ML24305A266
| ML24305A266 | |
| Person / Time | |
|---|---|
| Site: | 07109383 |
| Issue date: | 11/15/2024 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | GNS Gesellschaft fur Nuklear-Service mbH |
| Shared Package | |
| ML24305A264 | List: |
| References | |
| EPID L-2021-NEW-0002 CoC 9383, Rev 0 | |
| Download: ML24305A266 (1) | |
Text
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.
- a. CERTIFICATION NUMBER 9383 b.
REVISION NUMBER 0
c.
DOCKET NUMBER 71-9383 d.
PACKAGE IDENTIFICATION NUMBER USA/9383/B(U)F-96 PAGE PAGES 1 OF 5
Enclosure 1 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)
GNS Gesellschaft für Nuklear-Service mbH Frohnhauser Strae 67 45127 Essen Germany b.
TITLE AND IDENTIFICATION OF REPORT OR APPLICATION GNS Report 1014-SR-00001, Rev. 6 Safety Analyses Report Type B(U)F Transport Package CASTOR geo69, dated October 28, 2024.
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 No: CASTOR geo69 (2)
Description The Model No. CASTOR geo69 is a dual-purpose cask design intended for the transport, as a type B(U)F package, of up to 69 undamaged BWR fuel assemblies. The packaging consists of the cask with the cask body and the cask lid enclosing the canister, the fuel basket, and the shielding elements. The packaging includes two impact limiters fastened to the face ends of the cask in order to protect the cask and its content. The cask itself mainly consists of a monolithic cask body made of ductile cast iron that is sealed by the bolted cask lid. The cask body and the cask lid form the outer containment of the radioactive content. Neutron shielding is maintained by two circumferential rows of moderator columns inside the cask body wall and by moderator discs on the cask bottom and lid end. The package has trunnions at the top of the cask and tilting studs toward the bottom.
The canister, which contains the fuel basket and the fuel assemblies, forms the inner containment.
The canister consists of a welded stainless steel shell (canister body), which is sealed by the stainless steel canister lid. The canister components (shell, lid, lid seal, bottom plate) and cask components (body, lid, lid seal) provide a redundant enclosure for the contained spent fuel. The fuel basket consists of a structural skeleton that maintains the subcritical arrangement of the fissile material contained in the fuel assemblies and holds additional components required for heat dissipation and shielding.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.
- a. CERTIFICATION NUMBER 9383 b.
REVISION NUMBER 0
c.
DOCKET NUMBER 71-9383 d.
PACKAGE IDENTIFICATION NUMBER USA/9383/B(U)F-96 PAGE PAGES 2 OF 5
5.(a)(2)
Continued.
During transportation on public roads, the cask is protected by both lid-end and bottom-end impact limiters that cover the trunnions and tilting studs. The impact limiters consist of a steel casing filled with polyurethane foam. The selected materials and protection measures of the packaging are suitable for corrosion protection and decontamination under operating and transport conditions.
The weight of the fully loaded package, including the impact limiters is 148,880 kg (328,224 lbs.).
5.(a)(3)
Drawings The package shall be constructed and assembled in accordance with the following GNS Drawing numbers:
1014-DD-44719, Rev. 1, 1 Sheet CASTOR geo69 Transport Configuration 1014-DD-37023, Rev. 0, 1 Sheet CASTOR geo69 Transport & Storage Cask Assembly 1014-DD-36931, Rev. 0, 1 Sheet CASTOR geo69 Internals Transport & Storage Cask 1014-DD-30934, Rev. 0, 8 Sheets CASTOR geo69 Cask Transport & Storage Cask 1014-DD-36855, Rev. 0, 4 Sheets CASTOR geo69 Canister Internals 1014-DD-30984, Rev. 1, 1 Sheet CASTOR geo69 Basket Internals 1014-DD-33604, Rev. 2, 1 Sheet CASTOR geo69 Shielding Elements Internals 1014-DD-38772, Rev. 1, 4 Sheets CASTOR geo69 Impact Limiter 5.(b)
Contents of Packaging (1)
Type and Form of Material (a)
Undamaged spent BWR UO2 fuel in a fuel basket.
(b)
Non-fuel components integral to a fuel assembly such as fuel channels, spacer grids, end fittings and/or plenum springs.
(c)
The fuel shall not be damaged. Any fuel rod or fuel assembly that cannot meet the pertinent fuel-specific or system-related regulations for the transportation package may not be loaded into the basket. Fuel rods may not contain pinholes, hairline cracks, or gross ruptures. Fuel rod assemblies may have assembly defects if able to meet the pertinent fuel-specific or system-related regulations.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.
- a. CERTIFICATION NUMBER 9383 b.
REVISION NUMBER 0
c.
DOCKET NUMBER 71-9383 d.
PACKAGE IDENTIFICATION NUMBER USA/9383/B(U)F-96 PAGE PAGES 3 OF 5
5(b)(2)
Maximum quantity of material per package:
(a) 69 BWR UO2 fuel assemblies (General Electric (GE) 8x8-1, GE 8x8-2, SPC 8x8-2, GE9B 8x8, GE12 LUA, and ATRIUM-10A) with characteristics described in Table 1.2-12 of the application.
Fuel assemblies may contain unirradiated replacement dummy rods provided they displace equal or greater volume of water. The fuel assemblies are restricted to assembly burnup, enrichment, and cooling times as specified in Table 1.2-12 of the application.
(b)
The combined weight of all fuel assemblies, shall not exceed 22,000 kg (48,502 lbs.).
(c)
The total amount of initial heavy metal shall not exceed the limit listed in Table 1.2-11 of the application.
(d)
Fuel shall be loaded in accordance with one of the thermal requirements loading diagrams shown in Figure 1.2-9 of the application (with general loading schematic defined in Figure 1.2-8) and the maximum decay heat shall not be more than 18.5 kW.
5.(c)
Criticality Safety Index:
0.0 6.
In addition to the requirements of Subpart G of 10 CFR Part 71, the CASTOR geo69 package shall:
(a)
Be prepared for shipment and operate in accordance with the Package Operations in Chapter 7 of the application, (b)
Meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application, (c)
During transport, the fuel baskets aluminum-boron metal matrix composite (Al-B4C-MMC) neutron absorber shall have no contact with the outer environment, (d)
B4C content in the aluminum-boron metal matrix composite (Al-B4C-MMC) shall be in accordance with Section 3, Table 6 of Appendix 2-8, revision 6 of the application, (e)
Mechanical properties of the aluminum-boron metal matrix composite (Al-B4C-MMC) shall be in accordance with Section 3, Table 4 of Appendix 2-8, revision 6 of the application, (f)
Acceptance criteria for uniform boron distribution of the aluminum-boron metal matrix composite (Al-B4C-MMC) shall be in accordance with Section 2.5.2 of Appendix 2-8, revision 6 of the application,
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.
- a. CERTIFICATION NUMBER 9383 b.
REVISION NUMBER 0
c.
DOCKET NUMBER 71-9383 d.
PACKAGE IDENTIFICATION NUMBER USA/9383/B(U)F-96 PAGE PAGES 4 OF 5
6.
Continued.
(g)
Visual inspection criteria for of the aluminum-boron metal matrix composite (Al-B4C-MMC) shall be in accordance with Section 2.6 of Appendix 2-8, revision 6 of the application, (h)
Acceptance criteria for moderator material shall be in accordance with Section 8.1.6.1.2 of the application, (i)
Acceptance criteria for moderator material mechanical properties shall be in accordance with Section 5.2, Table 5-1 of Appendix 2-7, revision 2 of the application, (j)
Acceptance criteria for moderator material thermal properties shall be in accordance with Section 5.2, Table 5-2 of Appendix 2-7, revision 2 of the application, (k)
Acceptance criteria for moderator material chemical composition shall be in accordance with Section 5.2, Table 5-3 of Appendix 2-7, revision 2 of the application, and (l)
All test procedures used in demonstrating compliance with the above requirements shall conform to those in the application.
7.
The package must be transported under exclusive use.
8.
If a personnel barrier is placed over the package, an evaluation will be performed to ensure the barrier does not result in package temperatures above allowable values in the application due to impeded heat transfer.
9.
Prior to transport by rail, the Association of American Railroads must have evaluated and approved the railcar and the system used to support and secure the package during transport.
10.
Prior to marine or barge transport, the National Cargo Bureau, Inc., must have evaluated and approved the system used to support and secure the package to the barge or vessel, and must have certified that package stowage is in accordance with the regulations of the Commandant, United States Coast Guard.
11.
Transport by air is not authorized.
12.
The CASTOR geo69 package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
13.
Expiration Date: November 30, 2029.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.
- a. CERTIFICATION NUMBER 9383 b.
REVISION NUMBER 0
c.
DOCKET NUMBER 71-9383 d.
PACKAGE IDENTIFICATION NUMBER USA/9383/B(U)F-96 PAGE PAGES 5 OF 5
REFERENCES CASTOR geo69 Transportation Package Safety Analysis Report, 1014-SR-00001, Revision No. 6, dated October 28, 2024.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: November 15, 2024 Signed by Diaz-Sanabria, Yoira on 11/15/24