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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
{{#Wiki_filter: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 9380                               2                 71-9380             USA/9380/B(U)F-96                     1     OF   19
: 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
: 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.
: c. DOCKET NUMBER
: 3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
: 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                                                            for Certificate of Compliance for the Traveller Columbia Fuel Fabrication Facility                                      PWR Fuel Shipping Package, Revision No. 3.
71-9380 USA/9380/B(U)F-96 1
5801 Bluff Road Hopkins, SC 29061
OF 19
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
: 2.
5.
PREAMBLE
(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 Outerpack, 2) a Clamshell, and 3) a fuel assembly or rod pipe.
: a.
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 is used to mitigate rain and debris from entering the package.
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 for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, Revision No. 3.
: 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 Outerpack, 2) a Clamshell, 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 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 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
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 9380                       2             71-9380       USA/9380/B(U)F-96                 2 OF   19 5.(a)(2)             Description (Continued)
: 1.
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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.
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.
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.
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 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.
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
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 9380                       2             71-9380           USA/9380/B(U)F-96                 3 OF   19 5.(a)(2)             Description (Continued)
: 1.
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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.
There are two models of the Traveller packaging: the Traveller STD and the Traveller XL.
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                     68.8 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.)
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             1,479 kg (3,260 lbs)
Packaging gross weight 1,479 kg (3,260 lbs)
Contents gross weight               893 kg (1,970 lbs)
Contents gross weight 893 kg (1,970 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.)
5.(a)(3)             Drawings The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:
5.(a)(3)
10004E58, Rev. 10 (sheets 1-9) 10071E36, Rev. 5 (sheets 1-9) 10006E58, Rev. 7
Drawings The packagings are fabricated and assembled in accordance with the following Westinghouse Electric Companys Drawing Nos.:
10004E58, Rev. 10 (sheets 1-9) 10071E36, Rev. 5 (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
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 9380                     2                 71-9380             USA/9380/B(U)F-96                 4   OF 19
: 1.
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
71-9380 USA/9380/B(U)F-96 4
OF 19
: 5. (b) Contents (Type and Form of Material)
: 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:
(1)
Parameters for Square Lattice Group 1 Fuel Assemblies Fabrication Fuel Assembly Description                                             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
PWR Group 1 Fuel Assembly (i)
                                                      +0.005                0.580                  0.556              0.563 Nominal Pitch (in./cm)
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:
(+0.0127)             (1.4732)               (1.4122)           (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 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)  
Minimum Fuel Pellet Outer Diameter               -0.0007              0.3805                0.3439              0.3582 (in./cm)                                       (-0.0018)             (0.9665)               (0.8735)           (0.9098)
+0.005
Minimum Cladding Inner Diameter                   -0.002              0.3855                0.3489              0.3636 (in./cm)                                       (-0.0051)             (0.9792)               (0.8862)           (0.9235)
(+0.0127) 0.580 (1.4732) 0.556 (1.4122) 0.563 (1.4300)
Minimum Cladding Thickness                       -0.002              0.0245                0.0228              0.0228 (in./cm)                                       (-0.0051)             (0.0622)               (0.0579)           (0.0579)
Minimum Fuel Pellet Outer Diameter (in./cm)  
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
-0.0007
(-0.0018) 0.3805 (0.9665) 0.3439 (0.8735) 0.3582 (0.9098)
Minimum Cladding Inner Diameter (in./cm)  
-0.002
(-0.0051) 0.3855 (0.9792) 0.3489 (0.8862) 0.3636 (0.9235)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0245 (0.0622) 0.0228 (0.0579) 0.0228 (0.0579)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 136.70 (347.22) 144.00 (365.76) 144.00 (365.76) 14 Bin 1 Rod Pattern 14 Bin 2 Rod Pattern 15 Bin 1 Rod Pattern  


NRC FORM 618                                                                                   U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9380                       2             71-9380             USA/9380/B(U)F-96                 5 OF   19 5.(b)(1)(i)         PWR Group 1 Fuel Assembly (Continued)
: 1.
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
: a. CERTIFICATE NUMBER
                                                                            +0.0118                0.563 Nominal Pitch (in./cm)
: b. REVISION NUMBER
(+0.03)               (1.4300)
: c. DOCKET NUMBER
                                                                            -0.0007                0.3580 Minimum Fuel Pellet OD (in./cm)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(-0.0018)             (0.9092)
71-9380 USA/9380/B(U)F-96 5
                                                                              -0.002                0.3627 Minimum Cladding ID (in./cm)                   (-0.0051)             (0.9214)
OF 19 5.(b)(1)(i)
                                                                              -0.002                0.0265 Minimum Cladding Thickness (in./cm)
PWR Group 1 Fuel Assembly (Continued)
(-0.0051)             (0.0674)
Parameters for Group 1 Fuel Assemblies Fuel Assembly Description Fabrication 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)  
                                                                            +0.500                139.76 Maximum Active Fuel Length (in./cm)
+0.0118
(+1.270)               (355.00) 15 Bin 2 Rod Pattern
(+0.03) 0.563 (1.4300)
Minimum Fuel Pellet OD (in./cm)  
-0.0007
(-0.0018) 0.3580 (0.9092)
Minimum Cladding ID (in./cm)  
-0.002
(-0.0051) 0.3627 (0.9214)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0265 (0.0674)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 139.76 (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
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 9380                         2             71-9380           USA/9380/B(U)F-96                   6 OF 19 5.(b)(1)(i)         PWR Group 1 Fuel Assembly (Continued)
: 1.
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
: a. CERTIFICATE NUMBER
                                                                      +0.005            0.506                0.485 Nominal Pitch (in./cm)
: b. REVISION NUMBER
(+0.0127)         (1.2852)             (1.2319)
: c. DOCKET NUMBER
                                                                      -0.0007          0.3220              0.3083 Minimum Fuel Pellet OD (in./cm)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(-0.00178)         (0.8179)             (0.7831)
71-9380 USA/9380/B(U)F-96 6
                                                                        -0.002          0.3265              0.3125 Minimum Cladding ID (in./cm)
OF 19 5.(b)(1)(i)
(-0.0051)         (0.8293)             (0.7938)
PWR Group 1 Fuel Assembly (Continued)
                                                                        -0.002          0.0210              0.0210 Minimum Cladding Thickness (in./cm)
Parameters for Group 1 Fuel Assemblies Fuel Assembly Description Fabrication 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)  
(-0.0051)         (0.0533)             (0.0533)
+0.005
                                                                      +0.500            150.00              144.00 Maximum Active Fuel Length (in./cm)
(+0.0127) 0.506 (1.2852) 0.485 (1.2319)
(+1.270)         (381.00)             (365.76) 16 Bin 2                               16 Bin 3 Rod Pattern                            Rod Pattern
Minimum Fuel Pellet OD (in./cm)  
-0.0007
(-0.00178) 0.3220 (0.8179) 0.3083 (0.7831)
Minimum Cladding ID (in./cm)  
-0.002
(-0.0051) 0.3265 (0.8293) 0.3125 (0.7938)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.0051) 0.0210 (0.0533) 0.0210 (0.0533)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 150.00 (381.00) 144.00 (365.76) 16 Bin 2 Rod Pattern 16 Bin 3 Rod Pattern  


NRC FORM 618                                                                                     U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9380                         2               71-9380           USA/9380/B(U)F-96                   7 OF 19 5.(b)(1)(i)         PWR Group 1 Fuel Assembly (Continued)
: 1.
Parameters for Group 1 Fuel Assemblies Fabrication Fuel Assembly Description 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
: a. CERTIFICATE NUMBER
                                                                        +0.005            0.496                0.502 Nominal Pitch (in./cm)
: b. REVISION NUMBER
(+0.0127)         (1.2598)             (1.2751)
: c. DOCKET NUMBER
                                                                        -0.0007          0.3083              0.3238 Minimum Fuel Pellet OD (in./cm)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(-0.00178)         (0.7831)             (0.8225)
71-9380 USA/9380/B(U)F-96 7
                                                                          -0.002          0.3125              0.3276 Minimum Cladding ID (in./cm)
OF 19 5.(b)(1)(i)
(-0.00508)         (0.7938)             (0.8321)
PWR Group 1 Fuel Assembly (Continued)
                                                                          -0.002          0.0210              0.0220 Minimum Cladding Thickness (in./cm)
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)  
(-0.00508)         (0.0533)             (0.0559)
+0.005
                                                                        +0.500            168.00              144.00 Maximum Active Fuel Length (in./cm)
(+0.0127) 0.496 (1.2598) 0.502 (1.2751)
(+1.270)         (426.72)             (365.76) 17 Bin 1 / Bin 2 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.
Minimum Fuel Pellet OD (in./cm)  
-0.0007
(-0.00178) 0.3083 (0.7831) 0.3238 (0.8225)
Minimum Cladding ID (in./cm)  
-0.002
(-0.00508) 0.3125 (0.7938) 0.3276 (0.8321)
Minimum Cladding Thickness (in./cm)  
-0.002
(-0.00508) 0.0210 (0.0533) 0.0220 (0.0559)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 168.00 (426.72) 144.00 (365.76) 17 Bin 1 / Bin 2 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.  


NRC FORM 618                                                                             U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9380                       2             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).
: 1.
(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.
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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).
(0.3937 cm and 0.4648 cm).
(v)     Any quantity of stainless steel replacement rods is allowed in the assembly.
(v)
(vi)   Primary neutron sources or other radioactive material are not permitted.
Any quantity of stainless steel replacement rods is allowed in the assembly.
(vii)   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.
(vi)
(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.
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.
(vii)
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
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 9380                       2               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:
: 1.
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
: a. CERTIFICATE NUMBER
                                                              +0.01181            0.563                    0.500 Nominal Pitch (in./cm)
: b. REVISION NUMBER
(+0.0300)           (1.430)                 (1.27)
: c. DOCKET NUMBER
                                                                -0.0007          0.3581                  0.3165 Minimum Fuel Pellet OD (in./cm)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(-0.0018)         (0.9097)                 (0.8039)
71-9380 USA/9380/B(U)F-96 9
                                                                  -0.002          0.3665                  0.3236 Minimum Cladding ID (in./cm)
OF 19 5.(b)(2)
(-0.0051)         (0.9310)                 (0.8220)
PWR Group 2 Fuel Assembly (i)
                                                                  -0.002          0.0283                  0.0252 Minimum Cladding Thickness (in./cm)
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:
(-0.0051)         (0.0720)                 (0.0640)
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)  
                                                                +0.500            153.54                  153.54 Maximum Active Fuel Length (in./cm)
+0.01181
(+1.270)         (390.00)                 (390.00) 16 Bin 1                             18 Bin 1 Rod Pattern                          Rod Pattern
(+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) 16 Bin 1 Rod Pattern 18 Bin 1 Rod Pattern  


NRC FORM 618                                                                             U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9380                       2             71-9380       USA/9380/B(U)F-96               10 OF   19 (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.
: 1.
(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).
: 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. (0.3937 cm and 0.4648 cm).
: b. REVISION NUMBER
(v)     Any quantity of stainless steel replacement rods is allowed in the assembly.
: c. DOCKET NUMBER
(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.
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(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.
71-9380 USA/9380/B(U)F-96 10 OF 19 (ii)
(viii) Primary neutron sources or other radioactive material are not permitted.
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.
(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.
(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.
(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
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 9380                           2                 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:
: 1.
Parameters for Square Lattice Group 4 Fuel Assemblies Fabrication Fuel Assembly Description                                                   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
: a. CERTIFICATE NUMBER
                                                                        +0.005                    0.580                  0.506 Nominal Pitch (in./cm)
: b. REVISION NUMBER
(+0.0127)                 (1.4732)               (1.2852)
: c. DOCKET NUMBER
Minimum Fuel Pellet Outer Diameter                                             0.3805                0.3220 (in./cm)                                                                     (0.9665)               (0.8179)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
Minimum Cladding Inner Diameter                                               0.3855                0.3265 (in./cm)                                                                     (0.9792)               (0.8293)
71-9380 USA/9380/B(U)F-96 11 OF 19 5.(b)(3)
Minimum Cladding Thickness                                                     0.0245                0.0210 (in./cm)                                                                     (0.0622)               (0.0533)
PWR Group 4 Fuel Assembly (i)
Minimum GT/IT Inner Diameter                                                   0.9630                0.5450 (in./cm)                                                                     (2.4460)             (1.3843)
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:
Minimum GT/IT Thickness (in./cm)                                               0.0360                0.0360 (0.0914)             (0.0914)
Parameters for Square Lattice Group 4 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 1 16 Bin 2 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)  
Maximum Active Fuel Length                           +0.500                    136.70                150.00 (in./cm)                                           (+1.270)                 (347.22)               (381.00)
+0.005
Note: a Each GT/IT occupies four non-fuel holes that constitute a 2x2 lattice section.
(+0.0127) 0.580 (1.4732) 0.506 (1.2852)
Minimum Fuel Pellet Outer Diameter (in./cm) 0.3805 (0.9665) 0.3220 (0.8179)
Minimum Cladding Inner Diameter (in./cm) 0.3855 (0.9792) 0.3265 (0.8293)
Minimum Cladding Thickness (in./cm) 0.0245 (0.0622) 0.0210 (0.0533)
Minimum GT/IT Inner Diameter (in./cm) 0.9630 (2.4460) 0.5450 (1.3843)
Minimum GT/IT Thickness (in./cm) 0.0360 (0.0914) 0.0360 (0.0914)
Maximum Active Fuel Length (in./cm)  
+0.500
(+1.270) 136.70 (347.22) 150.00 (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
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 9380                   2             71-9380       USA/9380/B(U)F-96               12     OF 19 5.(b)(3)(i)         PWR Group 4 Fuel Assembly (Continued)
: 1.
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
: a. CERTIFICATE NUMBER
                                              -              179         204                 235             264 Assembly No. of Non-Fuel Holes                 -                17           21                   21             25 Guide Tubes/Instrument
: b. REVISION NUMBER
                                              -                17           21                   21             25 Tubes
: c. DOCKET NUMBER
                                          +0.001            0.556        0.563                0.485          0.496 Nominal Pitch (in./cm)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(+0.0025)         (1.4122)     (1.4300)             (1.2319)       (1.2598)
71-9380 USA/9380/B(U)F-96 12 OF 19 5.(b)(3)(i)
Minimum Fuel Pellet Outer                           0.3439      0.3654              0.3083          0.3083 Diameter (in./cm)                                 (0.8735)     (0.9281)             (0.7831)       (0.7831)
PWR Group 4 Fuel Assembly (Continued)
Minimum Cladding Inner                             0.3489      0.3709              0.3125          0.3125 Diameter (in./cm)                                 (0.8862)     (0.9421)             (0.7938)       (0.7938)
Parameters for Square Lattice Group 4 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 2 15 Bin 3 16 Bin 3 17 Bin 1 Array Size 14x14 15x15 16x16 17x17 No. of Fuel Rods per Assembly 179 204 235 264 No. of Non-Fuel Holes 17 21 21 25 Guide Tubes/Instrument Tubes 17 21 21 25 Nominal Pitch (in./cm)  
Minimum Cladding Thickness                         0.0228      0.0228              0.0210          0.0210 (in./cm)                                           (0.0579)     (0.0579)             (0.0533)       (0.0533)
+0.001
Minimum GT/IT Inner                                 0.3720      0.4970              0.3810          0.3950 Diameter (in./cm)                                 (0.9449)     (1.2624)             (0.9677)       (1.0033)
(+0.0025) 0.556 (1.4122) 0.563 (1.4300) 0.485 (1.2319) 0.496 (1.2598)
Minimum GT/IT Thickness                             0.0147      0.0147              0.0157          0.0137 (in./cm)                                           (0.0373)     (0.0373)             (0.0399)       (0.0348)
Minimum Fuel Pellet Outer Diameter (in./cm) 0.3439 (0.8735) 0.3654 (0.9281) 0.3083 (0.7831) 0.3083 (0.7831)
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)
Minimum Cladding Inner Diameter (in./cm) 0.3489 (0.8862) 0.3709 (0.9421) 0.3125 (0.7938) 0.3125 (0.7938)
Minimum Cladding Thickness (in./cm) 0.0228 (0.0579) 0.0228 (0.0579) 0.0210 (0.0533) 0.0210 (0.0533)
Minimum GT/IT Inner Diameter (in./cm) 0.3720 (0.9449) 0.4970 (1.2624) 0.3810 (0.9677) 0.3950 (1.0033)
Minimum GT/IT Thickness (in./cm) 0.0147 (0.0373) 0.0147 (0.0373) 0.0157 (0.0399) 0.0137 (0.0348)
Maximum Active Fuel Length (in./cm)  
+0.50
(+1.27) 144.00 (365.76) 144.00 (365.76) 144.00 (365.76) 168.00 (426.72)  


NRC FORM 618                                                                             U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9380                       2             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.
: 1.
(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).
: a. CERTIFICATE NUMBER
(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).
: b. REVISION NUMBER
(v)       Any quantity of stainless-steel replacement rods is allowed in the assembly.
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
71-9380 USA/9380/B(U)F-96 13 OF 19 5.(b)(3)(i)
PWR Group 4 Fuel Assembly (Continued) 14 Bin 1 Rod Pattern 16 Bin 2 Rod Pattern 14 Bin 2 Rod Pattern 15 Bin 3 Rod Pattern 16 Bin 3 Rod Pattern 17 Bin 1 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
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 9380                     2             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.
: 1.
(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.
: a. CERTIFICATE NUMBER
(viii)   Primary neutron sources or other radioactive material are not permitted.
: b. REVISION 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.
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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
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 9380                         2             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:
: 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, aluminum, or stainless steel alloy; Zirconium alloy cladding may include a chromium Cladding Material coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
: b. REVISION NUMBER
Including, but not limited to, gadolinia, erbia, boron, Integral absorber and hafnium No limit on length. Inner diameter must be 0.155 in.
: c. DOCKET NUMBER
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.
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
Maximum number of rods per Rod Pipe                 Up to Rod Pipe capacity
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:
                                                                              -    Polyethylene packing materials: unlimited quantity in the Rod Pipe.
Parameter Limit Maximum Enrichment 7.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a 0.308 (0.7823)
Wrapping or sleeving
Maximum stack length Up to rod container length Cladding Material Zirconium, aluminum, or stainless steel alloy; Zirconium alloy cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
                                                                              -    Materials with hydrogen density less than 0.1325 g/cm3.
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.
Note: a Maximum allowable negative tolerance is -0.0014 in. No limit on positive tolerance.
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. 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
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 9380                         2             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.
: 1.
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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:
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, aluminum, or stainless steel alloy; Zirconium alloy cladding may include a chromium Cladding Material coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
Maximum stack length Up to Rod Pipe length Cladding Material Zirconium, aluminum, or stainless steel alloy; Zirconium alloy cladding may include a chromium coating of 25 m thick, nominally and/or include an Optimized ZIRLO Liner (OZL).
Including, but not limited to, gadolinia, erbia, boron, Integral absorber and hafnium No limit on length. Inner diameter must be 0.155 in.
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.
Annular Blanket and 0.183 in. (0.3937 cm and 0.4648 cm).
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
Note: a Maximum allowable negative tolerance is -0.0014 in. No limit on positive tolerance.  
                                                                              -  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
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 9380                         2             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:
: 1.
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.
: a. CERTIFICATE NUMBER
(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.
: b. REVISION NUMBER
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
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
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 Fission Products 4.4 x 105 MeV-Bq/kgU (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 Alpha Activity from Np and Pu Expected to be below the detection limits of commonly used measurement methodology Total Gamma Activity from Fission Products Expected to be below the detection 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
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 9380                       2             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
: 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 application.
: b. REVISION NUMBER
(b)       The package must meet the Acceptance Tests and Maintenance Program in Chapter 8 of the application.
: c. DOCKET NUMBER
(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. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
(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.
71-9380 USA/9380/B(U)F-96 18 OF 19 5.(d)
: 7.         Transport by air of fissile material is not authorized.
Criticality Safety Index (1)
: 8.         The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 71.17.
When transporting Group 1 PWR fuel assemblies as described in 5.(b)(1):
: 9.         Expiration date: April 30, 2027
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.
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
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 9380               2               71-9380       USA/9380/B(U)F-96                   19 OF 19 REFERENCES Safety Analysis Report, Revision No. 3 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9380/B(U)F-96.
: 1.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira K. Diaz-                 Digitally signed by Yoira K. Diaz-Sanabria Sanabria                        Date: 2023.01.26 12:56:41 -05'00' Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: January 26, 2023}}
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2
71-9380 USA/9380/B(U)F-96 19 OF 19 REFERENCES Safety Analysis Report, Revision No. 3 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9380/B(U)F-96.
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: January 26, 2023 Yoira K. Diaz-Sanabria Digitally signed by Yoira K. Diaz-Sanabria Date: 2023.01.26 12:56:41 -05'00'}}

Latest revision as of 12:08, 27 November 2024

Certificate of Compliance No. 9380, Revision No. 2
ML23024A176
Person / Time
Site: 07109380
Issue date: 01/26/2023
From: Yoira Diaz-Sanabria
Storage and Transportation Licensing Branch
To:
Westinghouse
Shared Package
ML23024A175 List:
References
EPID L-2023-LLA-0004
Download: ML23024A176 (1)
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 9380 2

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 Nuclear Fuel Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061 Westinghouse Electric Company, LLC, application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, Revision No. 3.

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 Outerpack, 2) a Clamshell, 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 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 is used to mitigate rain and debris from entering the package.

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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.

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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. 10 (sheets 1-9) 10071E36, Rev. 5 (sheets 1-9) 10006E58, Rev. 7

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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 Fuel Assemblies Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 1 14 Bin 2 15 Bin 1 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

(+0.0127) 0.580 (1.4732) 0.556 (1.4122) 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 (0.9098)

Minimum Cladding Inner Diameter (in./cm)

-0.002

(-0.0051) 0.3855 (0.9792) 0.3489 (0.8862) 0.3636 (0.9235)

Minimum Cladding Thickness (in./cm)

-0.002

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

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 136.70 (347.22) 144.00 (365.76) 144.00 (365.76) 14 Bin 1 Rod Pattern 14 Bin 2 Rod Pattern 15 Bin 1 Rod Pattern

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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 Fuel Assembly Description Fabrication 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

(+0.03) 0.563 (1.4300)

Minimum Fuel Pellet OD (in./cm)

-0.0007

(-0.0018) 0.3580 (0.9092)

Minimum Cladding ID (in./cm)

-0.002

(-0.0051) 0.3627 (0.9214)

Minimum Cladding Thickness (in./cm)

-0.002

(-0.0051) 0.0265 (0.0674)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 139.76 (355.00) 15 Bin 2 Rod Pattern

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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 Fuel Assembly Description Fabrication 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

(+0.0127) 0.506 (1.2852) 0.485 (1.2319)

Minimum Fuel Pellet OD (in./cm)

-0.0007

(-0.00178) 0.3220 (0.8179) 0.3083 (0.7831)

Minimum Cladding ID (in./cm)

-0.002

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

Minimum Cladding Thickness (in./cm)

-0.002

(-0.0051) 0.0210 (0.0533) 0.0210 (0.0533)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 150.00 (381.00) 144.00 (365.76) 16 Bin 2 Rod Pattern 16 Bin 3 Rod Pattern

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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

(+0.0127) 0.496 (1.2598) 0.502 (1.2751)

Minimum Fuel Pellet OD (in./cm)

-0.0007

(-0.00178) 0.3083 (0.7831) 0.3238 (0.8225)

Minimum Cladding ID (in./cm)

-0.002

(-0.00508) 0.3125 (0.7938) 0.3276 (0.8321)

Minimum Cladding Thickness (in./cm)

-0.002

(-0.00508) 0.0210 (0.0533) 0.0220 (0.0559)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 168.00 (426.72) 144.00 (365.76) 17 Bin 1 / Bin 2 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.

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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.

(vii)

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.

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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 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)

+0.01181

(+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) 16 Bin 1 Rod Pattern 18 Bin 1 Rod Pattern

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71-9380 USA/9380/B(U)F-96 10 OF 19 (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 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.

(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.

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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 Tolerance Limit 14 Bin 1 16 Bin 2 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

(+0.0127) 0.580 (1.4732) 0.506 (1.2852)

Minimum Fuel Pellet Outer Diameter (in./cm) 0.3805 (0.9665) 0.3220 (0.8179)

Minimum Cladding Inner Diameter (in./cm) 0.3855 (0.9792) 0.3265 (0.8293)

Minimum Cladding Thickness (in./cm) 0.0245 (0.0622) 0.0210 (0.0533)

Minimum GT/IT Inner Diameter (in./cm) 0.9630 (2.4460) 0.5450 (1.3843)

Minimum GT/IT Thickness (in./cm) 0.0360 (0.0914) 0.0360 (0.0914)

Maximum Active Fuel Length (in./cm)

+0.500

(+1.270) 136.70 (347.22) 150.00 (381.00)

Note: a Each GT/IT occupies four non-fuel holes that constitute a 2x2 lattice section.

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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 Fuel Assembly Description Fabrication Tolerance Limit 14 Bin 2 15 Bin 3 16 Bin 3 17 Bin 1 Array Size 14x14 15x15 16x16 17x17 No. of Fuel Rods per Assembly 179 204 235 264 No. of Non-Fuel Holes 17 21 21 25 Guide Tubes/Instrument Tubes 17 21 21 25 Nominal Pitch (in./cm)

+0.001

(+0.0025) 0.556 (1.4122) 0.563 (1.4300) 0.485 (1.2319) 0.496 (1.2598)

Minimum Fuel Pellet Outer Diameter (in./cm) 0.3439 (0.8735) 0.3654 (0.9281) 0.3083 (0.7831) 0.3083 (0.7831)

Minimum Cladding Inner Diameter (in./cm) 0.3489 (0.8862) 0.3709 (0.9421) 0.3125 (0.7938) 0.3125 (0.7938)

Minimum Cladding Thickness (in./cm) 0.0228 (0.0579) 0.0228 (0.0579) 0.0210 (0.0533) 0.0210 (0.0533)

Minimum GT/IT Inner Diameter (in./cm) 0.3720 (0.9449) 0.4970 (1.2624) 0.3810 (0.9677) 0.3950 (1.0033)

Minimum GT/IT Thickness (in./cm) 0.0147 (0.0373) 0.0147 (0.0373) 0.0157 (0.0399) 0.0137 (0.0348)

Maximum Active Fuel Length (in./cm)

+0.50

(+1.27) 144.00 (365.76) 144.00 (365.76) 144.00 (365.76) 168.00 (426.72)

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71-9380 USA/9380/B(U)F-96 13 OF 19 5.(b)(3)(i)

PWR Group 4 Fuel Assembly (Continued) 14 Bin 1 Rod Pattern 16 Bin 2 Rod Pattern 14 Bin 2 Rod Pattern 15 Bin 3 Rod Pattern 16 Bin 3 Rod Pattern 17 Bin 1 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.

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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.

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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 Cladding Material Zirconium, aluminum, or stainless steel alloy; 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). 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. No limit on positive tolerance.

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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 Cladding Material Zirconium, aluminum, or stainless steel alloy; 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).

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 negative tolerance is -0.0014 in. No limit on positive tolerance.

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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 Fission Products 4.4 x 105 MeV-Bq/kgU (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 Alpha Activity from Np and Pu Expected to be below the detection limits of commonly used measurement methodology Total Gamma Activity from Fission Products Expected to be below the detection limits of the measurement methodology

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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.

Expiration date: April 30, 2027

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b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9380 2

71-9380 USA/9380/B(U)F-96 19 OF 19 REFERENCES Safety Analysis Report, Revision No. 3 - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, NRC Certificate of Compliance USA/9380/B(U)F-96.

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: January 26, 2023 Yoira K. Diaz-Sanabria Digitally signed by Yoira K. Diaz-Sanabria Date: 2023.01.26 12:56:41 -05'00'

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