ML22066B033
| ML22066B033 | |
| Person / Time | |
|---|---|
| Site: | 07109239 |
| Issue date: | 03/09/2022 |
| From: | Yoira Diaz-Sanabria, Bernie White Storage and Transportation Licensing Branch |
| To: | Sloma-Delosier T Westinghouse |
| C ALLEN NRC/NMSS/DFM/STLB 3014156877 | |
| Shared Package | |
| ML22066B031 | List: |
| References | |
| EPID L-2022-RNW-0006 | |
| Download: ML22066B033 (6) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9239 20 71-9239 USA/9239/AF 1
OF 5
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 Columbia Fuel Fabrication Facility 5801 Bluff Road Hopkins, SC 29061 Westinghouse Electric Company, LLC, application, Revision No. 13, dated October 28, 2011, as supplemented.
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.: MCC-3, MCC-4, and MCC-5 (2)
Description The MCC packages are shipping containers for unirradiated uranium oxide fuel assemblies. The packagings consist of a steel fuel element cradle assembly equipped with a strongback and an adjustable fuel element clamping assembly. The cradle assembly is shock mounted to a 13-gauge carbon steel outer container by shear mounts. The MCC-3 container is closed with thirty 1/2-inch T-bolts. The MCC-4 and MCC-5 containers are closed with fifty 1/2-inch T-bolts.
The MCC-3 and MCC-4 containers are permanently equipped with vertical Gd2O3 neutron absorber plates that are mounted on the center wall of the strongback.
Additional horizontal Gd2O3 neutron absorber plates, mounted on the underside of the strongback, are required for the contents as specified.
The MCC-5 container is permanently equipped with both the vertical and horizontal Gd203 neutron absorber plates. Additional vee-shaped, guided Gd203 neutron absorber plates are required for the contents as specified.
Approximate dimensions of the MCC-3 packaging are 441/2 inches O.D. by 1941/2 inches long. The gross weight of the packaging and contents is 7,544 pounds. The maximum weight of the contents is 3,300 pounds.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9239 20 71-9239 USA/9239/AF 2
OF 5
5.
(a)(2)
Packaging (continued)
Approximate dimensions of the MCC-4 packaging are 441/2 inches O.D. by 226 inches long. The gross weight of the packaging and contents is 10,533 pounds. The maximum weight of the contents is 3,870 pounds.
Approximate dimensions of the MCC-5 packaging are 441/2 inches O.D. by 226 inches long. The gross weight of the packaging and contents is 10,533 pounds. The maximum weight of the contents is 3,700 pounds.
(3)
Drawings The MCC-3 packaging is constructed in accordance with Westinghouse Electric Corporation Drawing No. MCCL301, Sheets 1, 2, 3, and 4, Rev. 6.
The MCC-4 packaging is constructed in accordance with Westinghouse Electric Corporation Drawing No. MCCL401, Sheets 1, 2, 3, 4, and 5, Rev. 9.
The MCC-5 packaging is constructed in accordance with Westinghouse Electric Corporation Drawing No. MCCL501, Sheets 1 through 10, Rev. 6.
(b)
Contents (1)
Type and form of material Unirradiated PWR uranium dioxide fuel assemblies with a maximum uranium-235 enrichment of 5.0 weight percent with the following exceptions: 15x15 BW fuel assemblies have a maximum enrichment of 4.65 wt%, and VVER-1000 fuel assemblies have a maximum enrichment of 4.80 wt%.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9239 20 71-9239 USA/9239/AF 3
OF 5
5.
(b)
(1)
Contents (continued)
The fuel assemblies shall meet the specifications given in Westinghouse Drawing No. 6481E15, Rev. 6, and in the following tables of Appendix 1-5 of the application:
Table 1-5.1, Rev. 13 Fuel Assembly Parameters 14x14 Type Fuel Assemblies Table 1-5.2, Rev. 13 Fuel Assembly Parameters 15x15 Type Fuel Assemblies Table 1-5.3, Rev. 13 Fuel Assembly Parameters 16x16 Type Fuel Assemblies**
Table 1-5.4, Rev. 13 Fuel Assembly Parameters 17x17 Type Fuel Assemblies**
Table 1-5.5, Rev. 13 Fuel Assembly Parameters VVER-1000 Type Fuel Assembly***
16x16 CE fuel assemblies and the 17x17 W-STD/XL fuel assemblies shall be shipped only in the Model No. MCC-4 package.
VVER-1000 fuel assemblies shall be shipped only in the Model No. MCC-5 package.
14x14 Type fuel assemblies annular pellet zone length is not restricted and may exceed 6-inches.
15x15 (Type B) OFA fuel assemblies may be modified by replacing seven fuel rods in locations O10 through O15 and N15 with solid stainless steel.
(2)
Maximum quantity of material per package Two (2) fuel assemblies (c)
Criticality Safety Index 0.4 6.
(a)
For shipments of 14x14, 15x15, 16x16, and 17x17 OFA fuel assemblies with U-235 enrichments of over 4.65 wt% and up to 5.0 wt%, horizontal Gd203 neutron absorber plates shall be positioned underneath each assembly. The horizontal absorber plates shall be placed horizontally on the underside of the strongback, as specified in the respective drawings in Condition 5(a)(3) for the MCC-3 and MCC-4 models.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9239 20 71-9239 USA/9239/AF 4
OF 5
6.
(b)
For shipments of 17x17 STANDARD lattice fuel assemblies (17x17 STD and 17x17 XL) with U-235 enrichments of over 4.85 wt% and up to 5.0 wt%, horizontal Gd203 neutron absorber plates shall be positioned underneath each assembly. The horizontal absorber plates shall be placed horizontally on the underside of the strongback, as specified in the respective drawings in Condition 5(a)(3) for the MCC-3 and MCC-4 models.
7.
Shipments of VVER-1000 fuel assemblies are authorized with U-235 enrichments up to 4.80 wt%.
8.
Each fuel assembly must be unsheathed or must be enclosed in an unsealed plastic sheath which may not extend beyond the ends of the fuel assembly. The ends of the sheath may not be folded or taped in any manner that would prevent flow of liquids into or out of the sheathed fuel assembly.
9.
The dimensions, minimum Gd203 loading and coating specifications, and acceptance testing of the neutron absorber plates shall be in accordance with the "Gd203 Neutron Absorber Plates Specifications," Appendix 1-7, Rev. 12, of the application, as supplemented. The minimum Gd203 coating areal density on the vertical and horizontal neutron absorber plates shall be 0.054 g-Gd203/cm2. The minimum Gd203 coating areal density on guided neutron absorber plates shall be 0.027 g-Gd203/cm2.
10.
In addition to the requirements of Subpart G of 10 CFR Part 71:
(a)
Each package shall be prepared for shipment and operated in accordance with the Routine Shipping Container Utilization Summary Operating Procedures, in Chapter 7 of the application; and (b)
Each package shall be tested and maintained in accordance with the Acceptance Tests, Maintenance Program, and Recertification Program, in Chapter 8 of the application, and as specified in the respective drawings in Condition 5(a)(3) for the MCC-3, MCC-4, and MCC-5 models.
11.
Transport by air of fissile material is not authorized.
12.
Fabrication of new packagings is not authorized.
13.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
14.
Revision No. 19 of this certificate may be used until March 31, 2022.
15.
Expiration date: March 31, 2027.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9239 20 71-9239 USA/9239/AF 5
OF 5
REFERENCES Westinghouse Electric Company, LLC, Application For Approval of Packaging Of Fissile Radioactive Material (MCC Shipping Containers), Revision No. 13, dated October 2011.
Supplement dated March 28, 2013, Revision No. 14, August 9, 2016, and March 3, 2022.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: March 9, 2022 White, Bernard signing on behalf of Diaz-Sanabria, Yoira on 03/09/22
ML22066B031; ML22066B033 OFFICE NMSS/DFM/STLB NMSS/DFM/STLB NMSS/DFM/STLB NAME SFigueroa WAllen YDiaz-Sanabria BWhite for DATE Mar 8, 2022 Mar 7, 2022 Mar 9, 2022