ML20269A339

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: ML20269A338 ML20269A339
References
Download: ML20269A339 (11)

Text

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1 a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 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 Westinghouse Electric Company, LLC, application Nuclear Fuel Revision No. 15, as supplemented.

Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging (1) Model Nos.: Traveller STD, Traveller XL, 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 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.

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 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)

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 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

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 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

- 176 179 204 - 205 per Assembly No. of Non-Fuel

- 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)

Minimum Fuel

-0.0007 0.3805 0.3439 0.3582 -0.0007 0.3580 Pellet Outer

(-0.0018) (0.9665) (0.8735) (0.9097) (-0.0018) (0.9092)

Diameter (in./cm)

Minimum Cladding

-0.002 0.3855 0.3489 0.3636 -0.002 0.3627 Inner Diameter

(-0.0051) (0.9792) (0.8862) (0.9237) (-0.0051) (0.9214)

(in./cm)

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)

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)

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)

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

- 236 235 264 264 Assembly No. of Non-Fuel Holes - 20 21 25 25

+0.005 0.506 0.485 0.496 0.502 Nominal Pitch (in./cm)

(+0.0127) (1.2852) (1.2319) (1.2598) (1.2751)

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)

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)

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)

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)

(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.

(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 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

+0.0118 0.563 0.500 Nominal Pitch (in./cm)

(+0.0300) (1.430) (1.27)

-0.0007 0.3581 0.3165 Minimum Fuel Pellet OD (in./cm)

(-0.0018) (0.9097) (0.8039)

-0.002 0.3665 0.3236 Minimum Cladding ID (in./cm)

(-0.0051) (0.9310) (0.8220)

Minimum Cladding Thickness -0.002 0.0283 0.0252 (in./cm) (-0.0051) (0.0720) (0.0640)

Maximum Active Fuel Length +0.500 153.54 153.54 (in./cm) (+1.270) (390.00) (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).

(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 VV Bin 1 Tolerance Limit Array Size - 11x21 a No. of Fuel Rods per Assembly - 312 No. of Non-Fuel Holes - 19

+0.001 0.502 Nominal Pitch (in./cm)

(+0.0026) (1.2751)

-0.0005 0.3083 Minimum Fuel Pellet OD (in./cm)

(-0.0013) (0.7831)

-0.0015 0.3125 Minimum Cladding ID (in./cm)

(-0.0051) (0.7938)

Minimum Cladding Thickness -0.0015 0.0210 (in./cm) (-0.0051) (0.0533)

+0.500 143.70 Maximum Active Fuel Length (in./cm)

(+1.270) (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.

(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 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:

Parameter Limit Maximum Enrichment 7.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a 0.308 (0.7823)

Maximum stack length Up to rod container length Zirconium 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).

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.

Maximum number of rods per Rod Pipe Up to Rod Pipe capacity

- Polyethylene packing materials: unlimited quantity in the Rod Pipe.

Wrapping or sleeving

- Materials with hydrogen density less than 0.1325 g/cm3.

Note: a Maximum allowable negative tolerance is -0.0014 in. (-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.

The fuel rods shall meet the parametric requirements given below:

Parameter Limit Maximum Enrichment 5.0 weight percent uranium-235 Minimum Pellet Diameter (in./cm) a 0.3078 (0.7818)

Maximum Pellet Diameter (in./cm) a 0.382 (0.9703)

Maximum stack length Up to Rod Pipe length Zirconium 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 number of rods per Rod Pipe 60 rods

- Polyethylene packing materials unlimited quantity in the Rod Pipe.

Wrapping or sleeving

- Materials with hydrogen density less than 0.1325 g/cm3.

Note: a Maximum allowable 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 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

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 B. Digitally signed by John B.

McKirgan McKirgan Date: 2020.09.29 10:31:30

-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