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{{#Wiki_filter: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 9297                                 13                 71-9297               USA/9297/AF-96                       1     OF 11
{{#Wiki_filter:NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: 2. PREAMBLE
: a. CERTIFICATE NUMBER
: 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. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 1
OF 11
: 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.
: 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
: 3.
: 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. 15, as supplemented.
THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061
: a.
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
ISSUED TO (Name and Address)
5.
: b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Westinghouse Electric Company, LLC Nuclear Fuel Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061 Westinghouse Electric Company, LLC, application Revision No. 15, as supplemented.
(a) Packaging (1)       Model Nos.: Traveller STD, Traveller XL, Traveller VVER (2)       Description The Traveller package is designed to transport fresh uranium fuel assemblies with enrichment up to 5.0 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 outerpack, 2) a clamshell, and 3) a fuel assembly or rod container.
: 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, Traveller VVER (2)
Description The Traveller package is designed to transport fresh uranium fuel assemblies with enrichment up to 5.0 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 outerpack, 2) a clamshell, and 3) a fuel assembly or rod container.
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 consisting 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 provides a barrier to prevent rain from entering the package.
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 consisting 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 provides a barrier to prevent rain from entering the package.
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
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  


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 9297                         13             71-9297             USA/9297/AF-96                 2 OF   11 5.(a)(2)           Description (Continued) latches and hinge pins. The Clamshell is a part of the confinement system that protects and restrains the fuel assembly or fuel rod tube 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.
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 2
OF 11 5.(a)(2)
Description (Continued) latches and hinge pins. The Clamshell is a part of the confinement system that protects and restrains the fuel assembly or fuel rod tube 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.
There are two general types of clamshells used, a typical rectangular clamshell, and a hexagonal VVER Clamshell. The rectangular clamshell is used in both the Traveller STD and XL packages, with minor differences between the two. The VVER Clamshell is used in the Traveller VVER package. The STD/XL Clamshell consists of an aluminum v extrusion strong back. The VVER Clamshell is similar in build to the STD/XL Clamshell, however it has been designed for the transport of hexagonal fuel assemblies. All clamshell designs consist of an aluminum base and two aluminum panel doors, bottom and top end plates, and similar multi-point cammed latch closure mechanism. The clamshells use 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.
There are two general types of clamshells used, a typical rectangular clamshell, and a hexagonal VVER Clamshell. The rectangular clamshell is used in both the Traveller STD and XL packages, with minor differences between the two. The VVER Clamshell is used in the Traveller VVER package. The STD/XL Clamshell consists of an aluminum v extrusion strong back. The VVER Clamshell is similar in build to the STD/XL Clamshell, however it has been designed for the transport of hexagonal fuel assemblies. All clamshell designs consist of an aluminum base and two aluminum panel doors, bottom and top end plates, and similar multi-point cammed latch closure mechanism. The clamshells use 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.
The Traveller package is designed to carry loose rods using a container or 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.)
The Traveller package is designed to carry loose rods using a container or 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.)
Line 35: Line 53:
There are three models of the Traveller packaging: the Traveller STD, the Traveller XL and the Traveller VVER.
There are three models of the Traveller packaging: the Traveller STD, the Traveller XL and the Traveller VVER.
Traveller STD:
Traveller STD:
Package gross weight               2,041 kilograms (kg) (4,500 pounds (lbs))
Package gross weight 2,041 kilograms (kg) (4,500 pounds (lbs))
Packaging gross weight             1,293 kg (2,850 lbs)
Packaging gross weight 1,293 kg (2,850 lbs)
Contents gross weight             748 kg (1,650 lbs)
Contents gross weight 748 kg (1,650 lbs)
Outer dimensions Length                   500.4 cm (197 in.)
Outer dimensions Length 500.4 cm (197 in.)
Width                   68.6 cm (27.0 in.)
Width 68.6 cm (27.0 in.)
Height                   99.8 cm (39.3 in.)
Height 99.8 cm (39.3 in.)
Traveller XL:
Traveller XL:
Package gross weight               2,372 kg (5,230 lbs)
Package gross weight 2,372 kg (5,230 lbs)
Packaging gross weight             1,476 kg (3,255 lbs)
Packaging gross weight 1,476 kg (3,255 lbs)
Contents gross weight             896 kg (1,975 lbs)
Contents gross weight 896 kg (1,975 lbs)
Outer dimensions Length                   574 cm (226.0 in.)
Outer dimensions Length 574 cm (226.0 in.)
Width                   68.8 cm (27.1 in.)
Width 68.8 cm (27.1 in.)
Height                   99.8 cm (39.3 in.)
Height 99.8 cm (39.3 in.)  


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 9297                       13             71-9297             USA/9297/AF-96                 3 OF   11 5.(a)(2)           Description (Continued)
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 3
OF 11 5.(a)(2)
Description (Continued)
Traveller VVER:
Traveller VVER:
Package gross weight               2,316 kg (5,105 lbs)
Package gross weight 2,316 kg (5,105 lbs)
Packaging gross weight             1,476 kg (3,255 lbs)
Packaging gross weight 1,476 kg (3,255 lbs)
Contents gross weight               840 kg (1,850 lbs)
Contents gross weight 840 kg (1,850 lbs)
Outer dimensions Length                   574 cm (226.0 in.)
Outer dimensions Length 574 cm (226.0 in.)
Width                   68.8 cm (27.1 in.)
Width 68.8 cm (27.1 in.)
Height                   99.8 cm (39.3 in.)
Height 99.8 cm (39.3 in.)
(3)     Drawings The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:
(3)
10004E58, Rev. 9 (sheets 1-9) 10006E58, Rev. 7 10037E43, Rev. 3 (sheets 1-8)
Drawings The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:
10004E58, Rev. 9 (sheets 1-9) 10006E58, Rev. 7 10037E43, Rev. 3 (sheets 1-8)  


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 9297                         13                 71-9297         USA/9297/AF-96                 4   OF 11
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 4
OF 11
: 5. (b) Contents (Type and Form of Material)
: 5. (b) Contents (Type and Form of Material)
(1)     PWR Group 1 Fuel Assembly (i)   Fresh PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
(1)
Parameters for Square Lattice Group 1 Fuel Assemblies Fabrication                                                    Fabrication Fuel Assembly Tolerance           14 Bin 1       14 Bin 2 15 Bin 1         Tolerance     15 Bin 2 Description Limit                                                          Limit Array Size                   -              14 x 14         14 x 14   15 x 15               -        15x15 No. of Fuel Rods
PWR Group 1 Fuel Assembly (i)
                                          -                176             179       204                 -          205 per Assembly No. of Non-Fuel
Fresh PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
                                          -                20             17       21                 -          20 Holes Nominal Pitch             +0.005              0.580          0.556    0.563            +0.0118        0.563 (in./cm)               (+0.0127)           (1.4732)       (1.4122) (1.4300)         (+0.0300)     (1.4300)
Parameters for Square Lattice Group 1 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 1 14 Bin 2 15 Bin 1 Fabrication Tolerance Limit 15 Bin 2 Array Size 14 x 14 14 x 14 15 x 15 15x15 No. of Fuel Rods per Assembly 176 179 204 205 No. of Non-Fuel Holes 20 17 21 20 Nominal Pitch (in./cm)  
Minimum Fuel
+0.005
                                      -0.0007           0.3805          0.3439    0.3582            -0.0007      0.3580 Pellet Outer
(+0.0127) 0.580 (1.4732) 0.556 (1.4122) 0.563 (1.4300)  
(-0.0018)           (0.9665)       (0.8735) (0.9097)         (-0.0018)     (0.9092)
+0.0118
Diameter (in./cm)
(+0.0300) 0.563 (1.4300)
Minimum Cladding
Minimum Fuel Pellet Outer Diameter (in./cm)
                                      -0.002            0.3855          0.3489    0.3636              -0.002     0.3627 Inner Diameter
-0.0007
(-0.0051)           (0.9792)       (0.8862) (0.9237)         (-0.0051)     (0.9214)
(-0.0018) 0.3805 (0.9665) 0.3439 (0.8735) 0.3582 (0.9097)  
(in./cm)
-0.0007
Minimum Cladding          -0.002           0.0245         0.0228    0.0228             -0.002      0.0265 Thickness (in./cm)      (-0.0051)           (0.0622)        (0.0579) (0.0579)          (-0.0051)     (0.0674)
(-0.0018) 0.3580 (0.9092)
Maximum Active           +0.500            136.70          144.00    144.00            +0.500      139.76 Fuel Length (in./cm)     (+1.270)           (347.22)       (365.76) (365.76)           (+1.270)     (355.00)
Minimum Cladding Inner Diameter (in./cm)  
-0.002
(-0.0051) 0.3855 (0.9792) 0.3489 (0.8862) 0.3636 (0.9237)  
-0.002
(-0.0051) 0.3627 (0.9214)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0245 (0.0622) 0.0228 (0.0579) 0.0228 (0.0579)  
-0.002
(-0.0051) 0.0265 (0.0674)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 136.70 (347.22) 144.00 (365.76) 144.00 (365.76)  
+0.500
(+1.270) 139.76 (355.00)  


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 9297                         13             71-9297             USA/9297/AF-96                     5 OF 11 5.(b)(1)(i)           PWR Group 1 Fuel Assembly (Continued)
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
Parameters for Group 1 Fuel Assemblies Fabrication Fuel Assembly Tolerance     16 Bin 2     16 Bin 3         17 Bin 1         17 Bin 2 Description Limit Array Size                       -        16x16         16x16           17x17           17x17 No. of Fuel Rods per
: a. CERTIFICATE NUMBER
                                                      -          236           235             264             264 Assembly No. of Non-Fuel Holes             -            20           21               25               25
: b. REVISION NUMBER
                                                  +0.005        0.506        0.485            0.496            0.502 Nominal Pitch (in./cm)
: c. DOCKET NUMBER
(+0.0127)     (1.2852)     (1.2319)         (1.2598)         (1.2751)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 5
Minimum Fuel Pellet           -0.0007      0.3220        0.3083          0.3083          0.3238 OD (in./cm)                 (-0.0018)     (0.8179)     (0.7831)         (0.7831)         (0.8225)
OF 11 5.(b)(1)(i)
Minimum Cladding ID           -0.002      0.3265        0.3125          0.3125          0.3276 (in./cm)                   (-0.0051)     (0.8293)     (0.7938)         (0.7938)         (0.8321)
PWR Group 1 Fuel Assembly (Continued)
Minimum Cladding               -0.002      0.0210        0.0210          0.0210          0.0220 Thickness (in./cm)         (-0.0051)     (0.0533)     (0.0533)         (0.0533)         (0.0559)
Parameters for Group 1 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 16 Bin 2 16 Bin 3 17 Bin 1 17 Bin 2 Array Size 16x16 16x16 17x17 17x17 No. of Fuel Rods per Assembly 236 235 264 264 No. of Non-Fuel Holes 20 21 25 25 Nominal Pitch (in./cm)  
Maximum Active Fuel           +0.500        150.00        144.00          168.00          144.00 Length (in./cm)             (+1.270)     (381.00)     (365.76)         (426.72)         (365.76)
+0.005
(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.
(+0.0127) 0.506 (1.2852) 0.485 (1.2319) 0.496 (1.2598) 0.502 (1.2751)
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner (OZL).
Minimum Fuel Pellet OD (in./cm)  
(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 0.46482 cm).
-0.0007
(v)   Any quantity of stainless steel or lead-filled replacement rods is allowed in the assembly.
(-0.0018) 0.3220 (0.8179) 0.3083 (0.7831) 0.3083 (0.7831) 0.3238 (0.8225)
(vi)   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.
Minimum Cladding ID (in./cm)  
-0.002
(-0.0051) 0.3265 (0.8293) 0.3125 (0.7938) 0.3125 (0.7938) 0.3276 (0.8321)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0210 (0.0533) 0.0210 (0.0533) 0.0210 (0.0533) 0.0220 (0.0559)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 150.00 (381.00) 144.00 (365.76) 168.00 (426.72) 144.00 (365.76)
(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 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 0.46482 cm).
(v)
Any quantity of stainless steel or lead-filled 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 hydrogen density greater than 0.1325 g/cm3.  


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 9297                       13                 71-9297         USA/9297/AF-96                     6 OF 11 (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.
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
(viii) Primary neutron sources or other radioactive material are not permitted.
: a. CERTIFICATE NUMBER
(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.
: b. REVISION NUMBER
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, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
: c. DOCKET NUMBER
Parameters for Square Lattice Group 2 Fuel Assemblies Fabrication Fuel Assembly Description                                       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
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 6
                                                                +0.0118            0.563                    0.500 Nominal Pitch (in./cm)
OF 11 (vii)
(+0.0300)           (1.430)                   (1.27)
Non-fissile base-plate mounted core components, and spider-body core components, including burnable absorbers, secondary source rods, and axial spacer assemblies, are permitted.
                                                                -0.0007            0.3581                    0.3165 Minimum Fuel Pellet OD (in./cm)
(viii)
(-0.0018)           (0.9097)                 (0.8039)
Primary neutron sources or other radioactive material are not permitted.
                                                                  -0.002          0.3665                    0.3236 Minimum Cladding ID (in./cm)
(ix)
(-0.0051)           (0.9310)                 (0.8220)
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.
Minimum Cladding Thickness                       -0.002          0.0283                    0.0252 (in./cm)                                     (-0.0051)           (0.0720)                 (0.0640)
5.(b)(2)
Maximum Active Fuel Length                     +0.500            153.54                    153.54 (in./cm)                                     (+1.270)           (390.00)                 (390.00)
PWR Group 2 Fuel Assembly (i)
(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.
PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner (OZL).
Parameters for Square Lattice Group 2 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 16 Bin 1 18 Bin 1 Array Size 16x16 18x18 No. of Fuel Rods per Assembly 236 300 No. of Non-Fuel Holes 20 24 Nominal Pitch (in./cm)  
+0.0118
(+0.0300) 0.563 (1.430) 0.500 (1.27)
Minimum Fuel Pellet OD (in./cm)  
-0.0007
(-0.0018) 0.3581 (0.9097) 0.3165 (0.8039)
Minimum Cladding ID (in./cm)  
-0.002
(-0.0051) 0.3665 (0.9310) 0.3236 (0.8220)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0283 (0.0720) 0.0252 (0.0640)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 153.54 (390.00) 153.54 (390.00)
(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 or include an Optimized ZIRLO Liner (OZL).  


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 9297                             13                 71-9297             USA/9297/AF-96                 7 OF   11 (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 0.46482 cm).
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
(v)       Any quantity of stainless steel or lead-filled replacement rods is allowed in the assembly.
: a. CERTIFICATE NUMBER
(vi)     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.
: b. REVISION NUMBER
(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.
: c. DOCKET NUMBER
(viii)   Primary neutron sources or other radioactive material are not permitted.
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 7
(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.
OF 11 (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 0.46482 cm).
(v)
Any quantity of stainless steel or lead-filled 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 hydrogen 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.
5.(b)(3) PWR Group 3 Fuel Assembly (VVER)
5.(b)(3) PWR Group 3 Fuel Assembly (VVER)
(i)       VVER uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
(i)
Parameters for VVER Fuel Assemblies Fuel Assembly Description                         Fabrication VV Bin 1 Tolerance Limit Array Size                                               -                  11x21 a No. of Fuel Rods per Assembly                             -                    312 No. of Non-Fuel Holes                                     -                      19
VVER uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:
                                                                                  +0.001                  0.502 Nominal Pitch (in./cm)
Parameters for VVER Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit VV Bin 1 Array Size 11x21 a No. of Fuel Rods per Assembly 312 No. of Non-Fuel Holes 19 Nominal Pitch (in./cm)  
(+0.0026)               (1.2751)
+0.001
                                                                                  -0.0005                0.3083 Minimum Fuel Pellet OD (in./cm)
(+0.0026) 0.502 (1.2751)
(-0.0013)               (0.7831)
Minimum Fuel Pellet OD (in./cm)  
                                                                                  -0.0015                0.3125 Minimum Cladding ID (in./cm)
-0.0005
(-0.0051)               (0.7938)
(-0.0013) 0.3083 (0.7831)
Minimum Cladding Thickness                           -0.0015                0.0210 (in./cm)                                           (-0.0051)               (0.0533)
Minimum Cladding ID (in./cm)  
                                                                                  +0.500                143.70 Maximum Active Fuel Length (in./cm)
-0.0015
(+1.270)               (365.00)
(-0.0051) 0.3125 (0.7938)
Note: a (shortest row) x (longest row).
Minimum Cladding Thickness (in./cm)  
-0.0015
(-0.0051) 0.0210 (0.0533)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 143.70 (365.00)
Note: a (shortest row) x (longest row).  


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 9297                       13             71-9297         USA/9297/AF-96                 8 OF   11 (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.
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
(iii) All rod cladding must be composed of a Zirconium Alloy. Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner (OZL).
: a. CERTIFICATE NUMBER
(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.
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 8
OF 11 (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 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 0.46482 cm).
(0.3937 cm and 0.46482 cm).
(v)   Any quantity of stainless steel is allowed in the assembly.
(v)
(vi)   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.
Any quantity of stainless steel is allowed in the assembly.
(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.
(vi)
(viii) Primary neutron sources or other radioactive material are not permitted.
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.
(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.  


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 9297                           13             71-9297             USA/9297/AF-96                   9     OF     11 5.(b)(4) 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:
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
Parameter                                                   Limit Maximum Enrichment                               7.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a               0.308 (0.7823)
: a. CERTIFICATE NUMBER
Maximum stack length                             Up to rod container length Zirconium alloy; Cladding may include a Cladding Material                                chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner Including, but not limited to, gadolinia, erbia, Integral absorber 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).
: b. REVISION NUMBER
Annular Blanket                                  For inner diameters >0.183 in. (>0.4648 cm), the inner diameter must be equivalent to no more than 44% of the fuel pellet diameter.
: c. DOCKET NUMBER
Maximum number of rods per Rod Pipe               Up to Rod Pipe capacity
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 9
                                                                          -    Polyethylene packing materials: unlimited quantity in the Rod Pipe.
OF 11 5.(b)(4) 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:
Wrapping or sleeving
Parameter Limit Maximum Enrichment 7.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a 0.308 (0.7823)
                                                                          -    Materials with hydrogen density less than 0.1325 g/cm3.
Maximum stack length Up to rod container length Cladding Material Zirconium alloy; Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner 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).
Note: a Maximum allowable negative tolerance is -0.0014 in. (-0.0036 cm). No limit on positive tolerance
For 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 Wrapping or sleeving Polyethylene packing materials: unlimited quantity in the Rod Pipe.
Materials with hydrogen density less than 0.1325 g/cm3.
Note: a Maximum allowable negative tolerance is -0.0014 in. (-0.0036 cm). 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 9297                           13               71-9297             USA/9297/AF-96                 10 OF   11 5.(b)(5) 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.
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 10 OF 11 5.(b)(5) 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:
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)
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 Pellet Diameter (in./cm) a 0.382 (0.9703)
Maximum stack length                               Up to Rod Pipe length Zirconium alloy; Cladding may include a Cladding Material                                  chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner Including, but not limited to, gadolinia, erbia, Integral absorber boron, and hafnium No limit on length. Inner diameter must be 0.155 Annular Blanket in. and 0.183 in. (0.3937 cm and 0.4648 cm).
Maximum stack length Up to Rod Pipe length Cladding Material Zirconium alloy; Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner 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).
Maximum number of rods per Rod Pipe               60 rods
Maximum number of rods per Rod Pipe 60 rods Wrapping or sleeving Polyethylene packing materials unlimited quantity in the Rod Pipe.
                                                                            -    Polyethylene packing materials unlimited quantity in the Rod Pipe.
Materials with hydrogen density less than 0.1325 g/cm3.
Wrapping or sleeving
                                                                            -    Materials with hydrogen density less than 0.1325 g/cm3.
Note: a Maximum allowable tolerance is +/-0.0014 in. (+/-0.0036 cm).
Note: a Maximum allowable tolerance is +/-0.0014 in. (+/-0.0036 cm).
5.(c)     Criticality Safety Index (1)       When transporting PWR Group 1 fuel assemblies as described in 5.(b)(1):                                 1.0 (2)       When transporting PWR Group 2 fuel assemblies as described in 5.(b)(2):                                 4.2 (3)       When transporting PWR Group 3 fuel assemblies as described in 5.(b)(3):                                 1.0 (4)       When transporting loose rods in the Rod Pipe as described in 5.(b)(4) and 5.(b)(5):                     0.7
5.(c)
Criticality Safety Index (1)
When transporting PWR Group 1 fuel assemblies as described in 5.(b)(1):
1.0 (2)
When transporting PWR Group 2 fuel assemblies as described in 5.(b)(2):
4.2 (3)
When transporting PWR Group 3 fuel assemblies as described in 5.(b)(3):
1.0 (4)
When transporting loose rods in the Rod Pipe as described in 5.(b)(4) and 5.(b)(5):
0.7  


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 9297                     13                 71-9297         USA/9297/AF-96                 11 OF   11
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1
: 6.         In addition to the requirements of Subpart G of 10 CFR Part 71:
: a. CERTIFICATE NUMBER
(a)       The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the Traveller License Application, as supplemented.
: b. REVISION NUMBER
(b)       Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the Traveller License Application, as supplemented.
: c. DOCKET NUMBER
: 7.         The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 71.17.
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 11 OF 11
: 8.         The package is not authorized by this certificate for air transport.
: 6.
: 9.         Revision Nos. 11 and 12 of this certificate may be used until December 31, 2021.
In addition to the requirements of Subpart G of 10 CFR Part 71:
: 10.       Expiration date: March 31, 2025.
(a)
The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the Traveller License Application, as supplemented.
(b)
Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the Traveller License Application, as supplemented.
: 7.
The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 71.17.
: 8.
The package is not authorized by this certificate for air transport.
: 9.
Revision Nos. 11 and 12 of this certificate may be used until December 31, 2021.
: 10.
Expiration date: March 31, 2025.
REFERENCES Safety Analysis Report, Revision No. 15 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9297/AF-96.
REFERENCES Safety Analysis Report, Revision No. 15 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9297/AF-96.
Supplement dated August 14, 2020.
Supplement dated August 14, 2020.
Revision Request Letter dated September 23, 2020.
Revision Request Letter dated September 23, 2020.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION John B.                         Digitally signed by John B.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: September 29, 2020 John B.
McKirgan McKirgan                        Date: 2020.09.29 10:31:30
McKirgan Digitally signed by John B.
                                                                                      -04'00' John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: September 29, 2020}}
McKirgan Date: 2020.09.29 10:31:30  
-04'00'}}

Latest revision as of 18:30, 29 November 2024

Certificate of Compliance No. 9297, Revision No. 13
ML20269A339
Person / Time
Site: 07109297
Issue date: 09/29/2020
From: John Mckirgan
Office of Nuclear Material Safety and Safeguards
To:
Westinghouse
PSaverot NMSS/DFM/STL 301.415.7505
Shared Package
ML20269A337 List:
References
Download: ML20269A339 (11)
v • d • e


Text

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 1

OF 11

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 Nuclear Fuel Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061 Westinghouse Electric Company, LLC, application Revision No. 15, as supplemented.
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, Traveller VVER (2)

Description The Traveller package is designed to transport fresh uranium fuel assemblies with enrichment up to 5.0 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 outerpack, 2) a clamshell, and 3) a fuel assembly or rod container.

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 consisting 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 provides a barrier to prevent rain from entering the package.

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

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 2

OF 11 5.(a)(2)

Description (Continued) latches and hinge pins. The Clamshell is a part of the confinement system that protects and restrains the fuel assembly or fuel rod tube 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.

There are two general types of clamshells used, a typical rectangular clamshell, and a hexagonal VVER Clamshell. The rectangular clamshell is used in both the Traveller STD and XL packages, with minor differences between the two. The VVER Clamshell is used in the Traveller VVER package. The STD/XL Clamshell consists of an aluminum v extrusion strong back. The VVER Clamshell is similar in build to the STD/XL Clamshell, however it has been designed for the transport of hexagonal fuel assemblies. All clamshell designs consist of an aluminum base and two aluminum panel doors, bottom and top end plates, and similar multi-point cammed latch closure mechanism. The clamshells use 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.

The Traveller package is designed to carry loose rods using a container or 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.

There are three models of the Traveller packaging: the Traveller STD, the Traveller XL and the Traveller VVER.

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 68.6 cm (27.0 in.)

Height 99.8 cm (39.3 in.)

Traveller XL:

Package gross weight 2,372 kg (5,230 lbs)

Packaging gross weight 1,476 kg (3,255 lbs)

Contents gross weight 896 kg (1,975 lbs)

Outer dimensions Length 574 cm (226.0 in.)

Width 68.8 cm (27.1 in.)

Height 99.8 cm (39.3 in.)

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 3

OF 11 5.(a)(2)

Description (Continued)

Traveller VVER:

Package gross weight 2,316 kg (5,105 lbs)

Packaging gross weight 1,476 kg (3,255 lbs)

Contents gross weight 840 kg (1,850 lbs)

Outer dimensions Length 574 cm (226.0 in.)

Width 68.8 cm (27.1 in.)

Height 99.8 cm (39.3 in.)

(3)

Drawings The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:

10004E58, Rev. 9 (sheets 1-9) 10006E58, Rev. 7 10037E43, Rev. 3 (sheets 1-8)

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 4

OF 11

5. (b) Contents (Type and Form of Material)

(1)

PWR Group 1 Fuel Assembly (i)

Fresh PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:

Parameters for Square Lattice Group 1 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 1 14 Bin 2 15 Bin 1 Fabrication Tolerance Limit 15 Bin 2 Array Size 14 x 14 14 x 14 15 x 15 15x15 No. of Fuel Rods per Assembly 176 179 204 205 No. of Non-Fuel Holes 20 17 21 20 Nominal Pitch (in./cm)

+0.005

(+0.0127) 0.580 (1.4732) 0.556 (1.4122) 0.563 (1.4300)

+0.0118

(+0.0300) 0.563 (1.4300)

Minimum Fuel Pellet Outer Diameter (in./cm)

-0.0007

(-0.0018) 0.3805 (0.9665) 0.3439 (0.8735) 0.3582 (0.9097)

-0.0007

(-0.0018) 0.3580 (0.9092)

Minimum Cladding Inner Diameter (in./cm)

-0.002

(-0.0051) 0.3855 (0.9792) 0.3489 (0.8862) 0.3636 (0.9237)

-0.002

(-0.0051) 0.3627 (0.9214)

Minimum Cladding Thickness (in./cm)

-0.002

(-0.0051) 0.0245 (0.0622) 0.0228 (0.0579) 0.0228 (0.0579)

-0.002

(-0.0051) 0.0265 (0.0674)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 136.70 (347.22) 144.00 (365.76) 144.00 (365.76)

+0.500

(+1.270) 139.76 (355.00)

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 5

OF 11 5.(b)(1)(i)

PWR Group 1 Fuel Assembly (Continued)

Parameters for Group 1 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 16 Bin 2 16 Bin 3 17 Bin 1 17 Bin 2 Array Size 16x16 16x16 17x17 17x17 No. of Fuel Rods per Assembly 236 235 264 264 No. of Non-Fuel Holes 20 21 25 25 Nominal Pitch (in./cm)

+0.005

(+0.0127) 0.506 (1.2852) 0.485 (1.2319) 0.496 (1.2598) 0.502 (1.2751)

Minimum Fuel Pellet OD (in./cm)

-0.0007

(-0.0018) 0.3220 (0.8179) 0.3083 (0.7831) 0.3083 (0.7831) 0.3238 (0.8225)

Minimum Cladding ID (in./cm)

-0.002

(-0.0051) 0.3265 (0.8293) 0.3125 (0.7938) 0.3125 (0.7938) 0.3276 (0.8321)

Minimum Cladding Thickness (in./cm)

-0.002

(-0.0051) 0.0210 (0.0533) 0.0210 (0.0533) 0.0210 (0.0533) 0.0220 (0.0559)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 150.00 (381.00) 144.00 (365.76) 168.00 (426.72) 144.00 (365.76)

(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 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 0.46482 cm).

(v)

Any quantity of stainless steel or lead-filled 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 hydrogen density greater than 0.1325 g/cm3.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 6

OF 11 (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.

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, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:

Parameters for Square Lattice Group 2 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 16 Bin 1 18 Bin 1 Array Size 16x16 18x18 No. of Fuel Rods per Assembly 236 300 No. of Non-Fuel Holes 20 24 Nominal Pitch (in./cm)

+0.0118

(+0.0300) 0.563 (1.430) 0.500 (1.27)

Minimum Fuel Pellet OD (in./cm)

-0.0007

(-0.0018) 0.3581 (0.9097) 0.3165 (0.8039)

Minimum Cladding ID (in./cm)

-0.002

(-0.0051) 0.3665 (0.9310) 0.3236 (0.8220)

Minimum Cladding Thickness (in./cm)

-0.002

(-0.0051) 0.0283 (0.0720) 0.0252 (0.0640)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 153.54 (390.00) 153.54 (390.00)

(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 or include an Optimized ZIRLO Liner (OZL).

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 7

OF 11 (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 0.46482 cm).

(v)

Any quantity of stainless steel or lead-filled 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 hydrogen 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.

5.(b)(3) PWR Group 3 Fuel Assembly (VVER)

(i)

VVER uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent, with an isotopic composition not exceeding a Type A quantity. The parameters of the fuel assemblies that are permitted are as follows:

Parameters for VVER Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit VV Bin 1 Array Size 11x21 a No. of Fuel Rods per Assembly 312 No. of Non-Fuel Holes 19 Nominal Pitch (in./cm)

+0.001

(+0.0026) 0.502 (1.2751)

Minimum Fuel Pellet OD (in./cm)

-0.0005

(-0.0013) 0.3083 (0.7831)

Minimum Cladding ID (in./cm)

-0.0015

(-0.0051) 0.3125 (0.7938)

Minimum Cladding Thickness (in./cm)

-0.0015

(-0.0051) 0.0210 (0.0533)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 143.70 (365.00)

Note: a (shortest row) x (longest row).

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 8

OF 11 (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 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 0.46482 cm).

(v)

Any quantity of stainless steel 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 hydrogen 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.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 9

OF 11 5.(b)(4) 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 Cladding Material Zirconium alloy; Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner 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).

For 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 Wrapping or sleeving Polyethylene packing materials: unlimited quantity in the Rod Pipe.

Materials with hydrogen density less than 0.1325 g/cm3.

Note: a Maximum allowable negative tolerance is -0.0014 in. (-0.0036 cm). No limit on positive tolerance

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 10 OF 11 5.(b)(5) 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 Cladding Material Zirconium alloy; Cladding may include a chromium coating of 25 m thick, nominally or include an Optimized ZIRLO Liner 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).

Maximum number of rods per Rod Pipe 60 rods Wrapping or sleeving Polyethylene packing materials unlimited quantity in the Rod Pipe.

Materials with hydrogen density less than 0.1325 g/cm3.

Note: a Maximum allowable tolerance is +/-0.0014 in. (+/-0.0036 cm).

5.(c)

Criticality Safety Index (1)

When transporting PWR Group 1 fuel assemblies as described in 5.(b)(1):

1.0 (2)

When transporting PWR Group 2 fuel assemblies as described in 5.(b)(2):

4.2 (3)

When transporting PWR Group 3 fuel assemblies as described in 5.(b)(3):

1.0 (4)

When transporting loose rods in the Rod Pipe as described in 5.(b)(4) and 5.(b)(5):

0.7

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1

a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9297 13 71-9297 USA/9297/AF-96 11 OF 11
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 Traveller License Application, as supplemented.

(b)

Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the Traveller License Application, as supplemented.

7.

The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 71.17.

8.

The package is not authorized by this certificate for air transport.

9.

Revision Nos. 11 and 12 of this certificate may be used until December 31, 2021.

10.

Expiration date: March 31, 2025.

REFERENCES Safety Analysis Report, Revision No. 15 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9297/AF-96.

Supplement dated August 14, 2020.

Revision Request Letter dated September 23, 2020.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: September 29, 2020 John B.

McKirgan Digitally signed by John B.

McKirgan Date: 2020.09.29 10:31:30

-04'00'

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