ML24332A060
| ML24332A060 | |
| Person / Time | |
|---|---|
| Site: | 07109225 |
| Issue date: | 12/19/2024 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | Baldner H NAC International |
| Shared Package | |
| ML24332A059 | List: |
| References | |
| EPID L-2024-LLA-0144 | |
| Download: ML24332A060 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Heath Baldner, Director, Licensing, Engineering NAC International, Inc.
Atlanta Corporate Headquarters 2 Sun Court, Suite 220 Peachtree Corners, GA 30092
SUBJECT:
REVISION 76 OF CERTIFICATE OF COMPLIANCE NO. 9225 FOR THE MODEL NO. NAC INTERNATIONAL, INC.-LEGAL WEIGHT TRUCK PACKAGE
Dear Heath Baldner:
By letters dated September 20, 2024, and October 4, 2024 (Agencywide Documents Access and Management System [ADAMS] Accession Nos. ML24264A126 and ML24278A118, respectively), NAC International, Inc., (NAC) requested an amendment and renewal to Certificate of Compliance (CoC) No. 9225 for the Model No. NAC-Legal Weight Truck (LWT) package. NAC requested an amendment to revised drawings to incorporate fabrication related improvements of the TRIGA Fuel basket for the LWT system.
The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 71.17, General License: NRC-Approved Package and 49 CFR 173.471.
In accordance with 10 CFR 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter will be available electronically for public inspection in the U.S. Nuclear Regulatory Commissions (NRC) Public Document Room (PDR) or from the Publicly Available Records component of the NRCs ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The PDR is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.
December 19, 2024
H. Baldner 2
If you have any questions regarding this CoC, please contact Nishka Devaser of my staff at 301-415-5196.
Sincerely, Yoira Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9225 EPID No. L-2024-LLA-0144
Enclosures:
1.
CoC No. 9225, Rev. No. 75 2.
Safety Evaluation Report cc w/encls. 1& 2: R. Boyle, DOT Julia Shenk, DOE c\\o L. F. Gelder Signed by Diaz-Sanabria, Yoira on 12/19/24
H. Baldner 3
SUBJECT:
REVISION 76 OF CERTIFICATE OF COMPLIANCE NO. 9225 FOR THE MODEL NO. NAC INTERNATIONAL, INC.-LEGAL WEIGHT TRUCK PACKAGE DOCUMENT DATE:
DISTRIBUTION:
DFM r/f NMSS r/f 71sf9225all@listmgr.nrc.gov 71sf9225coc@listmgr.nrc.gov SHelton, NMSS ADimitriadis, R-I BDesai, R-II DHills, R-III GWarnick, R-IV Closes EPID Nos. L-2024-LLA-0144 ADAMS Accession Package Nos.: ML24332A059 (pkg); ML24332A060 (ltr & encl 2);
ML24332A061 (encl 1)
OFFICE NMSS/REFS NMSS/DFM NMSS/DFM NMSS/DFM NMSS/DFM NAME NDevaser SFigueroa JSmith TBoyce YDiaz-Sanabria DATE 11/29/2024 12/2/2024 12/2/2024 12/2/2024 12/19/2024 OFFICIAL RECORD COPY December 19, 2024
Enclosure 2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 71-9225 Model No. NAC-LWT Package Certificate of Compliance No. 9225 Revision No. 76
SUMMARY
By letters dated September 20, 2024, and October 4, 2024 (Agencywide Documents Access and Management System Accession Nos. ML24264A126, non-public and ML24278A119, non-public, respectively), NAC International, Inc., (NAC, or the applicant) requested an amendment and renewal to Certificate of Compliance (CoC) No. 9225 for the Model No. NAC-Legal Weight Truck (LWT) package. NAC requested an amendment to revised drawings to incorporate fabrication related improvements of the TRIGA Fuel basket for the LWT system. The U.S.
Nuclear Regulatory Commission (NRC) staff reviewed the amendment requests using guidance in NUREG-2216, Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material, dated August 2020 (ML20234A651).
Following staff review of the associated safety analysis reports (SAR), the staff finds that the requested changes do not affect the ability of the package to meet the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71, Packaging and Transportation of Radioactive Material.
EVALUATION 1.0 GENERAL INFORMATION 1.1 Packaging Description The NAC-LWT is a Type B(U)F-96 radioactive material transportation packaging design. It is authorized to transport several types of contents, including light-water reactor spent fuel, research reactor spent fuel, and high enriched uranyl nitrate liquid in containers specifically designed for the liquid. The NAC-LWT package may be shipped by truck, boat, or railcar and depending on the content, within an international shipping organization container.
1.2 Drawings The applicant has proposed changes to the following drawings:
315-40-070, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Base Module 315-40-071, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Intermediate Module 315-40-072, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Top Module
2 2.0 STRUCTURAL EVALUATION The objective of the structural evaluation is to verify that the applicant has adequately evaluated the structural performance of the package (packaging together with contents) and demonstrated that it meets the regulations in 10 CFR Part 71.
2.1 Description of Changes The applicant has proposed changes to several chamfer fabrication tolerances and weld callouts at locations in the vicinity of the cask drain line radial notch-out for the NAC-LWT TRIGA fuel basket sections. The proposed changes are reflected in chapter 1 of revision 24E of the SAR and are illustrated on the proposed drawing revisions (see section 1.2 of this safety evaluation report).
2.1.1 Chamfer and weld callout changes The applicant is proposing the same type of changes to the plate chamfer fabrication tolerance callouts and the guide bar welding callouts on the three drawings corresponding to the three portions of the TRIGA fuel baskets cited above. The proposed changes affect the fuel basket sections support plate, mid plate, base plate and full-length guide bars welded to and situated between these plates. Staff notes that the mid plate is only present in the top module section of the fuel basket.
The proposed changes in some of the chamfer callouts is to move the fabrication tolerance allowance from the depth of the chamfer specified to the angle of the chamfer specification. In the remainder of the chamfer callout changes, a depth of chamfer tolerance is added where no tolerance was previously specified. As described in SAR section 2.6.12.7, the chamfers in the support, mid and base plates around the existing radial notch-out, and the presence of the guide bars, serve to provide alignment guidance of the baskets around the existing drain line in the transportation cask. Chamfers are made along the perimeter of the radial notch-outs, in the top and bottom surfaces of the support, mid and base plates of each basket section, to allow a smoother basket insertion into the transportation cask. Chamfers are also made for the same reason at the corners of the guide bars that are welded adjacent to the radial notch-outs. The changes in these chamfer callouts do not appreciably reduce the thickness of the support and bottom plates or the area of the nonstructural guide bars. A review of SAR sections 2.6.12.7 and 2.7.7.9, which address TRIGA fuel basket structural evaluation for drop conditions, indicates that any reduction of the plate thickness at the location of the radial notch-out does not affect the outcome of the structural evaluations presented therein.
The change in weld callout at both ends of the guide bars does not reduce the deposition of weld around the perimeter of each guide bar at its junction with each plate. The revised callout allows more fabrication flexibility to provide either a structural fillet or bevel weld at one face of the guide bar and seal welds at the remaining faces.
The staff reviewed the proposed fabrication callout changes and determined that, since they do not appreciably decrease the thicknesses of the guide bars and top, mid and base plates, and do not decrease the weld size of the nonstructural guide bars, they have no effect on the structural integrity of the fuel baskets.
3
2.2 Evaluation Findings
The staff reviewed the proposed changes summarized above and has the following findings:
Drawings submitted with the application provide a sufficiently detailed description of the changes of the TRIGA fuel baskets, thus meeting the requirements of 10 CFR Part 71.33.
Based on a review of the SAR for the structural evaluation of the basket components affected by the proposed changes, staff concludes that the revised package meets the structural integrity requirements of 10 CFR Part 71.35.
Based on review of the statements and representations in the application, the NRC staff concludes that the package has been adequately described and evaluated to demonstrate that it satisfies the structural integrity requirements of 10 CFR Part 71.
CONDITIONS The following changes have been made to the certificate:
Condition No. 5(a)(3)(ii), Drawings, was updated to reflect the latest revision (revision 7) of LWT 315-40-070, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Base Module, LWT 315-40-071, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Intermediate Module, and LWT 315-40-072, Rev 7, Weldment, 7 Cell Basket, TRIGA Fuel Top Module Condition No. 20, updated to include authorizing use of revision 75 of the certificate.
Condition No. 22 has been updated to certify use of the package for an additional five years.
The references section has been updated to include the current applications as supplements.
CONCLUSION Based on the statements and representations in the applications, as supplemented, and the conditions listed above, the staff concludes that the Model No. NAC-LWT package design has been adequately described and evaluated, and that these changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.
Issued with CoC No. 9225, Revision No. 76.