: a Each GT/IT occupies four non-fuel holes that constitute a 2x2 lattice section.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 12 OF 19
5.(b)(3)(i) PWR Group 4 Fuel Assembly (Continued)
Parameters for Square Lattice Group 4 Fuel Assemblies
Fabrication Fuel Assembly Description Tolerance 14 Bin 2 15 Bin 3 16 Bin 3 17 Bin 1 Limit
Array Size - 14x14 15x15 16x16 17x17
No. of Fuel Rods per - 179 204 235 264 Assembly
No. of Non-Fuel Holes - 17 21 21 25
Guide Tubes/Instrument - 17 21 21 25 Tubes
Nominal Pitch (in./cm) +0.001 0.556 0.563 0.485 0.496
(+0.0025) (1.4122) (1.4300) (1.2319) (1.2598)
Minimum Fuel Pellet Outer - 0.3439 0.3654 0.3083 0.3083 Diameter (in./cm) (0.8735) (0.9281) (0.7831) (0.7831)
Minimum Cladding Inner - 0.3489 0.3709 0.3125 0.3125 Diameter (in./cm) (0.8862) (0.9421) (0.7938) (0.7938)
Minimum Cladding Thickness - 0.0228 0.0228 0.0210 0.0210 (in./cm) (0.0579) (0.0579) (0.0533) (0.0533)
Minimum GT/IT Inner - 0.3720 0.4970 0.3810 0.3950 Diameter (in./cm) (0.9449) (1.2624) (0.9677) (1.0033)
Minimum GT/IT Thickness - 0.0147 0.0147 0.0157 0.0137 (in./cm) (0.0373) (0.0373) (0.0399) (0.0348)
Maximum Active Fuel Length +0.50 144.00 144.00 144.00 168.00 (in./cm) (+1.27) (365.76) (365.76) (365.76) (426.72)
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F -96 13 OF 19
5.(b)(3)(i) PWR Group 4 Fuel Assembly (Continued)
14 Bin 1 16 Bin 2 14 Bin 2 Rod Pattern Rod Pattern Rod Pattern
15 Bin 3 16 Bin 3 17 Bin 1 Rod Pattern Rod Pattern Rod Pattern
(ii) For each parameter, the listed fabrication tolerance limit applies to all bins included in the table. For maximum parameters, only the positive tolerance is limited and for minimum parameters, only the negative tolerance is limited.
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
(iv) The length of top and bottom annular blankets is restricted to 20 in. (50.8 cm). The annular fuel pellet inner diameter in the blanket region must be 0.155 in. and 0.183 in. (0.3937 cm and 0.4648 cm).
(v) Any quantity of stainless-steel replacement rods is allowed in the assembly.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 14 OF 19
(vi) Polyethylene packing materials are limited to a maximum of 2.0 kg in the Clamshell and may not have a density greater than 0.1325 g/cm3.
(vii) Non-fissile base-plate mounted core components, and spider-body core components, including burnable absorbers, secondary source rods, and axial spacer assemblies, are permitted.
(viii) Primary neutron sources or other radioactive material are not permitted.
(ix) Fuel rods in any location of the assembly may include ADOPT uranium dioxide pellets that are doped with up to 700 ppm Cr2O3 and up to 200 ppm Al2O3.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F -96 15 OF 19
5.(b)(3) Loose Uranium Dioxide Fuel Rods
Uranium dioxide (UO2) fuel rods with a maximum uranium-235 enrichment of 7.0 weight percent, and an isotopic composition not exceeding a Type A quantity. Any fuel rod may include ADOPT uranium dioxide pellets that are doped with up to 700 ppm Cr2O3 and up to 200 ppm Al2O3. Fuel rods shall be transported in the Traveller STD and XL package inside a Rod Pipe as specified in Drawing 10006E58. The fuel rods shall meet the parametric requirements given below:
Parameter Limit
Maximum Enrichment 7.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a 0.308 (0.7823)
Maximum stack length Up to rod container length
Zirconium, aluminum, or stainless steel alloy; Cladding Material Zirconium alloy cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
Integral absorber Including, but not limited to, gadolinia, erbia, boron, and hafnium
No limit on length. Inner diameter must be 0.155 in.
and 0.183 in. (0.3937 cm and 0.4648 cm). For Annular Blanket inner diameters >0.183 in. (>0.4648 cm), the inner diameter must be equivalent to no more than 44% of the fuel pellet diameter.
Maximum number of rods per Rod Pipe Up to Rod Pipe capacity
- Polyethylene packing materials: unlimited quantity in the Rod Pipe.
Wrapping or sleeving
- Materials with hydrogen density less than 0.1325 g/cm3.
Note: a Maximum allowable negative tolerance is -0.0014 in. No limit on positive tolerance.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 16 OF 19
5.(b) (4) Loose Uranium Silicide Fuel Rods
Uranium silicide (U3Si2) fuel rods with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. Fuel rods shall be transported in the Traveller STD package inside a Rod Pipe as specified in Drawing 10006E58.
The fuel rods shall meet the parametric requirements given below :
Parameter Limit
Maximum Enrichment 5.0 weight percent uranium - 235 Minimum Pellet Diameter (in./cm) a 0.3078 (0.7818)
Maximum Pellet Diameter (in./cm) a 0.382 (0.9703)
Maximum stack length Up to Rod Pipe length
Zirconium, aluminum, or stainless steel alloy; Cladding Material Zirconium alloy cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
Integral absorber Including, but not limited to, gadolinia, erbia, boron, and hafnium
Annular Blanket No limit on length. Inner diameter must be 0.155 in.
and 0.183 in. (0.3937 cm and 0.4648 cm).
Mimum mr ofoi ods
- mylencking mis uimite qityn the ood mip trapn sleevi
- Misitogen densitys tOcm 3.
ko a Maxim lablgative tolaes -00N4 i ko limitsitive tc
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 17 OF 19
5.(c) Maximum quantity of material per package
(1) PWR fuel assemblies as described in 5.(b)(1), 5.(b)(2) and 5.(b)(3) may only be transported as Type B quantities, if
(i) The material is enriched commercial grade uranium or slightly contaminated uranium with trace quantities limits as specified below:
Content Slightly Contaminated U
232U 0.0500 g/gU
234U 2000 g/gU
236U 25,000 g/gU
99Tc 5 g/gU
Alpha Activity from Np and Pu 3300 Bq/kgU Total Gamma Activity from 4.4 x 105 MeV-Bq/kgU Fission Products
(ii) The bottom support spacer/plate and top axial clamping mechanism configuration, as defined in Section 1.2.1.5.3 of the application, are utilized.
(2) PWR fuel assemblies as described in 5.(b)(1), 5.(b)(2) and 5.(b)(3) and Loose rods in the rod pipe as described in 5.(b)(4) and 5.(b)(5) may be transported as Type A quantities, if
(i) The uranium content meets the unirradiated uranium definition of 10 CFR 71.4, or
(ii) The contents meet the requirements of the Enriched Commercial Grade specification of ASTM C996, specifically the 236U limit (250 g236U/gU) and the total quantity of material does not exceed a Type A quantity.
Content Enriched Commercial Grade
232U 0.0001 g/gU
234U 11.0 x 103 g/g235U
236U 250 g/gU
99Tc 0.01 g/gU Expected to be below the detection Alpha Activity from Np and Pu limits of commonly used measurement methodology Total Gamma Activity from Expected to be below the detection Fission Products limits of the measurement methodology
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 18 OF 19
5.(d) Criticality Safety Index
(1) When transporting Group 1 PWR fuel assemblies as described in 5.(b)(1): 1.0
(2) When transporting Group 2 PWR fuel assemblies as described in 5.(b)(2): 4.2
(3) When transporting Group 4 PWR fuel assemblies as described in 5.(b)(3): 2.5
(4) When transporting loose rods in the rod pipe as described in 5.(b)(4) and 5.(b)(5): 0.7
- 6. In addition to the requirements of Subpart G of 10 CFR Part 71:
(a) The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application.
(b) The package must meet the Acceptance Tests and Maintenance Program in Chapter 8 of the application.
(c) The maximum backfill pressure of the fuel rod shall not exceed 460 psig in a Type A configuration or 275 psig in a Type B configuration.
(d) All Zirconium alloy cladding must have at least a total minimum strain energy of 263 psi-in/in when considering tensile yield strength, ultimate strength, and elongation at failure.
- 7. Transport by air of fissile material is not authorized.
- 8. The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 71.17.
- 9. Revision No. 0 of this certificate may be used until April 30, 2023.
- 10. Expiration date: April 30, 2027
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE
FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 1 71-9380 USA/9380/B(U)F - 96 19 OF 19
REFERENCES
Safety Analysis Report, Revision No. 2 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9380/B(U)F-96. Revision request Letter dated August 2, 2021. Supplement SAR Revision No. 2A, dated March 11, 2022.
Renewal Request Letter dated March 11, 2022.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
Date: April 7, 2022